Component Category: any or undefined
264 documents found
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About the behavior of Zirconium hydride solid bodies under reactor irradiation Ueber das Verhalten von Zirkonhydridmassivkoerpern unter Reaktorbestrahlung
Greiner, L.;Paetz, P.;Staubwasser, WINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--35 - German - 1965
Key words: getr reactor;irradiation;knk-2 reactor;metallography;microhardness;microstructure;moderators;neutron fluence;radiation effects;temperature range 0400-1000 k;zirconium hydrides
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087401.pdf
SNEAK-4, a series of physics experiments for KNK II
Engelmann, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK--1022 - English - 1969
Key words: comparative evaluations;control rod worths;critical mass;doppler effect;experimental data;fuel assemblies;knk-2 reactor;power distribution;reactivity coefficients;reactor physics;sneak reactor;theoretical data
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087738.pdf
Development work for the moderator of the ITR-fuel Entwicklungsarbeiten zum ITR-Brennstoff-Moderator
Duenner, P.;Becker, DINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--73.42 - German - 1973
Key words: burnup;dido reactor;fission product release;fuel pellets;hydration;irradiation;knk-2 reactor;materials testing;thermionic reactors;uranium;yttrium hydrides;zirconium hydrides
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087419.pdf
Diverse shutdown systems for the KNK-1, KNK-2, and SNR-300 reactors
Morgenstern, F.H.;Buchholz, H.;Krueger, H.;Roehrs, H. (INTERATOM, Bensberg, Ger.)CONF-740401--P3 - English - 1974
Key words: knk reactor;knk-2 reactor;performance;reactor protection systems;reactor shutdown;snr reactor;specifications
R&D Category: Reactor physics
display the document: 06169206.pdf
Operating experience and design criteria of sodium valves
Markford, D. (INTERATOM, Bensberg, Ger.)CONF-740964-- - English - 1974
Key words: knk reactor;knk-2 reactor;performance;reactor cooling systems;snr reactor;sodium;valves
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 06201858.pdf
Statistical hot spot analysis of reactor cores Statistische Heisstellenanalyse von Reaktorkernen
Schaefer, HINTERATOM GmbH, Bergisch Gladbach (Germany)
IA-ITB--74.26 - German - 1974
Key words: boundary conditions;hot channel factor;hot channel;hot spot factor;knk-2 reactor;mathematical models;power distribution;reactor cores;statistics;temperature distribution
R&D Category: Reactor physics
display the document: 34087420.pdf
KNK II: Supply of the Compact Sodium Cooled Reactor Plant with a fast core (Final report for the experimental tasks of the project oriented R and D program) KNK II: Ausruestung der Kompakten Natriumgekuehlten Kernreaktoranlage mit einem Schnellen Kern (Abschliessender Bericht ueber die Versuchsvorhaben des projektgebundenen F und E Programms)
INTERATOM GmbH, Bergisch-Gladbach (Germany)IA-INTAT--75.89 - German - 1975
Key words: experiment planning;fuel assemblies;knk-2 reactor;performance testing;reactor physics;reactor safety fuses;reactor shutdown;research programs;scram
R&D Category: any or undefined
display the document: 34087409.pdf
INTERATOM Program: Program DLS
GroenefeldInternationale Atomreaktorbau G.m.b.H. (INTERATOM), Bensberg/Koeln (Germany, F.R.)
ORNL-tr--4007 - English - 1976
Key words: cavities;computer codes;d codes;fortran;knk-2 reactor;neutron transport;shielding;two-dimensional calculations
R&D Category: -Analytic and numeric methods
display the document: 08305027.pdf
The carbide fuel element for the reload of the KNK-II. Das Karbid-Brennelement fuer die KNK II-Nachladung
Bojarsky, E. (Kernforschungszentrum Karlsruhe (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung)KFK--2416 - German - 1976
Key words: comparative evaluations;fuel elements;knk-2 reactor;plutonium carbides;pressure drop;specifications;testing;uranium carbides
R&D Category: Reactor physics
display the document: 08335294.pdf
The SNR-Cores: KNK-II, SNR-300 up to SNR-2. Die SNR-Kerne - KNK-II, SNR-300 bis SNR-2
Hoechel, J. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))KFK--2416 - German - 1976
Key words: fuel management;knk-2 reactor;planning;reactor cores;snr reactor;snr-2 reactor;specifications;steel-din-1-4970
R&D Category: any or undefined
display the document: 08335299.pdf
Heat transfer calculations on the KNK II emergency cooling system Waermetechnische Rechnungen zum KNK II Notkuehlsystem
Vossebrecker, H.;Groenefeld, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--76.130 - German - 1976
Key words: after-heat removal;boiling points;eccs;heat transfer;knk-2 reactor;natural convection;reactor cores;reactor vessels;safety analysis;sodium
R&D Category: Safety aspects
display the document: 34087422.pdf
Basic concept and design data of a nuclear sodium boiling experiments in KNK II Grundkonzept und Auslegungsdaten eines nuklearen Na-Siedeversuches in KNK
Edelmann, MKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--1.24.3/5 - German - 1976
Key words: boiling detection;calculation methods;design;feasibility studies;knk-2 reactor;measuring instruments;sodium;thermal hydraulics
R&D Category: Safety aspects
display the document: 34087743.pdf
Status of the USSR fast reactor programme as of March 1977
Krasnojarov, N.V.;Inyutin, E.IIWGFR--18 - Russian - 1977
Key words: belgium;coordinated research programs;federal republic of germany;knk reactor;knk-2 reactor;lmfbr type reactors;netherlands;snr reactor
R&D Category: any or undefined
display the document: 09363511.pdf
Documentation of the SILOE experiments results (Experiment S2) Dokumentation der SILOE Ergebnisse (Versuch S2)
Glauner, W.;Plitz, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--1210 - German - 1977
Key words: coolant loops;failed element detection;fission product release;fuel element failure;international cooperation;knk-2 reactor;reactor safety experiments;siloe reactor
R&D Category: -Failure detection
display the document: 34086307.pdf
Compact sodium cooled nuclear power plant with fast core (KNK II- Karlsruhe), Safety Report Kompakte natriumgekuehlte Kernreaktoranlage mit schnellem Kern (KNK II- Karlsruhe), Sicherheitsbericht
INTERATOM GmbH, Bergisch-Gladbach (Germany)IA-INTAT--78.7 - German - 1977
Key words: design;fuel assemblies;heat transfer;knk-2 reactor;radiation protection;reactivity coefficients;reactor accidents;reactor cooling systems;reactor cores;reactor licensing;reactor safety;safety analysis;safety reports
R&D Category: any or undefined
display the document: 34087410.pdf
KNK II Second Core - Feasibility Study IIa KNK II Nachladung - Durchfuehrbarkeitsstudie IIa
INTERATOM GmbH, Bergisch Gladbach (Germany)INIS-DE-IA--082 - German - 1977
Key words: burnup;design;feasibility studies;fuel assemblies;knk-2 reactor;power distribution;reactivity coefficients;reactor cores;reactor licensing;thermal hydraulics
R&D Category: any or undefined
display the document: 34087475.pdf
Safety aspects about the installation of a nuclear boiling generator in KNK II Sicherheitstechnische Gesichtspunkte beim Einsatz eines nuklearen Siedegenerators in KNK II
Mitzel, FKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--01.24.3/11 - German - 1977
Key words: boiling detection;creep;engineered safety systems;in core instruments;knk-2 reactor;reactivity coefficients;safety analysis;stress analysis;thermal fatigue
R&D Category: Safety aspects
display the document: 34087741.pdf
Transfer functions between the central fuel temperature, the cladding temperature and the power of fuel assemblies Uebertragungsfunktionen zwischen der zentralen Brennstofftemperatur und der Huellrohrtemperatur sowie der Leistung von Brennelementen
Ferranti, P.;Mitzel, FKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--01.24.9/3 - German - 1977
Key words: boiling detection;calculation methods;fuel elements;heat transfer;in core instruments;knk-2 reactor;temperature monitoring;transfer functions
R&D Category: -Analytic and numeric methods
display the document: 34087742.pdf
Feasibility study of a sodium boiling experiment at KNK II at nuclear power Studie zur Durchfuehrbarkeit eines Na-Siedeversuchs in der KNK II mit nuklearer Leistung
Edelmann, M.;Artz, D.;Bestenreiner, G.;Dorr, B.;Erhardt, J.;Hoppe, P.;Huber, F.;Kempe, H.;Mitzel, F.;Reimann, G.;Ricken, E.;Schaefer, L.;Schleisiek, K.;Schwarz, M.;Seitz, H.;Steinbock, K.;Vaeth, W.;Venker, H.;Zihla, WKernforschungszentrum Karlsruhe GmbH (Germany), INTERATOM;Bergisch-Gladbach (Germany)
KFK-INR--01.24.3 - German - 1977
Key words: boiling detection;experiment planning;feasibility studies;flow blockage;fuel elements;knk-2 reactor;sodium
R&D Category: Safety aspects
display the document: 34087740.pdf
Instrumentation, threshold and signal processing for the nuclear boiling generator of KNK II Instrumentierung, Grenzwerte und Signalverarbeitung fuer den nuklearen Siedegenerator an KNK II
Erhardt, J.;Hoppe, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--1.24.3/7 - German - 1977
Key words: boiling detection;data processing;feasibility studies;flowmeters;knk-2 reactor;neutron detectors;reactor monitoring systems;reactor safety;signal conditioning;thermocouples
R&D Category: Safety aspects
display the document: 34087744.pdf
Thermal-hydraulic and hydrodynamic investigations for the nuclear boiling generator in KNK II Thermohydraulische und hydrodynamische Untersuchungen fuer den nuklearen Siedegenerator KNK II
Dorr, B.;Schleisiek, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-IRE--5/01.24.3/75/77 - German - 1977
Key words: boiling detection;bubble growth;flow blockage;in core instruments;knk-2 reactor;reactor cooling systems;temperature distribution;thermal hydraulics;transfer functions
R&D Category: Thermo hydraulics in all operating, shut-down and accident regimes
display the document: 34087746.pdf
Detection of local sodium boiling in the nuclear boiling generator in KNK II and in the cores of SNR 300 and SNR 2 Nachweis von lokalem Na-Sieden im nuklearen Siedegenerator an der KNK II sowie im Core des SNR 300 und SNR 2
Erhardt, J.;Hoppe, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--1.24.3/9 - German - 1977
Key words: boiling detection;knk-2 reactor;neutron flux;reactor monitoring systems;reactor noise;reactor safety;snr reactor;snr-2 reactor
R&D Category: Safety aspects
display the document: 34087745.pdf
Assessment of the design of oxidic fuels and acceptance criteria for fuel elements (KNK 2, KWO). Beurteilung der Auslegungen von oxidischen Brennstoffen und Abnahmekriterien fuer Brennelemente (KNK 2, KWO)
Beisswenger, H.;Brodt, F. (Technischer Ueberwachungs-Verein Baden e.V., Karlsruhe (Germany, F.R.))AED-Conf--78-114 - German - 1978
Key words: fuel pellets;inspection;knk-2 reactor;mixtures;obrigheim reactor;performance;plutonium dioxide;quality control;reactor licensing;uranium dioxide
R&D Category: Reactor physics
display the document: 09402072.pdf
Status of fast breeder reactor development in the Federal Republic of Germany, Belgium and the Netherlands
Daeunert, U. (Bundesministerium fuer Forschung und Technologie, Bonn (Germany));Kessler, G. (Kernforschungszentrum Karlsruhe, Karlsruhe (Germany))IWGFR--24-2 - English - 1978
Key words: computer codes;construction;criticality;federal republic of germany;fluid mechanics;fuel elements;fuel-cladding interactions;international cooperation;knk-2 reactor;performance testing;reactor commissioning;reactor core disruption;reactor materials;reactor safety;snr reactor;verification
R&D Category: any or undefined
display the document: 32008089.pdf
On-line gamma spectroscopy system for observation of the cover gas of KNK II, description and instruction Messplatz on-line Gammaspektroskopie zur Schutzgasueberwachung an der KNK II, Beschreibung und Betriebsanleitung
Hoffmann, G.;Letz, K.DKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P02A - German - 1978
Key words: activity levels;cover gas;failed element detection;failed element monitors;gamma spectroscopy;knk-2 reactor;on-line systems;performance testing;reactor safety
R&D Category: -Failure and failure propagation mechanisms
display the document: 34086277.pdf
Out-of-pile experiments with an electrical boiler for Acoustic Boiling Detection Out-of-pile Experimente mit einem elektrischen Siedegenerator zur akustischen Siededetektion
Aberle, J.;Bartholomay, R.;Reimann, G.;Rohrbacher, H.A.;Schleisiek, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P01A - German - 1978
Key words: acoustic measurements;boiling detection;flow blockage;knk-2 reactor;reactor accidents;sodium;test facilities;thermal conduction;thermodynamics
R&D Category: any or undefined
display the document: 34086288.pdf
Influence of fuel pin bowing on the temperature distribution in fuel pin cladding tubes in case of sodium cooling. Experimental results Einfluss der Stabverbiegung auf die Temperaturverteilung in Brennstabhuellrohren bei Natriumkuehlung - Experimentelle Ergebnisse -
Moeller, R.;Tschoeke, H.;Kolodziej, MKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.23P01D - German - 1978
Key words: bowing;deformation;design;fuel assemblies;knk-2 reactor;sodium;temperature distribution;testing;thermal hydraulics;turbulent flow
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34086298.pdf
Concepts of annular fuel elements for installation of irradiation inserts in KNK II and layout of a carbide test bundle Konzepte ringfoermiger Brennelemente zur Aufnahme von Bestrahlungseinsaetzen in KNK II und Entwurf eines Karbidkleinbuendels
Haefner, H.E.;Philipp, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.03.02P03C - German - 1978
Key words: annular fuel elements;fuel assemblies;fuel pins;knk-2 reactor;mixed carbide fuels;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;specifications
R&D Category: Reactor physics
display the document: 34086299.pdf
The behavior of the fuel pins of the fuel element NY 205 of KNK II Zum Verhalten der Staebe des Brennelementes NY 205 aus der KNK II
Goetzmann, OKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.11.03P02A - German - 1978
Key words: burnup;cladding;corrosion;fission products;fuel element failure;fuel pins;knk-2 reactor;performance testing;post-irradiation examination;spacers;swelling
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34086301.pdf
Local coolant flow perturbations in KNK II - coolant inlet blockages of assemblies of the test and driver zone Lokale Kuehlflusstoerungen in KNK II - Kuehlmitteleinlaufblockaden von Elementen der Test- und Treiber-zone
Duesing;Friedel;GerlingINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--70.670.4 - German - 1978
Key words: boiling;flow blockage;fluid flow;knk-2 reactor;loss of flow;reactor accidents;risk assessment;safety analysis;scram;sodium
R&D Category: Safety aspects
display the document: 34087395.pdf
Nuclear startup of the Compact Sodium Cooled Nuclear Power Plant KNK II, Zero Power Tests Nukleare Inbetriebnahme der Kompakten Natriumgekuehlten Kernreaktoranlage KNK II, Nulleistungspruefungen
Feltes, W.;Richard, H.;Schmidt-Hoenow, M.;Stroemich, A.;Wilhelm, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--78.48 - German - 1978
Key words: comparative evaluations;control elements;control rod worths;experimental data;knk-2 reactor;reactivity coefficients;reactor fueling;reactor start-up;sodium;theoretical data;void coefficient
R&D Category: Reactor physics
display the document: 34087423.pdf
KNK II, Compact Sodium-Cooled Reactor in the Nuclear Research Center Karlsruhe
INTERATOM GmbH, Bergisch-Gladbach (Germany)INIS-DE-IA--013 - English - 1978
Key words: construction;knk-2 reactor;program management;reactor cores;reactor licensing;reactor operation;safety analysis;training
R&D Category: any or undefined
display the document: 34087474.pdf
Nuclear startup of the compact sodium-cooled nuclear power plant KNK II, zero power tests Nukleare Inbetriebnahme der Kompakten Natriumgekuehlten Kernreaktoranlage KNK II, Nulleistungspruefungen
Richard, H.;Schmidt-Hoenow, M.;Feltes, W.;Stroemich, A.;Wilhelm, HKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH Bergisch-Gladbach (DE)
INIS-DE-KBG--013 - German - 1978
Key words: calculation methods;comparative evaluations;control rod worths;criticality;design;experimental data;knk-2 reactor;reactivity coefficients;reactor cores;reactor safety;reactor start-up;temperature coefficient
R&D Category: Reactor physics
display the document: 34087483.pdf
The KNK II test program Das KNK II Versuchsprogramm
Kathol, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.04P00A - German - 1978
Key words: fuel cycle;knk-2 reactor;materials testing;post-irradiation examination;reactor instrumentation;research programs
R&D Category: any or undefined
display the document: 34087763.pdf
Axial fission rate distribution in SNEAK 11A Axiale Spaltratenverteilung in SNEAK 11A
Moellendorff, U. von;Henneges, GKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P02E - German - 1978
Key words: fission;knk-2 reactor;neutron diffusion equation;nuclear reaction kinetics;plutonium 239;reactor cores;reactor fueling;reactor kinetics;sneak reactor;spatial distribution;two-dimensional calculations;uranium 235;uranium 238;zero power reactors
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087773.pdf
Investigations concerning gas entrainment at KNK II. Untersuchungen zum Gaseintrag an KNK II
Hoppe, P.;Massier, H.;Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--2867 - German - 1979
Key words: entrainment;fluctuations;gases;knk-2 reactor;reactivity;reactor commissioning;reactor operation;reactor start-up;valves
R&D Category: Commissioning and start-up testing, rise to power, transient testing
display the document: 11514378.pdf
Status of the DEBENE fast breeder reactor development, March 1979
Daeunert, U.;Kessler, GIWGFR--30-2 - English - 1979
Key words: cladding;fuel elements;knk-2 reactor;measuring methods;performance testing;radiation effects;reactor components;reactor core disruption;reactor cores;reactor safety;snr reactor;sodium;stainless steels;technology assessment
R&D Category: any or undefined
display the document: 33014309.pdf
Design report for core assemblies of KNK II: Driver zone assemblies with moderator Auslegungsbericht fuer Kernelemente KNK II: Treiberzonenelemente mit Moderator
Huesken, J.;Fenneker, K.;Singer, J.;Zihla, W.;Coors, DINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.01910.8 - German - 1979
Key words: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;safety standards;specifications;zirconium hydrides
R&D Category: Reactor physics
display the document: 34085694.pdf
Design report for core assemblies KNK II/2: Secondary shutdown assemblies Auslegungsbericht fuer Kernelemente KNK II/2: Zweitabschaltelemente
Koenigsdorf, E.;Huesken, J.;Schmitz, K.J.;West, G.;Zolti, EINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.03541.1 - German - 1979
Key words: boron carbides;calculation methods;design;knk-2 reactor;neutron absorbers;reactor shutdown;scram rods
R&D Category: Reactor physics
display the document: 34085700.pdf
Design report for core assemblies KNK II/2: Standard control assemblies and control assemblies with test pins Auslegungsbericht fuer Kernelemente KNK II/2: Standard-Regeltrimmelemente und Regeltrimmelemente mit Versuchsstaeben
Ricken, E.;Schmitz, K.J.;West, G.;Sperber, F.;West, G.;Zolti, EINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.04177.9 - German - 1979
Key words: boron carbides;burnable poisons;burnup extension;calculation methods;control elements;europium borides;europium oxides;fuel cycle;knk-2 reactor;neutron absorbers;reactor cores;reactor safety;scram rods
R&D Category: Reactor physics
display the document: 34085703.pdf
Detection of the first fuel pin failure in KNK II Detektion des ersten defekten Brennstabs in der KNK II
Hoffmann, G.;Jacobi, S.;Jonatzke, O.;Letz, K.D.;Schmitz, GKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P22A - German - 1979
Key words: defects;delayed neutron analysis;failed element detection;fuel element failure;fuel pins;gamma spectroscopy;knk-2 reactor;neutron detection;on-line control systems;reactor safety
R&D Category: -Failure detection
display the document: 34086280.pdf
Measurement and calculation of the reactivity-to-power transfer function of KNK II for the examination of the reactivity coefficients of the first core Messung und Berechnung der Reaktivitaets-Leistungs-Uebertragungsfunktion von KNK II zur Ueberpruefung von Reaktivitaetskoeffizienten der Erstbeladung
Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P09A - German - 1979
Key words: bowing;comparative evaluations;experimental data;knk-2 reactor;power coefficient;reactivity coefficients;theoretical data;transfer functions
R&D Category: Reactor physics
display the document: 34086290.pdf
Vibration measurements at KNK II Schwingungsmessungen an KNK II
Hoppe, P.;Massier, H.;Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P05D - German - 1979
Key words: fuel assemblies;knk-2 reactor;mechanical vibrations;neutron detectors;performance testing;reactor cores;reactor noise;sodium;strains;transducers
R&D Category: Safety aspects
display the document: 34086289.pdf
Investigations of gas entrainment in KNK II Untersuchungen zum Gaseintrag an KNK II
Hoppe, P.;Massier, H.;Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P25A - German - 1979
Key words: bubbles;entrainment;gases;knk-2 reactor;performance testing;reactivity insertions;reactor accidents
R&D Category: Safety aspects
display the document: 34086291.pdf
Detection of local cooling disturbances in the core of SNR 300 by Delayed Neutron Detection DND and by fuel element outlet temperature surveillance Detektion lokaler Kuehlungsstoerungen im Kern des SNR 300 durch DND-System und Ueberwachung der Brennelementaustrittstemperatur
Schleisiek, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.19P21A - German - 1979
Key words: delayed neutron analysis;dryout;flow blockage;fuel element failure;knk-2 reactor;neutron detection;reactor accidents;snr reactor;sodium;temperature monitoring
R&D Category: Safety aspects
display the document: 34086297.pdf
The irradiation of carbide fuel pins in the frame of the Fast Breeder Project Die Bestrahlung von Karbid-Brennstaeben im Rahmen des PSB
Steiner, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.03.03P23C - German - 1979
Key words: burnup;carburization;cladding;fuel pellets;irradiation;knk-2 reactor;mixed carbide fuels;physical radiation effects
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34086300.pdf
Investigation of different reactor protection systems Untersuchung verschiedener Reaktorschutzsysteme
Eggenberger, O.;Gmeiner, L.;Nehmer, J.;Racke, W.;Voges, UKernforschungszentrum Karlsruhe GmbH (Germany)
PSB--01.02.19P23A - German - 1979
Key words: computerized control systems;fast reactors;knk-2 reactor;performance testing;reactor protection systems;thermal reactors
R&D Category: Safety aspects
display the document: 34086370.pdf
Test of In-core Flux Detectors in KNK II
Hoppe, P.;Mitzel, FKernforschungszentrum Karlsruhe GmbH (Germany)
INIS-DE-PSB--010 - English - 1979
Key words: in core instruments;ionization chambers;knk-2 reactor;neutron detectors;neutron monitors;performance testing;self-powered gamma detectors
R&D Category: any or undefined
display the document: 34087494.pdf
KNK II - JOYO Information Exchange, Proceedings of the 3rd Expert-Meeting
Kernforschungszentrum Karlsruhe GmbH (Germany)INIS-DE-KFK--014 - English - 1979
Key words: boiling detection;bubbles;entrainment;international cooperation;joyo reactor;knk-2 reactor;reactor components;reactor cores;reactor operation
R&D Category: any or undefined
display the document: 34087491.pdf
Subcritical experiments in SNEAK 11B1 Unterkritische Experimente in SNEAK 11B1
Henneges, G.;Moellendorff, U. vonKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P02F - German - 1979
Key words: comparative evaluations;control elements;control rod worths;experimental data;fuel elements;knk-2 reactor;neutron absorbers;reactivity insertions;sneak reactor;subcritical assemblies;theoretical data;zero power reactors
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087774.pdf
On-line gamma spectroscopy measuring station for cover gas monitoring at KNK II
Hoffmann, G.;Letz, K.DKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--2797 - English - 1980
Key words: automation;cover gas;failed element monitors;fuel cans;gamma spectrometers;ge semiconductor detectors;knk-2 reactor
R&D Category: -Failure detection
display the document: 11536175.pdf
Simulation of fuel element thermal hydraulics for sensitive monitoring of coolant flow
Edelmann, M. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik)GRS--19 - English - 1980
Key words: disturbances;flow blockage;flow rate;knk-2 reactor;loss of flow;reactor control systems;reactor noise;temperature control
R&D Category: Thermo hydraulics in all operating, shut-down and accident regimes
display the document: 13665581.pdf
Annual meeting on nuclear technology 1980. Technical meeting: Operating experiences. Jahrestagung Kerntechnik 1980. Fachsitzung: Betriebserfahrungen
Deutsches Atomforum e.V., Bonn (Germany, F.R.)INIS-mf--10622 - German - 1980
Key words: availability;avr reactor;isar reactor;knk-2 reactor;obrigheim reactor;performance;phenix reactor;philippsburg-2 reactor;radiation protection;radioactive effluents;reactor operation
R&D Category: any or undefined
display the document: 18052413.pdf
Operating experiences with the KNK-2 reactor. Betriebserfahrungen mit KNK II
Brudermueller, G. (Kernkraftwerk-Betriebsgesellschaft m.b.H., Eggenstein-Leopoldshafen (Germany, F.R.))INIS-mf--10622 - German - 1980
Key words: bubbles;cover gas;failed element detection;knk-2 reactor;reactor maintenance;reactor operation;scram
R&D Category: any or undefined
display the document: 18052719.pdf
Pin, assembly and core design for the extended residence time of the first core of KNK II Stab-, Element-, und Kernauslegung fuer den verlaengerten Betrieb des Erstkerns der KNK II
Fenneker, K.;Menssen, R.;Ricken, E.;Spenke, H.;Sperber, F.;Wehmann, U.;West, GINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--33.02587.1 - German - 1980
Key words: burnup extension;configuration;design;fuel assemblies;fuel pins;knk-2 reactor;reactor cores
R&D Category: Reactor physics
display the document: 34085695.pdf
Development of an absorber pin with diving bell Entwicklung eines Absorberstabes mit Tauchglocke
Dreyer, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.03724.4 - German - 1980
Key words: boron carbides;boron;degassing;fuel elements;interstitial helium generation;knk-2 reactor;neutron absorbers;performance testing;research programs;snr reactor
R&D Category: Reactor physics
display the document: 34085701.pdf
KNK II, MTE II design report, temperature distribution KNK II, MTE II-Auslegungsbericht, Temperaturverteilung
Puetz, HINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--33.02637.0 - German - 1980
Key words: calculation methods;design;fuel elements;knk-2 reactor;temperature distribution;thermal hydraulics
R&D Category: Reactor physics
display the document: 34085696.pdf
Release of fission products from the KNK II fuel element failure and search for released fuel in the primary sodium Freisetzung von Spaltprodukten aus dem KNK II-Brennelementschaden und aktivierungsanalytische Suche nach ausgetragenem Brennstoff im Primaernatrium
Hanke, H.-D.;Clauss, H.;Stamm, H.-HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P24B - German - 1980
Key words: after-heat removal;antimony 124;cesium 136;cesium 137;defects;delayed neutron analysis;fission product release;fuel element failure;iodine 131;knk reactor;knk-2 reactor;neutron activation analysis;neutron detection;primary coolant circuits;silver 110;sodium;testing;zinc 65
R&D Category: -Failure and failure propagation mechanisms
display the document: 34086281.pdf
Investigations of the gas passage through the reactor core of KNK II Untersuchungen zu den Gasdurchlaeufen durch den Reaktorkern KNK II
Hoechel, J.;Schott, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--75.01284.1 - German - 1980
Key words: entrainment;fuel elements;gases;knk-2 reactor;reactivity insertions;reactor cores;reactor operation
R&D Category: Safety aspects
display the document: 34087407.pdf
Model experiments for the problem of the gas storage and gas transport in the KNK reactor Modellversuche zum Problem der Gasspeicherung und des Gastransports im KNK-Reaktor
Voj, P.;Granner, N.;Penny, WINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--53.03970.1 - German - 1980
Key words: entrainment;gases;knk-2 reactor;reactivity meters;reactivity;reactor start-up;sodium
R&D Category: Safety aspects
display the document: 34087403.pdf
Safety related investigations for the second and third operation period of KNK II Sicherheitstechnische Untersuchungen fuer die zweite und dritte Betriebsperiode der KNK II
Friedel, G.;Groenefeld, G.;Lenzen, M.;Niebel, H.;Pueschel, H.;Schade, H.-J.;Stepan, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--70.01486.9 - German - 1980
Key words: dynamics;eccs;fluid flow;fuel assemblies;heat transfer;knk-2 reactor;primary coolant circuits;radiation protection;reactor cores;safety analysis;steady-state conditions;thermal analysis;transients
R&D Category: Safety aspects
display the document: 34087418.pdf
First KNK II Seminar, September 1980 Erstes KNK II Seminar, September 1980
Kathol, WKernforschungszentrum Karlsruhe GmbH (Germany)
INIS-DE-KFK--016 - German - 1980
Key words: fuel assemblies;knk-2 reactor;radioactive waste disposal;reactor operation;reactor safety
R&D Category: any or undefined
display the document: 34087492.pdf
BMFT-CEA-US-DOE Exchange on Fast Breeder Reactors, Proceedings of the 1st Expert-Meeting at Karlsruhe March 24 and 25, 1980
Kernforschungszentrum Karlsruhe GmbH (Germany)INIS-DE-KFK--017 - English - 1980
Key words: ebr-2 reactor;international cooperation;knk-2 reactor;rapsodie reactor;reactor operation;reactor safety
R&D Category: any or undefined
display the document: 34087493.pdf
Comparison of diffusion- and transportcode-results in the course of the evaluations of the SNEAK 11B1 control rod experiments Vergleich von Diffusions- und Transportcode-Ergebnissen bei der Auswertung von Kontrollstabexperimenten im Rahmen des SNEAK 11B1-Experimentierprogramms
Henneges, G.;Kuefner, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P43B - German - 1980
Key words: calculation methods;control rod worths;discrete ordinate method;knk-2 reactor;neutron diffusion equation;neutron flux;sneak reactor;subcritical assemblies;zero power reactors
R&D Category: Reactor physics
display the document: 34087776.pdf
KNK II irradiation project of an annular element with 19-pin carbide test bundle on a ring position of the test zone KNK II Bestrahlungsvorhaben Ringelement mit 19-Stab Karbidtestbuendel auf einer Kranzposition der Testzone
Haefner, H.E.;Steiner, H.;Weinberg, D.;Norajitra, P.;Frey, H.HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P42A - German - 1980
Key words: annular fuel elements;fuel pins;knk-2 reactor;mixed carbide fuels;performance testing;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;research programs;thermal hydraulics
R&D Category: any or undefined
display the document: 34087757.pdf
SNEAK-11: Mockup critical studies of a small sodium-cooled fast reactor SNEAK-11: Mockup-Untersuchungen fuer einen kleinen natriumgekuehlten Reaktor
Moellendorff, U. von;Helm, FKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P42B - German - 1980
Key words: calculation methods;control rod worths;design;experimental data;knk-2 reactor;nuclear reaction kinetics;sneak reactor;sodium;spatial distribution;void coefficient;zero power reactors
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087775.pdf
Identification of vibrational effects in KNK II fuel elements
Vaeth, W.;Mitzel, F.;Ansari, SKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--3157 - English - 1981
Key words: correlations;frequency dependence;fuel elements;knk-2 reactor;measuring methods;mechanical vibrations;neutron flux;reactivity;reactor cores;reactor noise;spectral density;temperature dependence;thermocouples
R&D Category: Commissioning and start-up testing, rise to power, transient testing
display the document: 13650951.pdf
Analysis of reactivity noise measured at KNK II with respect to vibrations of control rods and primary loop components
Mitzel, F.;Ansary, S.;Vaeth, W. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.))INIS-mf--8131 - English - 1981
Key words: control elements;knk-2 reactor;mechanical vibrations;primary coolant circuits;reactivity insertions;reactor noise
R&D Category: Safety aspects
display the document: 14755895.pdf
Decladding of fast breeder reactor fuel elements with lattice spaces. Die Zerlegung von Schnellbrueter-Brennelementen mit Gitterabstandshaltern
Bestenreiner, G. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))INIS-mf--10197 - German - 1981
Key words: fuel assembly dismantling;knk-2 reactor;mechanical decladding;reprocessing;snr reactor;spent fuel elements
R&D Category: Decontamination, decommissioning, disassembly
display the document: 17054134.pdf
Status of the fast breeder reactor development in the Federal Republic of Germany, Belgium and The Netherlands, February 1981
Hueper, R.;Friese, R. (Kernforschungszentrum Karlsruhe, Karlsruhe (Germany))IWGFR--37/2 - English - 1981
Key words: belgian organizations;computer codes;fbr type reactors;german fr organizations;heat exchangers;international cooperation;knk-2 reactor;netherlands organizations;reactor components;reactor cooling systems;reactor safety;research programs;snr reactor;sodium
R&D Category: any or undefined
display the document: 33018450.pdf
Core design of the second core of KNK II Kernauslegung fuer die zweite Betriebsperiode von KNK II
Spenke, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.02743.4 - German - 1981
Key words: breeding pellets;calculation methods;design;knk-2 reactor;neutron absorbers;reactor cores;reactor physics;thermal hydraulics
R&D Category: Reactor physics
display the document: 34085697.pdf
Design report for core assemblies of KNK II/2: Mark II assemblies of the test zone (Central position)2.4 and 2.5 Auslegungsbericht fuer Kernelemente KNK II/2: Mark II Elemente der Testzone (Zentralelemente) 2.4 und 2.5
Fenneker, K.;Heinecke, J.;Singer, J.;Sperber, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.02749.5 - German - 1981
Key words: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;standards
R&D Category: Reactor physics
display the document: 34085698.pdf
Design report for core assemblies of KNK II/2: Driver zone assemblies without moderator Auslegungsbericht fuer Kernelemente KNK II/2: Treiberzonenelemente ohne Moderator
Bestenreiner, G.;Fenneker, K.;Ricken, E.;Singer, J.;Sperber, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--33.02750.2 - German - 1981
Key words: burnup;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;standards
R&D Category: Reactor physics
display the document: 34085699.pdf
Design report for core assemblies of KNK II/2: Mark II test zone fuel assemblies on the first ring 2.1, 2.2, 2.3, 2.6, 3.1, 3.3 and 3.5 Auslegungsbericht fuer Kernelemente KNK II/2: Mark II Kranzelemente der Testzone 2.1, 2.2, 2.3, 2.6, 3.1, 3.3 und 3.5
Bestenreiner, G.;Fenneker, K.;Heinecke, J.;Singer, J.;Sperber, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.04164.+ - German - 1981
Key words: calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;reactor cores;safety standards
R&D Category: Reactor physics
display the document: 34085702.pdf
Potential and state of development of acoustic boiling detection methods in sodium cooled reactors Potential und Entwicklungsstand akustischer Messverfahren zur Siededetektion in natriumgekuehlten Reaktoren
Rohrbacher, H.A.;Schleisiek, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P61A - German - 1981
Key words: acoustic measurements;background noise;boiling detection;bubbles;knk-2 reactor;measuring methods;on-line systems;reactor monitoring systems;sodium
R&D Category: Safety aspects
display the document: 34086292.pdf
Analysis of reactivity noise observed at KNK-II with respect to vibration of control rods and primary loop components Analyse von Reaktivitaets-Rauschen an KNK-II im Hinblick auf Vibrationen von Absorbern und Primaerkreis-Komponenten
Ansari, S.;Mitzel, F.;Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P65A - German - 1981
Key words: control elements;control rod drives;correlation functions;knk-2 reactor;mechanical vibrations;reactor control systems;reactor noise;transducers
R&D Category: Safety aspects
display the document: 34086293.pdf
Avoidance of gas bubble caused scrams at KNK II without reducing the sensitivity of the reactimeter to bulk sodium boiling Vermeidung der an der KNK II durch Gasblasen ausgeloesten Schnellabschaltungen ohne Beeintraechtigung der Sicherheitsfunktion des Reaktimeters bei integralem Natrium-Sieden
Vaeth, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P67A - German - 1981
Key words: boiling detection;cover gas;entrainment;knk-2 reactor;mechanical vibrations;reactivity insertions;reactor cores;reactor safety;scram;transducers
R&D Category: Safety aspects
display the document: 34086294.pdf
Design of the grid-plate inserts of the second core of KNK II Auslegung der Gitterplatteneinsaetze fuer den zweiten Kern der KNK II (Bearbeitungsstand 02.81)
Schade, H.-JINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--70.01654.9 - German - 1981
Key words: bubbles;eccs;entrainment;fluid flow;fuel elements;knk-2 reactor;reactivity insertions;reactor operation;thermal hydraulics
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087405.pdf
KNK II, Safety Report for the second core, following cores and the test program KNK II, Sicherheitsbericht fuer den zweiten Kern sowie Folgekerne und das Versuchsprogramm
INTERATOM GmbH, Bergisch-Gladbach (Germany)IA-INTAT--75.1438.5 - German - 1981
Key words: knk-2 reactor;reactor cores;reactor licensing;reactor protection systems;reactor safety;research programs;safety analysis;safety reports
R&D Category: any or undefined
display the document: 34087408.pdf
Description of the KNK II first core und its assemblies for an extended residence time of 400 equivalent full-power days Beschreibung des KNK II Erstkerns und seiner Elemente fuer eine verlaengerte Standzeit von 400 Vollasttagen
Schade, H.J.;Toebbe, H.;Wehmann, UINTERATOM GmbH, Bergisch Gladbach (Germany)
IA-ITB--54.04231.0 - German - 1981
Key words: burnup extension;eccs;heat transfer;knk-2 reactor;reactor accidents;reactor cores;reactor kinetics;thermal hydraulics
R&D Category: any or undefined
display the document: 34087411.pdf
PNC/CEA/DEBENE specialists' meeting on LMFBR plant experience, Cadarache, FRANCE, October 1981
Kernforschungszentrum Karlsruhe GmbH (Germany)INIS-DE-PSB--066 - English - 1981
Key words: entrainment;failed element detection;fuel element failure;knk-2 reactor;post-irradiation examination;reactivity coefficients;reactor kinetics;reactor operation;safety analysis
R&D Category: any or undefined
display the document: 34087497.pdf
Power operation start-up of the compact sodium-cooled nuclear power plant KNK II/1 Leistungsinbetriebnahme der Kompakten Natriumgekuehlten Kernreaktoranlage KNK II/1
Richard, H.;Schmidt-Hoenow, MKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH Bergisch-Gladbach (DE)
INIS-DE-KBG--008 - German - 1981
Key words: after-heat removal;dose rates;knk-2 reactor;power distribution;reactivity coefficients;reactor control systems;reactor operation;reactor start-up;thermal hydraulics
R&D Category: Reactor physics
display the document: 34087481.pdf
KNK - annular fuel element with carbide test bundle: Estimation of the sodium outlet temperature in case of obstruction of the test bundle, respectively the annular carrier element KNK - Ringelement mit 19-Stab Karbid-Testbuendel: Abschaetzung der Natriumaustrittstemperatur bei Verstopfung von Testbuendel bzw. Ringelement
Norajitra, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P62B - German - 1981
Key words: annular fuel elements;flow blockage;knk-2 reactor;mixed carbide fuels;reactor experimental facilities;reactor safety;reloadable fuel assemblies;replaceable fuel assemblies;temperature distribution;thermal hydraulics
R&D Category: Reactor physics
display the document: 34087758.pdf
Technical specifications for the fuel pin of the carbide element in the test zone of KNK II/2 Technische Spezifikationen fuer den Brennstab des Karbidelementes der Testzone von KNK II/2
Freund, D.;Jacobi, O.;Ritzhaupt-Kleissl, H.-J.;Steiner, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.16P66A - German - 1981
Key words: design;fertile materials;fissile materials;fuel assemblies;fuel pins;knk-2 reactor;mixed carbide fuels;specifications
R&D Category: any or undefined
display the document: 34087771.pdf
Measurement of the fission rate distribution in SNEAK 11B2 Messung der Spaltratenverteilung in SNEAK 11B2
Moellendorff, U. vonKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.01P62A - German - 1981
Key words: experimental data;knk-2 reactor;reactor cores;reactor fueling;sneak reactor;zero power reactors
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 34087777.pdf
Fuel reprocessing of the first failed KNK-II fuel element in MILLI. Die Wiederaufarbeitung von Brennstoff aus dem ersten defekten KNK II-Brennelementen in der MILLI
Bleyl, H.J. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Heisse Chemie)KFK--3278 - German - 1982
Key words: fuel element failure;fuel pins;knk-2 reactor;purex process;solvent extraction
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13695220.pdf
Experience on fuel recycling. Erfahrungen zur Brennstoff-Rezyklierung
Schneider, V.;Druckenbrodt, W.G. (Alpha Chemie und Metallurgie G.m.b.H.)KFK--3278 - German - 1982
Key words: fuel fabrication plants;knk-2 reactor;plutonium recycle
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13695223.pdf
KNK-II fuel elements and their operational behavior. Die Brennelemente der KNK-II und ihr Betriebsverhalten
Mayer, H. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.));Richard, H. (Kernkraftwerk-Betriebsgesellschaft m.b.H., Eggenstein-Leopoldshafen (Germany, F.R.))KFK--3278 - German - 1982
Key words: burnup;fuel element failure;fuel elements;fuel pins;knk-2 reactor;performance;reactor operation
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 13696676.pdf
The reference concept of the KNK-2 back end fuel cycle. Das Referenzkonzept zur Entsorgung der KNK II
Schnetgoeke, G. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter)KFK--3278 - German - 1982
Key words: fuel cycle;fuel storage pools;knk-2 reactor;spent fuel elements;spent fuel storage
R&D Category: any or undefined
display the document: 13696677.pdf
Sodium removal from fuel elements. Die Entfernung des Natriums von Brennelementen
Stade, K.C.;Breitlaender, H. (Kernkraftwerk-Betriebsgesellschaft m.b.H., Eggenstein-Leopoldshafen (Germany, F.R.));Stamm, H.H. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Radiochemie)KFK--3278 - German - 1982
Key words: argon;blowers;fuel washers;knk-2 reactor;purification;sodium;spent fuel elements
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13696678.pdf
Dismantling and post-irradiation examination of the two first defective fuel pins of the KNK-II. Die Zerlegung und Nachuntersuchung des ersten und zweiten defektiven KNK II-Brennelemente
Enderlein, H.;Kathol, W. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Hauptabteilung Kerntechnische Betriebe;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter)KFK--3278 - German - 1982
Key words: failed element detection;fuel assemblies;fuel assembly dismantling;fuel element failure;fuel pins;knk-2 reactor;post-irradiation examination
R&D Category: Safety aspects
display the document: 13696679.pdf
Conceptual study on the interim underwater storage of KNK-II fuel elements. Konzeptstudie zur Zwischenlagerung von KNK II-Brennelementen unter Wasser
Wasinger, K. (Kraftwerk Union A.G., Offenbach am Main (Germany, F.R.))KFK--3278 - German - 1982
Key words: feasibility studies;knk-2 reactor;planning;spent fuel elements;spent fuel storage;storage;underwater
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13696682.pdf
Conceptual design for interim storage of KNK II-fuel elements in a block storage facility. Konzeptstudie zur Zwischenlagerung von KNK II-Brennelementen in einem Blocklager
Arntzen, P.;Gasch, A. (Nuklear-Chemie und -Metallurgie G.m.b.H. (NUKEM), Hanau (Germany, F.R.))KFK--3278 - German - 1982
Key words: feasibility studies;knk-2 reactor;planning;spent fuel elements;spent fuel storage
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13696683.pdf
Concept on the interim storage of KNK-2 spent fuel elements in transport or storage containers. Konzept zur Zwischenlagerung bestrahlter KNK-II-Brennelemente in Transport-/Lagerbehaeltern
Bergmann, W.;Dries, G.;Laug, R. (Transnuklear G.m.b.H., Hanau (Germany, F.R.))KFK--3278 - German - 1982
Key words: containers;knk-2 reactor;spent fuel storage;transport
R&D Category: Decontamination, decommissioning, disassembly
display the document: 13696684.pdf
Reprocessing of KNK II reactor fuel rods at the MILLI plant. Wiederaufarbeitung von KNK II-Brennstaeben in der MILLI
Bleyl, H.J.;Ochsenfeld, W. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Heisse Chemie)KFK--3290 - German - 1982
Key words: decontamination;efficiency;knk-2 reactor;laboratory equipment;mixed oxide fuels;plutonium;purex process;solvent extraction;uranium
R&D Category: any or undefined
display the document: 13713539.pdf
Detection of fuel element vibration at KNK II. Nachweis von Brennelementschwingungen in KNK II
Mitzel, F.;Vaeth, W.;Ansari, SKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--3379 - German - 1982
Key words: correlation functions;fluid flow;fuel elements;jets;knk-2 reactor;mechanical vibrations;oscillations;reactor noise;vortices
R&D Category: Safety aspects
display the document: 14756090.pdf
Status of the fast breeder reactor development in the Federal Republic of Germany, Belgium and the Netherlands
Hueper, R. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter)IWGFR--42 - English - 1982
Key words: belgium;construction;coordinated research programs;fabrication;fbr type reactors;federal republic of germany;fuel cycle;fuel elements;heat transfer;hydraulics;international agreements;knk-2 reactor;netherlands;reactor components;reactor cores;reactor instrumentation;reactor materials;reactor operation;reactor physics;reactor safety;snr reactor;sodium;testing
R&D Category: any or undefined
display the document: 15056824.pdf
Progress report on research and development in 1981 of Institut fuer Radiochemie. Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1981 des Instituts fuer Radiochemie
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer RadiochemieKFK--3299 - German - 1982
Key words: air pollution;condensed aromatics;coolants;corium;desalination;fission product release;fission products;german fr organizations;knk-2 reactor;performance;primary coolant circuits;radioactive waste processing;radioactive waste storage;radiochemistry;safety;sodium;voloxidation process;water chemistry;zeolites
R&D Category: any or undefined
display the document: 15062364.pdf
Design report for core assemblies KNK II/2: Fuel pins with high density fuel Auslegungsbericht fuer Kernelemente KNK II/2: Brennstaebe mit hoher Dichte
Fenneker, KINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.04214.9 - German - 1982
Key words: burnup extension;calculation methods;cladding;density;design;fuel assemblies;fuel pellets;fuel pins;knk-2 reactor
R&D Category: Reactor physics
display the document: 34085704.pdf
KNK II on-line gamma spectrometer: Documentation of measurement results of the defected pin experiments from 28.10.1981 till 22.6.1982 KNK II on-line -Gammaspektrometer: Messwert-Dokumentation der Defektstabexperimente vom 28.10.1981 bis 22.6.1982
Hoffmann, G.;Letz, K.DKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P82A - German - 1982
Key words: cover gas;failed element monitors;fuel element failure;fuel pins;gamma spectroscopy;knk-2 reactor;on-line systems;reactor safety;testing
R&D Category: -Failure and failure propagation mechanisms
display the document: 34086287.pdf
Vibrational effects of fuel elements detected during KNK II power operation
Mitzel, F.;Vaeth, W.;Ansari, SKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.18P85B - English - 1982
Key words: flow stress;fuel elements;knk-2 reactor;mechanical vibrations;performance testing;reactivity;vortex flow
R&D Category: Safety aspects
display the document: 34086295.pdf
BMFT-CEA-US-DOE Exchange on KNK II-Rapsodie-EBR II operating experience, German contributions for the second expert meeting at Idaho Falls, USA, October 27 and 28, 1982
Kernforschungszentrum Karlsruhe GmbH (Germany)INIS-DE-PSB--062 - English - 1982
Key words: ebr-2 reactor;international cooperation;knk-2 reactor;rapsodie reactor;reactor operation;reactor safety
R&D Category: any or undefined
display the document: 34087496.pdf
Test operation KNK II: Investigation of the gas entrainments with disengaged reactivity limit (May '81 till Febr. '82) Versuchsbetrieb KNK II: Untersuchung von Gasdurchlaeufen bei abgeschaltetem Reaktivitaetsgrenzwert (Mai '81 bis Febr. '82)
Becker, M.;Richard, H.;Schmidt-Hoenow, MKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH Bergisch-Gladbach (DE)
KBG--UP0382.1 - German - 1982
Key words: entrainment;gases;knk-2 reactor;power distribution;reactivity;reactor operation;reactor start-up
R&D Category: Safety aspects
display the document: 34087735.pdf
Design report for an annular fuel element for accommodation of a carbide test bundle on the ring position of the KNK II/2 test zone Auslegungsbericht fuer ein Ringbrennelement zur Aufnahme eines Karbidtestbuendels auf der Kranzposition 201 der Testzone von KNK II/2
Haefner, H.EKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P82A - German - 1982
Key words: annular fuel elements;design;knk-2 reactor;mixed carbide fuels;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;specifications
R&D Category: any or undefined
display the document: 34087759.pdf
Safety considerations for the KNK II annular fuel element with carbide test bundle Sicherheitsbetrachtungen fuer das KNK II-Ringelement mit Karbidtestbuendel
Haefner, H.EKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P82B - German - 1982
Key words: annular fuel elements;irradiation devices;knk-2 reactor;mixed carbide fuels;reactor safety;reloadable fuel assemblies;replaceable fuel assemblies;risk assessment;safety analysis
R&D Category: Safety aspects
display the document: 34087760.pdf
Design Report for a 19-pin carbide test-bundle in a ring-subassembly of the test zone of KNK II/2 Auslegungsbericht fuer ein 19-Stab Karbidtestbuendel in einem Ringelement auf der Kranzposition 201 der Testzone KNK II/2
Haefner, H.EKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.16P83A - German - 1982
Key words: annular fuel elements;burnup;design;fuel assemblies;interstitial helium generation;knk-2 reactor;mixed carbide fuels
R&D Category: any or undefined
display the document: 34087772.pdf
SNEAK 11: Critical and subcritical experiments concerning reloading cores for KNK-II. SNEAK 11: Kritische und unterkritische Experimente zu Nachladekernen fuer KNK-II
Moellendorff, U. vonKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--3464 - German - 1983
Key words: criticality;knk-2 reactor;reactor cores;reactor lattice parameters;reactor physics;sneak reactor;subcritical assemblies
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 15010000.pdf
Fast breeder physics and nuclear core design. Schnellbrueterphysik und nukleare Kernauslegung
Marth, W.;Schroeder, R. (eds.)Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--3543 - German - 1983
Key words: computerized simulation;control rod worths;fbr type reactors;knk-2 reactor;planning;reactivity coefficients;reactor cores;reactor physics;reactor safety experiments;reactor safety;research programs
R&D Category: Reactor physics
display the document: 15028461.pdf
Several neutron-physical aspects of modified KNK-II assemblies. Einige neutronenphysikalische Aspekte modifizierter KNK II-Anordnungen
Broeders, I.;Krieg, B.;Kuesters, H.;Stein, E. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik)KFK--3543 - German - 1983
Key words: enriched uranium;knk-2 reactor;mixed oxide fuels;neutron diffusion equation;neutron flux;neutron reactions;reactor physics
R&D Category: Reactor physics
display the document: 15028466.pdf
KNK-II reactor: Reload experiments in SNEAK-11 reactor. KNK II: Experimente in SNEAK 11 zu Nachladungen
Moellendorff, U. v. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik)KFK--3543 - German - 1983
Key words: control rod worths;criticality;knk-2 reactor;reactor kinetics;reactor lattice parameters;reactor physics;sneak reactor
R&D Category: -Testing at zero-power in critical assemblies and confirmation at various power levels
display the document: 15028467.pdf
Assays on homogeneity of the mixed oxide at various stages of the fuel cycle. Untersuchungen zur Homogenitaet des Mischoxids in verschiedenen Stadien des Brennstoffkreislaufs
Kleykamp, H. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung 1 - Teilinstitut Kernbrennstoffe);Pejsa, R. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Hauptabteilung Kerntechnische Betriebe)KFK--3505 - German - 1983
Key words: fuel cycle;homogenization methods;knk-2 reactor;mixed oxide fuels;plutonium dioxide;uranium dioxide
R&D Category: any or undefined
display the document: 15028662.pdf
Development of materials for higher burn-up rates. Werkstoffentwicklung fuer hoehere Abbraende
Ehrlich, K.;Anderko, K. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung 2 - Teilinstitut Huellwerkstoffe)KFK--3505 - German - 1983
Key words: austenitic steels;burnup;fbr type reactors;fuel cans;knk-2 reactor;martensitic steels;reactor materials
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 15028667.pdf
Steady-state irradiation experiments. Stationaere Bestrahlungsexperimente
Geithoff, D. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung 3 - Teilinstitut Brennelemente)KFK--3505 - German - 1983
Key words: fuel element failure;fuel pins;irradiation capsules;irradiation devices;irradiation procedures;knk-2 reactor;post-irradiation examination
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 15028668.pdf
Status of fast breeder reactor development in the Federal Republic of Germany, Belgium and Netherlands - February 1983
Hueper, R. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter)IWGFR--47 - English - 1983
Key words: belgium;construction;coordinated research programs;fbr type reactors;federal republic of germany;fuel assemblies;international agreements;knk-2 reactor;monitoring;netherlands;nuclear power plants;political aspects;reactor components;reactor cores;reactor materials;reactor operation;reactor safety;snr reactor
R&D Category: any or undefined
display the document: 15056833.pdf
Determination of radionuclides in the primary sodium and in the primary cover gas Argon and of the Tritium content of the ternary water-/steam circuit of KNK II at the start-up of the second core Bestimmung von Radionukliden im Primaernatrium, im primaeren Schutzgas Argon und von Tritium im tertiaeren Wasser-/Dampfkreislauf der KNK-II bei der Inbetriebnahme des Zweitkerns
Stamm, H.-H.;Hanke, H.-D.;Clauss, H.;Schmidt, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P11A - German - 1983
Key words: argon;cover gas;knk-2 reactor;primary coolant circuits;radiochemical analysis;secondary coolant circuits;sodium;tritium
R&D Category: Commissioning and start-up testing, rise to power, transient testing
display the document: 34086278.pdf
Design of the second core of KNK II Auslegung des zweiten Kerns der KNK II
Schade, H.-JINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-INTAT--70.02244.0 - German - 1983
Key words: design;irradiation;knk-2 reactor;reactor cores;reactor protection systems;reactor safety;risk assessment;safety analysis;snr reactor
R&D Category: any or undefined
display the document: 34087406.pdf
Fuel element failure detection experiments, evaluation of the experiments at KNK II/1 (Intermediate Report) Brennelement-Schadensnachweisversuche, Auswertung der Versuche von KNK II/1 (Zwischenbericht)
Bruetsch, DaukINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--61.03068.7 - German - 1983
Key words: adsorption;electrostatic precipitators;failed element detection;gas chromatography;knk-2 reactor;measuring instruments;sensitivity;xenon
R&D Category: -Failure detection
display the document: 34087416.pdf
Nuclear, thermal-hydraulic and mechanical investigations of different variants for the third core of KNK II Nukleare, thermohydraulische und mechanische Untersuchungen zu verschiedenen Varianten des dritten Kerns der KNK II
Wehmann, UINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--54.05674.4 - German - 1983
Key words: design;fuel assemblies;knk-2 reactor;mechanical properties;mixed oxide fuels;neutron absorbers;reactor cores;reactor physics;thermal hydraulics
R&D Category: any or undefined
display the document: 34087412.pdf
Study of definition: Investigation of different variants for the third core of KNK II Definitionsstudie KNK II/3: Untersuchung verschiedener Kernvarianten fuer einen dritten Kern der KNK II
Schade, H.-J.;Toebbe, H.;Wehmann, UINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--54.05817.2''A'' - German - 1983
Key words: design;feasibility studies;fuel assemblies;fuel pins;knk-2 reactor;licensing regulations;mixed oxide fuels;neutron absorbers;reactor cores;safety analysis;shielding;uranium oxides
R&D Category: any or undefined
display the document: 34087413.pdf
In pile operation and post-examination of degassed and wet B4C absorber pins in the KNK II second core, experimental boundary conditions and documentation of the pre-examination results In-Pile Einsatz und Nachuntersuchung entgaster und nasser B4C-Absorberstaebe im KNK II Folgecore, Experimentelle Randbedingungen und Dokumentation der Voruntersuchungsergebnisse
Hoeller, P.;Hoerle, MINTERATOM GmbH, Bergisch Gladbach (Germany)
IA-ITB--54.05968.* - German - 1983
Key words: boron carbides;control elements;irradiation;knk-2 reactor;neutron absorbers;performance;post-irradiation examination;reactor cores;research programs
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087414.pdf
Evaluation of the ceramographies of the KNK II/1 test zone fuel assembly NY-202-IA Auswertung von Keramographien des KNK II/1 Testzonenbrennelements NY-202-IA
Geier, FINTERATOM GmbH, Bergisch Gladbach (Germany)
IA-ITB--54.06172.9 - German - 1983
Key words: burnup;ceramography;comparative evaluations;destructive testing;fuel element failure;fuel pins;hot cells;knk-2 reactor;post-irradiation examination
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087415.pdf
Legend and operational data of KNK (March 1966 until Dec. 1982) Legende und Betriebsdaten der KNK (Maerz 1966 bis Dez. 1982)
Alfke, H.-W.;Richard, H.;Streib, K.-PhKernkraftwerk-Betriebsgesellschaft mbH (Germany)
INIS-DE-KBG--002 - German - 1983
Key words: fast reactors;knk-2 reactor;power generation;radiation protection;reactor cores;reactor operation;reactor start-up;thermal reactors
R&D Category: any or undefined
display the document: 34087477.pdf
Annular fuel elements with replaceable test bundles in KNK II Ring-Brennelemente mit auswechselbaren Testbuendeln in KNK II
Philipp, K.D.;Haefner, H.EKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P06C - German - 1983
Key words: annular fuel elements;fuel assemblies;fuel element clusters;in pile loops;irradiation devices;knk-2 reactor;mixed carbide fuels;performance testing;reloadable fuel assemblies;replaceable fuel assemblies
R&D Category: any or undefined
display the document: 34087748.pdf
Evaluation of post-irradiation examination results on oxide fuel pins of the KNK II/1 test subassemblies 208 BN and 202 IA Auswertung von Untersuchungsergebnissen an bestrahlten Oxidbrennstaeben aus den KNK II/1 Testzonen Brennelementen 208 BN und 202 IA
Dienst, W.;Blumhofer, MKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.03P82A - German - 1983
Key words: burnup;cladding;corrosion;fuel element failure;fuel pins;fuel-cladding interactions;irradiation;knk-2 reactor;mixed oxide fuels;post-irradiation examination
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087762.pdf
Results of research and development activities in 1983 of the Institut fuer Material- und Festkoerperforschung. Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1983 des Instituts fuer Material- und Festkoerperforschung
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und FestkoerperforschungKFK--3688 - German - 1984
Key words: austenitic steels;bibliographies;building materials;chemical reactions;coordinated research programs;corrosion;fbr type reactors;fuel cans;fuel element failure;fuel-cladding interactions;international cooperation;irradiation devices;irradiation procedures;knk-2 reactor;martensitic steels;materials testing;mathematical models;mechanical properties;microanalysis;mixed oxide fuels;neutron absorbers;nuclear fuels;oxidation;post-irradiation examination;production;quality control;radioactive waste processing;reactor accidents;reactor safety;reprocessing;sodium;spent fuel storage;thermal shock;thermonuclear fuels;thermonuclear reactor material;transients;uranium carbides
R&D Category: any or undefined
display the document: 15062366.pdf
Report on research and development work 1983 of the Institut fuer Radiochemie. Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1983 des Instituts fuer Radiochemie
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer RadiochemieKFK--3691 - German - 1984
Key words: adsorption;aerosols;bibliographies;burnup;catalysts;cesium;chemical analysis;chemical reaction kinetics;cooling systems;corrosion products;desalination;desorption;electrolysis;explosions;fission product release;fission products;ion exchange;isotope ratio;knk-2 reactor;krypton;liquid metals;meltdown;ozone;phosphates;pressure vessels;purification;radiochemistry;residues;safeguards;separation processes;sewage sludge;spectrometers;spectroscopy;tritium;uranyl compounds;voloxidation process;wastes;water treatment;water vapor;xenon
R&D Category: any or undefined
display the document: 15066292.pdf
Dynamic simulation of the air-cooled decay heat removal system of the German KNK-II experimental breeder reactor
Schubert, B.KBrookhaven National Lab., Upton, NY (USA)
NUREG/CR--3910 - English - 1984
Key words: after-heat removal;control systems;feedback;heat exchangers;knk-2 reactor;simulation
R&D Category: Safety aspects
display the document: 16058473.pdf
Review of LMFBR absorber development in DeBeNe
Duenner, P.;Steinmetz, B. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))IWGFR--48 - English - 1984
Key words: boron 10;boron carbides;helium generation;knk-2 reactor;lmfbr type reactors;materials testing;neutron absorbers;post-irradiation examination;reactor control systems;regulating rods;research programs;snr reactor;specifications;swelling
R&D Category: Reactor physics
display the document: 16061281.pdf
Status of fast breeder reactor development in the Federal Republic of Germany, Belgium and The Netherlands - February 1984
Hueper, R. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter)IWGFR--52 - English - 1984
Key words: coordinated research programs;federal republic of germany;fuel elements;international cooperation;knk-2 reactor;lmfbr type reactors;materials testing;modifications;reactor cores;reactor monitoring systems;reactor operation;reactor safety;reprocessing;reviews;snr reactor;snr-2 reactor;specifications
R&D Category: any or undefined
display the document: 17003594.pdf
Overview of the design of core restraint systems
Heinecke, J. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))IWGFR--54 - English - 1984
Key words: computerized simulation;knk-2 reactor;reactor core restraints;snr reactor;snr-2 reactor;specifications
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 18010132.pdf
Post-irradiation examinations on the KNK II/1 fuel element NY-203 with 400 equivalent full-power days residence time and 10 % burnup Nachbestrahlungsuntersuchungen an dem KNK II/1 Brennelement NY-203 mit 400 Vollasttagen Standzeit und 10 % Abbrand
Patzer, G.;Geier, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.06442.+ - German - 1984
Key words: austenitic steels;cladding;design;destructive testing;fuel assemblies;fuel pins;hot cells;knk-2 reactor;mixed oxide fuels;nondestructive analysis;post-irradiation examination
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085706.pdf
First Test of a Radionuclide Trap at KNK II Erste Test einer Radionuklid-Falle in KNK-II
Stamm, H.-H.;Hanke, H.-D.;Clauss, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P16A - German - 1984
Key words: knk-2 reactor;manganese 54;nickel;primary coolant circuits;sodium;sorption;zinc 65
R&D Category: any or undefined
display the document: 34086279.pdf
Intermediate report about the use of fuel assembly test probes, temperature measurement probes and sound recorders in KNK II/1 Zwischenbericht ueber den Einsatz von Brennelementmesssonden, Temperaturmesssonden und Schallaufnehmern in der KNK II/1
Blasius, DINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA-ITB--61.03615.7 - German - 1984
Key words: acoustic monitoring;fuel elements;knk-2 reactor;neutron probes;recording systems;temperature measurement;thermocouples
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087417.pdf
Operational tests at zero power and at power of the second core of the compact sodium cooled power plant KNK II Funktionspruefungen bei Nulleistung und Leistung des Kerns II/2 der Kompakten Natriumgekuehlten Kernreaktoranlage KNK II
Richard, H.;Schmidt-Hoenow, MKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH Bergisch-Gladbach (DE)
KBG--UP0384.2 - German - 1984
Key words: comparative evaluations;control rod worths;critical mass;experimental data;knk-2 reactor;reactivity coefficients;reactor operation;reactor physics;reactor start-up;temperature distribution;theoretical data;thermal hydraulics
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087736.pdf
Final Report about the gas bubble problem in KNK II Abschlussbericht zum Gasblasenproblem der KNK II
Richard, H.;Schade, H.-JKernkraftwerk-Betriebsgesellschaft mbH (Germany), INTERATOM GmbH, Bergisch Gladbach (DE)
KBG--UP1084.2 - German - 1984
Key words: bubbles;degassing;entrainment;fuel elements;gases;knk-2 reactor;reactivity insertions;reactor cores;reactor operation;scram
R&D Category: Safety aspects
display the document: 34087737.pdf
Reloadable annular fuel elements with replaceable test bundles (TOAST) for a ring position of the test zone of KNK II/3 Wiederbeladbare Ringelemente mit auswechselbaren Testbuendeln (TOAST) fuer eine Kranzposition der Testzone in KNK II/3
Haefner, H.EKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P08B - German - 1984
Key words: annular fuel elements;knk-2 reactor;mixed carbide fuels;performance testing;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;specifications
R&D Category: any or undefined
display the document: 34087749.pdf
Thermal-hydraulic design calculations for the annular fuel element with replaceable test bundles (TOAST) on the test zone position 205 of KNK II/3 Thermohydraulische Auslegungsrechnungen fuer das Ringelement mit auswechselbaren Testbuendeln (TOAST) auf der Kranzposition 205 der KNK II/3
Norajitra, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P08D - German - 1984
Key words: annular fuel elements;c codes;design;knk-2 reactor;performance testing;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;spacers;specifications;temperature distribution;thermal hydraulics
R&D Category: any or undefined
display the document: 34087750.pdf
Irradiation experiments in the KNK II reactor Bestrahlungsexperimente im KNK II Reaktor
Bojarsky, E.;Haefner, H.E.;Schmidt, LKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.12P08B - German - 1984
Key words: fuel element clusters;irradiation;knk-2 reactor;materials testing;performance testing
R&D Category: any or undefined
display the document: 34087766.pdf
Examination of sodium wetted steam generator tube segments of KNK II Nachuntersuchungen natriumseitiger Dampferzeugerrohrabschnitte aus der KNK II
Adelhelm, Ch.;Borgstedt, H.UKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.14P07A - German - 1984
Key words: auger electron spectroscopy;chromium additions;corrosion;emission spectroscopy;knk reactor;knk-2 reactor;metallography;microstructure;oxides;scanning electron microscopy;spectroscopy;steam generators;steel-crmo;surface properties;thin films;tubes;zirconium
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087770.pdf
Kernforschungszentrum Karlsruhe. Institut fuer Datenverarbeitung in der Technik: Progress report on research and development works in 1984. Kernforschungszentrum Karlsruhe. Institut fuer Datenverarbeitung in der Technik: Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1984
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Datenverarbeitung in der TechnikKFK--3893 - German - 1985
Key words: computer calculations;computer networks;data processing;elementary particles;knk-2 reactor;nuclear physics;process computers;radioactive wastes;research programs;thermonuclear reactions;wak;waste processing
R&D Category: any or undefined
display the document: 16058832.pdf
Institut fuer Radiochemie: Results of R and D work in 1984. Institut fuer Radiochemie: Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1984
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer RadiochemieKFK--3897 - German - 1985
Key words: aerosols;automation;bibliographies;breeding;burnup;cesium;chemical analysis;fission product release;fission products;isotope production;isotope separation;knk-2 reactor;krypton;liquid wastes;meltdown;molybdenum;purification;radioactive waste processing;solvent extraction;spent fuel elements;tbp;tritium;water treatment
R&D Category: any or undefined
display the document: 16066997.pdf
Influence of the KNK II postscram control on the thermohydraulic plant behavior
Schubert, B. (GKSS-Forschungszentrum Geesthact GmbH, West Germany)CONF-850410--Vol.2 - English - 1985
Key words: flow rate;fluid flow;heat transfer;knk-2 reactor;pipes;reactor control systems;reactor cooling systems;reactor cores;reactor protection systems;reactor safety;scram;thermal shock
R&D Category: Thermo hydraulics in all operating, shut-down and accident regimes
display the document: 17036590.pdf
Theory, design, and operation of liquid metal fast breeder reactors, including operational health physics
Adams, S.RIdaho National Engineering Lab., Idaho Falls (USA)
NUREG/CR--4375 - English - 1985
Key words: alara;ebr-2 reactor;fftf reactor;knk-2 reactor;lmfbr type reactors;pfr reactor;phenix reactor;radiation protection
R&D Category: any or undefined
display the document: 17036831.pdf
Design report for the residence time extension of KNK II/2 from 455 to 720 equivalent full-power days Auslegungsbericht fuer die Standzeitverlaengerung der KNK II/2 von 455 bis 720 Vollasttage
Schade, H.-J.;Steinmetz, B.;Wehmann, UINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.06665.7 - German - 1985
Key words: burnup extension;design;heat transfer;knk-2 reactor;reactor cores;reactor kinetics;safety analysis
R&D Category: Reactor physics
display the document: 34085707.pdf
Design report for the test control rod with special pins Auslegungsbericht fuer das Test-Regeltrimmelement mit Sonderstaeben
Willinger, OINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.06696.* - German - 1985
Key words: boron carbides;coatings;control elements;design;europium borides;fuel assemblies;knk-2 reactor;neutron absorbers;niobium;reactor cores;testing;zirconium hydrides
R&D Category: Reactor physics
display the document: 34085708.pdf
Characteristics of the KNK II second core-- irradiation history, power tilting campaign, subassembly reloadings, failed fuel detection and burnup data (358/758 VLT), status of October 10th,1985. Charakteristik der KNK II Zweitbeladung, Bestrahlungsverlauf, Elementwechsel, Schieflastbetrieb, Defektsuche und Abbranddaten (358/758 VLT), Stand 10.10.1985
Geier, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.06820.8 - German - 1985
Key words: atomic displacements;burnup;failed element detection;fuel element failure;fuel management;knk-2 reactor;neutron flux tilting;reactor operation
R&D Category: Reactor physics
display the document: 34085709.pdf
Determination of the isotopic ratios Xe131/Xe134 in the cover gas of KNK II (Leaker phase from 6. 4. to 2. 5. 85) Bestimmung der Isotopenverhaeltnisse Xe-131/Xe-134 im Covergas der KNK II (Leakerphase vom 6.4. bis 2.5.85)
Stieglitz, L.;Becker, R.;Will, RKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P33A - German - 1985
Key words: delayed neutron analysis;failed element detection;fuel element failure;isotope ratio;knk-2 reactor;plutonium 239;reactor operation;reactor safety;uranium 235;xenon 131;xenon 134
R&D Category: -Failure and failure propagation mechanisms
display the document: 34086282.pdf
Flux tilting campaign at KNK II on May 3rd, 1985 for the prelocation of a fuel subassembly cladding failure Schieflastbetrieb an der KNK II am 3. Mai 1985 zur Vorlokalisierung eines Brennelement-Huellrohrfehlers
Jacobi, S.;Hoffmann, G.;Jonatzke, O.;Klein, D.;Schleisiek, K.;Schmitz, GKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.02.17P35A - German - 1985
Key words: delayed neutron analysis;failed element detection;fuel element failure;isotope ratio;knk-2 reactor;neutron flux tilting;neutron flux;reactor fueling;xenon
R&D Category: -Failure and failure propagation mechanisms
display the document: 34086283.pdf
Description of the global fuel element failure detection for SNR 300 Beschreibung des globalen BE-Schadensnachweises fuer den SNR 300
Dauk, JINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--61.03915.9 - German - 1985
Key words: analog computers;cover gas;electronic equipment;failed element detection;fuel element failure;gamma spectroscopy;ge semiconductor detectors;knk-2 reactor;reactor control systems;reactor monitoring systems;reactor safety;snr reactor
R&D Category: -Failure detection
display the document: 34087388.pdf
Standard deviation of the cooling channel temperature increase and the pin linear power for the annular elements RE 100, RE 205 and the TOAST test bundle in KNK II/3 Standardabweichungen der Kuehlkanalaufwaermspanne und der Stablaengenleistung fuer die Ringelemente RE 100, RE 205 und das TOAST-Testbuendel der KNK II/3
Norajitra, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P12A - German - 1985
Key words: annular fuel elements;hot channel factor;hot spot factor;knk-2 reactor;reactor experimental facilities;reactor safety;reloadable fuel assemblies;replaceable fuel assemblies;thermal hydraulics
R&D Category: any or undefined
display the document: 34087751.pdf
Temperature transient experiments TETRA in the third core of KNK II Temperaturtransientenexperimente TETRA im dritten Kern des KNK II Reaktors
Reimann, G.;Haefner, H.EKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.04P20A - German - 1985
Key words: annular fuel elements;fluid flow;knk-2 reactor;reactor experimental facilities;reactor safety;reloadable fuel assemblies;replaceable fuel assemblies;safety analysis;temperature coefficient;temperature dependence;testing
R&D Category: Safety aspects
display the document: 34087764.pdf
Hydraulic tests with measuring and control plug for KNK II temperature transient experiments (TETRA) Hydraulische Tests mit Mess- und Regelstopfen fuer KNK II Temperaturtransientenexperimente (TETRA)
Reimann, G.;Grossgarten, H.-D.;Heckert, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.04P20B - German - 1985
Key words: annular fuel elements;knk-2 reactor;pressure drop;reactor safety;testing;thermal hydraulics;transients
R&D Category: -Thermo hydraulic testing
display the document: 34087765.pdf
Novel models of controller parts for the SSC-L code. Neumodellierung der Regelung fuer das Rechenprogramm SSC-L
Schubert, B. (GKSS-Forschungszentrum Geesthacht G.m.b.H., Geesthacht-Tesperhude (Germany, F.R.). Inst. fuer Anlagentechnik);Moench, D. (Fachhochschule Hamburg (Germany, F.R.). Fachbereich Maschinenbau und Chemieingenieurwesen)GKSS-Forschungszentrum Geesthacht G.m.b.H., Geesthacht-Tesperhude (Germany, F.R.)
GKSS--86/E/12 - German - 1986
Key words: computerized simulation;knk-2 reactor;lmfbr type reactors;mathematical models;numerical solution;reactor control systems;transients
R&D Category: -Analytic and numeric methods
display the document: 17062681.pdf
The Karlsruhe KNK-2 reactor. Residence time of the 2nd core extended to 720 full-load days. Brief report. KNK 2. Kompakte Natriumgekuehlte Kernreaktoranlage mit schnellem Kern. Standzeitverlaengerung 2. Kern auf 720 Vollasttage. Kurzbeschreibung
Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.);Kernkraftwerk-Betriebsgesellschaft m.b.H., Eggenstein-Leopoldshafen (Germany, F.R.);Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.)INIS-mf--10221 - German - 1986
Key words: knk-2 reactor;reactor cores
R&D Category: any or undefined
display the document: 17065598.pdf
A protocol system as an extension of the MIRA reactor protection system
Elies, V. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Datenverarbeitung in der Technik)INIS-mf--10499 - English - 1986
Key words: computer codes;data processing;electronic equipment;knk-2 reactor;on-line systems;reactor shutdown;safety engineering
R&D Category: Safety aspects
display the document: 17069159.pdf
Consulting core surveillance system COCOSS I at KNK II
Hoffmann, GKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--4139 - English - 1986
Key words: cover gas;flowsheets;fuel cans;fuel element failure;gamma spectra;in pile loops;knk-2 reactor;monitoring;on-line measurement systems;r codes
R&D Category: Safety aspects
display the document: 18024009.pdf
Fast breeder fuel pin bundle tests in the KNK II-reactor
Haefner, H.E.;Bojarsky, EKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--4141 - English - 1986
Key words: flow rate;fuel element clusters;knk-2 reactor;loss of flow;reactor channels;reactor cores;simulation;temperature dependence;temperature distribution;testing;transients
R&D Category: Reactor physics
display the document: 18028687.pdf
Irradiation capsules with heat pipes for KNK II and SNR 300. Bestrahlungskapsel mit Waermerohr fuer KNK II und SNR 300
Mueller, K.;Bojarsky, E.;Norajitra, P.;Schmidt, LKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--4151 - German - 1986
Key words: annular space;cylindrical configuration;heat pipes;heat transfer;helium;irradiation capsules;knk-2 reactor;power distribution;reactor cores;rhodium;snr reactor;temperature dependence;thermal conductivity;thermal insulation
R&D Category: Reactor physics
display the document: 18032779.pdf
Controllable irradiation facilities for KNK II. Regelbare Bestrahlungseinrichtungen fuer den KNK II-Reaktor
Schmidt, L.;Lehning, H.;Mueller, K.;Reimann, GKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Material- und Festkoerperforschung;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--4149 - German - 1986
Key words: annular space;electric cables;irradiation devices;irradiation procedures;knk-2 reactor;neutron reflectors;operation;pressure tubes;reactor cores;thermocouples
R&D Category: Reactor physics
display the document: 18042436.pdf
Status of fast breeder reactor development in the Federal Republic of Germany, Belgium and the Netherlands - February 1985
Hueper, R. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter)IWGFR--56 - English - 1986
Key words: belgium;construction;coordinated research programs;federal republic of germany;fuel cycle;fuel elements;international cooperation;knk-2 reactor;netherlands;planning;reactor monitoring systems;reactor operation;reviews;snr reactor;snr-2 reactor;specifications
R&D Category: any or undefined
display the document: 18080623.pdf
Status of fast breeder reactor development in the Federal Republic of Germany, Belgium and the Netherlands - January 1986
Hueper, R. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter)IWGFR--60 - English - 1986
Key words: belgium;federal republic of germany;france;fuel assemblies;international cooperation;japan;knk-2 reactor;mockup;netherlands;performance testing;planning;reactor fueling;reactor instrumentation;reactor licensing;reactor operation;reactor safety;research programs;snr reactor;snr-2 reactor;specifications;usa
R&D Category: any or undefined
display the document: 18080636.pdf
Activities on flow induced vibration within the FRG Fast Reactor Program, current status and future planning
Rangette, A.;Schmidt, H. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))IWGFR--62 - English - 1986
Key words: dynamic loads;fluid-structure interactions;knk-2 reactor;mechanical vibrations;planning;research programs;snr reactor
R&D Category: -Structural properties, static design, structural integrity, movements due to thermal expansion
display the document: 18095650.pdf
Results of post-irradiation examinations of the absorber NS 201 (with pellets) of the KNK II first core Ergebnisse von Nachbestrahlungsuntersuchungen am Absorber NS 201 der Erstbeladung KNK II/1 (mit pelletierten Absorberstaeben)
Hess, BINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.06852.2 - German - 1986
Key words: absorber pellets;boron carbides;burnup;destructive testing;knk-2 reactor;neutron absorbers;post-irradiation examination;reactor operation
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085710.pdf
Fuel assembly NY-308 Compilation of the fuel and fuel pin fabrication data from the T264 data bank system BESEX Das KNK II/2 Brennelement NY-308 Zusammenstellung der Brennstoff- und Brennstabfertigungs-Daten aus dem T264-Datenbanksystem BESEX
Patzer, GINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.06863.8 - German - 1986
Key words: burnup;data compilation;fissile materials;fuel assemblies;fuel pins;knk-2 reactor;post-irradiation examination
R&D Category: Reactor physics
display the document: 34085712.pdf
Material properties of high density (U,Pu)O2-fuel for use in fuel behavior models Materialeigenschaften von hoch-dichtem (U,Pu)O2 Brennstoff fuer Modelle zum Brennstoffverhalten
Toebbe, H.;Freund, D.;Gaertner, HINTERATOM GmbH, Bergisch Gladbach (Germany), Kernforschungszentrum Karlsruhe GmbH (DE)
IA--54.06862.6 - German - 1986
Key words: creep;irradiation;knk-2 reactor;mechanical properties;mixed oxide fuels;performance;swelling
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085711.pdf
Summary of the post-irradiation examinations of the defective fuel assembly NY-202 of the KNK II first core Zusammenfassende Darstellung der Nachbestrahlungs-Untersuchungen am defekten Brennelement NY-202 der Erstbeladung KNK II/1
Hess, BINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.06874.3 - German - 1986
Key words: cladding;corrosion;destructive testing;failures;fuel element failure;fuel pins;hot cells;knk-2 reactor;nondestructive analysis;post-irradiation examination;spacers
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085713.pdf
Material correlations and models for the irradiation behavior of fissile and fertile material in SNR-300, Mark-II and KNK II, third core Materialkorrelationen und Modelle zum Brennstoff- und Brutstoffbestrahlungsverhalten fuer SNR-300, Nachladung Mark-II und 3. Kern KNK II
Fenneker;Steinmetz;ToebbeINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.06938.3 - German - 1986
Key words: fuel pins;i codes;irradiation;knk-2 reactor;mechanical properties;mixed oxide fuels;performance testing;reactor fueling;uranium dioxide
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085714.pdf
KNK II: Evaluation of the neutron dosimetry MTE1 on position 517 KNK II: Auswertung der Neutronendosimetrie MTE1 auf Position 517
Timm, WINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.06953.1 - German - 1986
Key words: activation analysis;cobalt 60;evaluation;fuel cycle;knk-2 reactor;manganese 54;neutron dosimetry;neutron flux;scandium 46;spatial distribution
R&D Category: Reactor physics
display the document: 34085715.pdf
Design Report for the third core of KNK II (KNK II/3) Auslegungsbericht fuer den dritten Kern der KNK II (KNK II/3)
Stanculescu, AINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.06990.0 - German - 1986
Key words: design;fuel assemblies;hot channel factor;hot spot factor;knk-2 reactor;mechanics;neutron absorbers;reactor cores;reactor physics;thermal hydraulics
R&D Category: Reactor physics
display the document: 34085716.pdf
KNK II, third core: Design report for Mark II test zone NY401 to NY406 fuel assemblies on the first ring KNK II, dritter Kern: Auslegungsbericht fuer Mark II Kranzelemente der Testzone NY401 bis NY406
Ricken, E.;Toebbe, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07020.4 - German - 1986
Key words: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor
R&D Category: Reactor physics
display the document: 34085717.pdf
KNK II, third core: Design report for driver zone assemblies NU 401 bis 407 (without moderator) and NW 401 bis 421 (with moderator) KNK II, dritter Kern: Auslegungsbericht fuer Treiberzonenelemente NU 401 bis 407 (ohne Moderator) und NW 401 bis 421 (mit Moderator)
Ricken, E.;Toebbe, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07025.3 - German - 1986
Key words: burnup extension;calculation methods;design;fuel assemblies;fuel cycle;knk-2 reactor;moderators;safety standards;zirconium hydrides
R&D Category: Reactor physics
display the document: 34085720.pdf
Decay heat and activity of the structural materials of the fuel and blanket assemblies of the second and third core of KNK II Nachzerfallsleistung und Aktivitaet aus den Strukturmaterialien der Brenn- und Brutelemente der KNK II Kerne 2 und 3
Winterhagen, DINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--70.03765.0 - German - 1986
Key words: after-heat;breeding blankets;cobalt 60;fuel assemblies;knk-2 reactor;radioactivity;reactor cores
R&D Category: Reactor physics
display the document: 34087390.pdf
Safety related investigations for the third core of KNK II with a residence time of 720 equivalent full-power days (part B) Sicherheitstechnische Untersuchungen fuer den dritten Kern der KNK II mit einer Standzeit von 720 Vollasttagen (Teil B)
Becker;Stepan;WinterhagenINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--70.03907.7 - German - 1986
Key words: after-heat removal;burnup extension;eccs;fuel cycle;knk-2 reactor;radiology;reactor accidents;safety analysis;shielding;steady-state conditions
R&D Category: Safety aspects
display the document: 34087391.pdf
KNK II, Safety Report for the residence time extension of the second core to 720 equivalent full-power days KNK II, Sicherheitsbericht fuer die Standzeitverlaengerung 2. Kern auf 720 Vollasttage
INTERATOM GmbH, Bergisch-Gladbach (Germany)IA--75.15917.* - German - 1986
Key words: burnup extension;design;knk-2 reactor;licensing;radiation protection;reactor cores;reactor safety;research programs;safety analysis;safety reports
R&D Category: any or undefined
display the document: 34087396.pdf
Short description of the residence time extension for KNK II second core to 720 equivalent full-power days Kurzbeschreibung der Standzeitverlaengerung KNK II zweiter Kern auf 720 Vollasttage
Richard, H.;Schmidt-Hoenow, MINTERATOM GmbH Bergisch-Gladbach (Germany), Kernkraftwerk-Betriebsgesellschaft mbH (DE), Kernforschungszentrum Karlsruhe GmbH (DE)
IA--75.15918.1 - German - 1986
Key words: burnup extension;knk-2 reactor;reactivity;reactor licensing;reactor operation;reactor safety;research programs
R&D Category: any or undefined
display the document: 34087397.pdf
Operation of KNK with defective fuel assemblies and consequences to be drawn. Presentation at the Exchange Meeting about the operation of KNK II and BOR 60/BR 10 Plants, Dimitrowgrad, September 5.- 8., 1988 Betrieb der KNK mit schadhaften Brennelementen und Konsequenzen daraus. Praesentation auf dem Meeting zum Erfahrungsaustausch ueber den Betrieb von KNK II und BOR 60/BR 10 Anlagen in Dimitrowgrad, 5. - 8. September 1988
Steiger, WKernkraftwerk-Betriebsgesellschaft mbH (Germany)
INIS-DE-KBG--014 - German - 1986
Key words: failed element detection;failed element monitors;fuel cycle;fuel element failure;isotope ratio;knk-2 reactor;reactor operation;reactor safety;xenon 131;xenon 134
R&D Category: Safety aspects
display the document: 34087484.pdf
Prelocation of the defective fuel assembly via the determination of the Xe131/Xe134 ratio in the primary cover gas during the third fuel assembly failure of KNK II/2 Vorlokalisierung des defekten Brennelementes ueber die Bestimmung der Isotopenverhaeltnisse 131Xe/134Xe im Primaerschutzgas waehrend des dritten Brennelementschadens KNK II/2
Stade, SchroeterKernkraftwerk-Betriebsgesellschaft mbH (Germany)
INIS-DE-KBG--016 - German - 1986
Key words: delayed neutron analysis;failed element detection;fission products;fuel element failure;isotope ratio;knk-2 reactor;neutron detection;neutron flux tilting;plutonium 239;reactor operation;reactor safety;uranium 235;xenon 131;xenon 134
R&D Category: -Failure detection
display the document: 34087485.pdf
Irradiation capsule with heat pipes for KNK II and SNR 300 Bestrahlungskapsel mit Waermerohr fuer KNK II und SNR 300
Mueller, K.;Bojarsky, E.;Norajitra, P.;Schmidt, LKernforschungszentrum Karlsruhe GmbH (Germany)
INIS-DE-PSB--061 - German - 1986
Key words: heat pipes;heat transfer;irradiation capsules;irradiation;knk-2 reactor;radiation heating;snr reactor;temperature dependence;temperature monitoring
R&D Category: any or undefined
display the document: 34087495.pdf
Behavior of the core coolant outlet temperatures of KNK II. Performed investigations, summary of the results and present status of knowledge Verhalten der Kuehlmittelaustrittstemperaturen beim Kern KNK II/2. Durchgefuehrte Untersuchungen, Zusammenfassung der Ergebnisse und gegenwaertiger Kenntnisstand
Finke, GKernkraftwerk-Betriebsgesellschaft mbH (Germany)
KBG--BL1/86 - German - 1986
Key words: cladding;deposits;friction;fuel assemblies;knk-2 reactor;reactor fueling;reactor operation;roughness;spacers;temperature distribution;temperature measurement;thermal hydraulics
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087731.pdf
Pressure drop measurements at the KNK II annular fuel element with replaceable test bundles TOAST Druckverlustmessungen am KNK II Ringbrennelement mit auswechselbaren Testbuendeln TOAST
Haefner, H.E.;Lehning, H.;Norajitra, P.;Philipp, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P15A - German - 1986
Key words: annular fuel elements;fluid flow;fuel element clusters;knk-2 reactor;pressure drop;pressure measurement;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;safety analysis;thermal hydraulics
R&D Category: any or undefined
display the document: 34087752.pdf
Material Test Elements MTE1 and MTE2 in KNK II: Design Report for the sample loadings Materialtestelemente MTE1 und MTE2 in KNK II: Auslegungsbericht fuer die Probenbeladungen
Schmidt, L.;Mueller, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.12P20A - German - 1986
Key words: breeding blankets;design;knk-2 reactor;materials testing;neutron flux;reloadable fuel assemblies
R&D Category: any or undefined
display the document: 34087767.pdf
Equipment for temperature control and test data registration for KNK II irradiation experiments Temperaturregel- und Messwerterfassungseinrichtung fuer KNK II Bestrahlungsexperimente
Lehning, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.12P20B - German - 1986
Key words: cladding;knk-2 reactor;neutron reflectors;reactor experimental facilities;sodium;temperature measurement;test facilities;testing
R&D Category: any or undefined
display the document: 34087768.pdf
Radiochemical surveillance of KNK primary sodium
Stamm, H.H. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Radiochemie);Stade, K.C. (Kernkraftwerk-Betriebsgesellschaft m.b.H., Eggenstein-Leopoldshafen (Germany, F.R.))KFK--4279 - English - 1987
Key words: contamination;corrosion products;deposition;fission products;knk-2 reactor;optimization;primary coolant circuits;radiation doses;reactor maintenance;repair
R&D Category: any or undefined
display the document: 19036786.pdf