Component Category: --Fuel assemblies
57 documents found
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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
Abstract: Within the framework of the study on the irradiation behaviour of carbide fuel rods, complete carbide fuel elements are to be tested in the fast neutron flux of the KNK II. The main data and the construction of the carbide fuel elements are presented. Some data of the KNK II carbide elements with regard to thermo-hydraulics are compared with the data of an oxide element of the type Mark II. (HR)
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
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
Abstract: not available
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
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
Abstract: A variety of basic proposals for the irradiation of test fuel elements in the test zone of KNK II are being discussed recently. As a further concretization annular fuel elements with two or three rows of oxide fuel pins for the installation of different irradiation devices are considered. In this report the layout of a carbide test bundle in a carrier element with two pin rows is proposed
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
Abstract: The fuel element NY 205 has been irradiated in the first and in the second core of KNK II up to a maximum local burnup of 18.6 % with a total residence time of 832 equivalent full-power days and a maximum local steel damage of 66 dpa-NRT. Because of a fuel pin failure it was unloaded on May 28, 1987 and carried to the Hot Cells of the Karlsruhe Research Center. The results of the post-irradiation examinations and the conclusions to be drawn are described in this report. The pin claddings, made of the steels 1.4970 and 1.4980, experienced expansion due to swelling with maxima around or just below core mid-plane. The axial redistribution of volatile fission products lead to an accumulation in the upper third of the fissile column. In this area the inner clad corrosion was most intensive with a depth of up to 130
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
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
Abstract: The report describes the driver zone fuel assemblies with moderator of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
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
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
Abstract: The sensitivity of outlet temperatures for cooling disturbances can be improved significantly by eleminating temperature noise and variations of the temperature rise of a subassembly due to inlet temperature and power noise or control of the reactor power level. This has been demonstrated at the KNK II. The different types of KNK fuel elements were modeled by individual combinations of two first-order low-pass filters, one for the fuel element and one for the thermocouple. Using a neutron detector signal as input for these filters provides simulated outlet temperature signals for comparison with the measured signals. Under stationary conditions of reactor operation these signals agreed within less than 1 K. For non-stationary conditions a more general model of the fuel element was applied. In this model time-dependent thermohydraulic parameters could be used. In this way a cooling disturbance consisting of gas bubbles in the sodium was simulated. A sensitivity study showed that gas bubbles of 1% of the sodium volume in the fuel region could be detected at KNK II in spite of the power drop caused simultaneously by the negative sodium void effect. (orig./HP)
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
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
Abstract: The carbide fuel is considered as a promising long-term alternative to the oxide fuel for fast breeder reactors. Also the KfK is working since 1968 in the frame of the fuel element development program of the Fast Breeder Project (PSB) on carbide fuels, whereby until now the main effort was spent on the carbide fabrication and the irradiation behavior of single pins. One result of these activities is the KfK carbide reference concept: low pellet density, relatively large gap and helium bonding between fuel and cladding. As completion of the past work a small carbide test bundle with 19 pins is planned to be irradiated in KNK II under sufficient representative conditions. To provide a corresponding irradiation channel, an annular oxide carrier element is being developed, which can also accommodate other test inserts in future. Characteristic design data of the carbide element are the following: pin diameter 8.5 mm, pellet diameter 7.0 mm, maximum nominal pin linear rating 800 W/cm, maximum nominal burnup 70 MWd/kgHM. Besides a short description of the combined element, the report contains the design and operational data for the test bundle and the carrier element, a first thermohydraulic design of both elements and treats the thermo-mechanical design of the carbide pins
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
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
Abstract: Several observations indicate vibrational effects in some fuel elements of the KNK-II core. This report describes how the coolant outlet temperature of each fuel element was used successfully as a means of the identification of these vibrations. As a result the cause of the sharp peaks in the power spectral density of the KNK-II reactivity noise was found. (orig.)
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
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
Abstract: The method of decladding and desintegration of fuel rods is already applicable. The paper deals with the marginal conditions relevant for the desintegration (deformations, decay heat, decontamination of fuel elements), R and D work performed by INTERATOM so far and related results. The resulting courses of desintegration for SNR-300 Mk Ia or Mk II fuel elements and first practical experience made with the desintegration of KNK-II fuel elements at the KfK's hot cells are discussed. Finally a desintegration device for SNR-300 first core fuel elements designed in accordance with the aforesaid results is presented. (orig./DG)
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
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
Abstract: The report describes the Mark II assemblies for the central position of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
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
Abstract: The report describes the driver zone fuel assemblies without moderator of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
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
Abstract: The report describes the Mark II test zone fuel assemblies of the second core of KNK II and their behavior during the operation period of 455 equivalent full-power days. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of generally valid standards for strength criteria the capacitance of the assemblies and their components is evidenced, and the fulfilment of the design criteria is shown
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
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
Abstract: For KNK II an annular carrier element with an integrated 19-pin carbide test bundle is planned to be placed on a ring position of the test zone. With regard to safety aspects, the effects of obstruction in, both, the annular element and the test bundle on the sodium outlet temperature were studied. It was found that a 60 % reduction of mass flow in the test bundle leads to a temperature increase behind the mixing device of 26 K. This value has been suggested as a limit for reactor scram in order to obviate the possibility of sodium boiling in the test bundle. For the annular element the same value already leads to reactor scram at 16 % mass flow reduction
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
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
Abstract: Design, fabrication, authorization for operation and the operation itself signify for the project partners involved the step from an research and development program to the procurment of a larger number of fuel subassemblies for a nuclear power plant. Although priority is given to operations experience, those assemblies have to be part of the long-term fuel development program. The first fast core of the KNK-II has reached a residence time of 273 efpd corresponding to a peak burnup of 65.000 MWd/tsub(HM) in 5 assemblies. By such, the originally planned target of 255 efpd has already been exceeded. The authorization for an operation up to 355 efpd has been granted. The extended periods of operation at 100% load as well as the reached burnup prove that the two fuel pin defects (in two assemblies one pin each) do not have any systematic origin. (orig.)
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
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
Abstract: The steam-nitrogen method was used for the sodium removal from undamaged KNK-I fuel elements. 66 fuel bundles (= 2904 fuel pins) with an average burn-up of 5800 MWd/tsub(HM) were cleaned using this method, four to six months after the final shut-down, during the time from December 1974 to February 1975. The sodium removal was complete. No defects originated from the cleaning procedure. The sodium removal from KNK-II and SNR-300 fuel without cladding failures will be accomplished by the same process. At KNK-II, the existing plant has to be modified before KNK-II elements may be treated. So far, two defective fuel elements (burn-up 17400 MWd/tsub(HM), and 48000 MWd/tsub(HM), respectively) have been removed from the KNK-II core. The limited sodium removal achieved by blowing with hot argon was sufficient for the following dismantling of these bundles in the KfK hot cell laboratories. (orig.)
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
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
Abstract: The reactivity signal of the KNK-II-plant shows almost harmonic oscillations of
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
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
Abstract: This report describes an annular oxide element with Mark II rods for accommodation of a 19-pin carbide test bundle on position 201 in the test zone of the second core of KNK II as well as its behavior during the period of operation. The ring element comprises within a driver wrapper in three rows of pins 102 fuel pins of 7.6 mm diameter and six structural rods for fixing the spark eroded spacers. The report deals with the ring element with its individual components fuel rod, bundle, wrappers, head and foot and describes methods, criteria and results concerning the design. The carbide test bundle to be accommodated by the annular carrier element will be treated in a separate report. The loadability of the annular element with its components is demonstrated by generally valid standards for strength criteria
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
Abstract: The present safety considerations concern the accident analysis for the KNK II annular fuel element with an integrated 19-pin carbide bundle. In the investigations those possible accidents had been selected from the total number of accidents studied for the first and second KNK II cores, in which the annular element with the carbide bundle could show an irregular behavior. The results of the analysis did not reveal an elevated risk for the irradiation of this special fuel element compared with a standard oxide fuel element
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
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
Abstract: In the frame of the fuel element failure detection experiments at KNK II with its first core the measurement devices of INTERATOM were taken into operation in August 1981 and were in operation almost continuously. Since the start-up until the end of the first KNK II core operation plugs with different fuel test areas were inserted in order to test the efficiency of the different measuring devices. The experimental results determined during this test phase and the gained experiences are described in this report and valuated. All three measuring techniques (Xenon adsorption line XAS, gas-chromatograph GC and precipitator PIT) could fulfil the expectations concerning their susceptibility. For XAS and GC the nuclide specific sensitivities as determined during the preliminary tests could be confirmed. For PIT the influences of different parameters on the signal yield could be determined. The sensitivity of the device could not be measured due to a missing reference measuring point
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
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
Abstract: From the 211 fuel pins of the KNK II/1 fuel assembly NY-202-IA six intact fuel pins were selected in addition to the defective pin for destructive post-irradiation examinations in the Hot Cells of the KfK Karlsruhe. The assembly had been unloaded due to a pin failure after 192 equivalent full-power days and a maximum burnup of 5.4 %. The main aspect of these investigations was to record the fuel and fuel pin behavior and thus to allow a comparison of the status before and after irradiation. The results can also be used for comparative calculations and adaptations of existing calculational models. This report documents in detailed form the results of the fuel and fuel pin examinations
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
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
Abstract: Since the commissioning of the KNK II reactor proposals have been elaborated to provide irradiation channels for smaller sized test elements contained in annular carrier elements. A first annular fuel element with a firmly integrated 19-rod carbide test bundle will be installed soon in an innermost ring position of the second KNK II core. In a subsequent step it is planned to develop a ring element for the third core in which the test element can be replaced at any time. This report contains, in addition to aspects related to the mentioned systems, various exchangeable concepts and a description of their characteristic features. Possible bundle configurations are indicated. Finally, proposals are made for further development work
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
Abstract: After a brief survey of the irradiation conditions of the KNK II/1 fuel pins the post-irradiation results are presented and discussed concerning cladding diameter changes, corrosion depth on the cladding inside and the cladding cracks observed. It is demonstrated that after a maximum burnup of 5.1 % cladding plastic strain and cladding inside corrosion do not considerably exceed the data known from previous pin irradiation tests. Combined mechanical and chemical interaction between fuel and cladding is considered to produce the cladding failures observed after 1.2 % and 5.1 % local burnup. In this case the low sintered density of the fuel (nominal 86.5 % of theoretical density) could play a part, but perhaps the cladding material (1.4980) is jointly responsible. The results do not give reason to question in principle the suitability of the fuel pin design applied. But on a long-term basis, it seems advisable to proceed to higher fuel density
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
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
Abstract: The fuel assembly NY-203 has been irradiated in the first core of KNK II up to a burnup of about 10 % and a residence time of 400 equivalent full-power days. The assembly contained 211 fuel pins with 6.0 mm outer diameter and fuel pellets with the composition (U0.7Pu0.3)O2.00. The cladding material was the austenitic steel 1.4988 lg. Some selected pins were examined in the hot cells of the KfK Karlsruhe. The post-irradiation examinations did not reveal any critical design aspects
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
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
Abstract: In the test zone of the second core of KNK II a first annular carrier element with an integrated 19-pin test bundle is in operation since February 1984. Starting mid 1984 another annular fuel element will be operated on the central position, which can house replaceable material test inserts. In the third core of KNK II, starting in 1986, for the first time an annular fuel element shall be inserted on the ring position 205, which can accommodate replaceable fuel test bundles. In the first step, two test bundles with 19 oxide fuel pins with 7.6 mm outer diameter are planned, for which the fuel will be fabricated according to less strict tolerances. These enlarged tolerances should allow a considerable reduction of the fuel pin fabrication costs. In addition to a detailed explanation of the goals of this tolerance-enlargement-study TOAST, the report gives a description of the annular element with its test bundles, discusses the design data and first preliminary operational data and explains the handling operations. The consequences of the enlarged tolerances on the fuel pin performance are also discussed
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
Abstract: Annular fuel elements are foreseen in KNK II as carrier elements for irradiation inserts and test bundles. For the third core a reloadable annular element on position 205 is foreseen, in which replaceable 19-pin test bundles (TOAST) shall be irradiated. The present report deals with the thermal-hydraulic design of the annular carrier element and the test bundle, whereby the test bundle required additional optimization. The code CIA has been used for the calculations. Start of irradiation of the subassembly is planned at the beginning of the third core operation. After optimization of the pin-spacer geometry in the test bundle, design calculations for both bundles were performed, whereby thermal coupling between both was taken into account. The calculated mass-flows and temperature distributions are given for the nominal and the eccentric element configuration. The calculated bundle pressure losses have been corrected according to experimental results
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
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
Abstract: For the detection of fission products in the cover gas of SNR 300 a high-resolution gamma-spectrometer with connected mini-computer is applied. The mechanical structure of the two Ge-detectors, which are positioned at two redundant gas lines, the analogous electronic and the structure of the computer with its periphery are described in this report. The concept of the software is presented, which had been developed especially for SNR 300. The start-up of the system and the calibration of the auxiliary measuring points and of the Ge-detectors are described
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
Abstract: Annular carrier elements are increasingly installed in KNK II. For the third core an annular element for material test bundles is foreseen as before on the central position 100. On the first ring position 205 another annular assembly is planned with an integrated replaceable 19-pin test bundle for the fuel tolerance-widening project TOAST. For the annular carrier assemblies and the TOAST test bundle thermal-hydraulic design calculations have been performed already. As basis for the hot channel and the hot spot analysis the standard deviations of the cooling channel temperature rise and of the linear pin power are determined for the two annular assemblies and the TOAST test bundle
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
Abstract: Within the development and test of fast breeder fuel elements, several important questions concerning the behavior under transient conditions, under overload and with fuel failures are still open. Focussed on these questions is the experimental program TETRA (Temperature Transient Experiments) foreseen at the KNK II reactor. The experimental equipment contains a measuring and control plug together with the already tested annular fuel elements as carrier element for small test bundles. The plug is fixed on top of the test bundle and allows the variation and measurement of the coolant flow and consequently of the coolant temperature. By this means, a large variety of temperature programs are possible with exact definition and control. Experiments with test bundles of 19 pre-irradiated pins are foreseen, so that on one side the pre-damage as an important parameter for the transient behavior is given, and on the other side there is the feedback within the bundle. The experiments are foreseen in the third core of KNK II. The present report is a preliminary design report for TETRA. In addition to the goals of the experimental program it contains the description of the measuring and control plug, first design and operational data as well as details of handling operations and safety considerations
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
Abstract: For the temperature transient experiments (TETRA) at KNK II the sodium flow rate of a 19-pin test bundle integrated in an annular fuel element shall be reduced and the coolant temperature consequently increased with the help of a measuring and control plug. A valve will act as orificing device. It is designed in such a way that even in closed condition a remaining mass flow will be given, with which the aimed maximum coolant temperature of 750 deg. C will be reached at the outlet of the test bundle. With the nominal mass flow of the test bundle of 1.35 kg/s and a core pressure drop of 1.33 bar, for the test operation with maximum coolant outlet temperature a minimum mass flow of 0.76 kg/s and a test element pressure drop of 0.4 bar is calculated. The experimental plug has therefore to provide a pressure drop of 0.9 bar. During the hydraulic tests the pressure drop of the plug and the characteristic of the valve had to be determined. For this purpose a test line with the same inner dimensions and installations as the plug was established and a first series of experiments was performed in a water circuit. The experiments showed that most of the pressure drop was caused by the valve. It amounts to 0.5 bar with the minimum mass flow, i.e. the aimed pressure drop of 0.9 bar is not yet reached. Further tests will be performed with smaller ring gaps of the valve. In a second series of experiments the characteristics of four valves with different geometries have been determined
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
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
Abstract: Three variants of ring elements with test bundles will be reported in this paper: In a first step a ring element was built with a permanently integrated test bundle (19 carbide pins of the Karlsruhe reference concept) while the proven fuel element components have been largely maintained. This irradiation will be completed in autumn 1986 after 380 full power days of operation. The central topic of this paper will be the technique of reloadable ring elements with replaceable test bundles. A first experiment, TOAST, is in preparation. For this experiment, above all the components of the fuel element head and foot had to be newly developed and tested. A special version of double-walled replaceable test bundles to be used in the TETRA temperature transient experiments will be briefly mentioned. It is envisaged in these experiments to vary in a defined manner the coolant flow at remotely assembled test bundles consisting of 19 KNK pins each having undergone a high burnup and to use a measuring and control plug placed on the test bundle so that a variety of fuel pin temperature programs can be realized. Finally, some additional aspects of bundle design will be indicated. (orig./GL)
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
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
Abstract: This report presents a collection of materials properties data for use in fuel performance and safety calculations and specifically for the IAMBUS and SATURN fuel behavior models. Data are given for the physical fuel properties, for the fuel behavior under irradiation and for the fuel-gap conductance. This set of material correlations was established in a common working group of KfK/INTERATOM with special respect to high density (U,Pu)O2-fuel
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
Abstract: The defective fuel assembly NY-202 of the test zone of the KNK II first core had been irradiated for further 12 days with reduced reactor power after detection of a fuel pin failure and its localization. After unloading and cooling in the sodium storage the assembly had been transported to the hot cells of the KfK Karlsruhe for post-irradiation examinations. This report summarizes the results of these examinations as well as the interpretations with respect to the general fuel and fuel pin behavior and the analysis' of causes and mechanisms of the cladding failure. The results show a normal irradiation behavior of the fuel and the fuel pins, which is conform with the expectations, with the exception of local surface abrasion of fuel pins and spacers, which is due to mechanical interactions as a special phenomenon of the first KNK II loading. The results allow the derivation of more or less clear differences in the behavior of the two fabrication campaigns differing by 1.5 years. The cladding failure can be explained with high probability by strong inner corrosion of the cladding with local corrosion due to chemical interaction with fuel impurities
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
Abstract: The report contains the material correlations and models used in the fuel pin design code IAMBUS for the irradiation behavior of PuO2-UO2 fissile materials and UO2 fertile materials of the SNR-300 Mark-II reload and the KNK II third core. They are applicable for pellet densities of more than 90 % of the theoretical density. The presented models of the fuel behavior and the applied material correlations have been derived either from single experiments or from the comparison of theoretically predicted integral fuel behavior with the results of fuel pin irradiation experiments. The material correlations have been examined and extended in the frame of the collaborations INTERATOM/KWU and INTERATOM/KfK. French and British results were included, when available from the European fast reactor knowledge exchange
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, 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
Abstract: The report describes the Mark II fuel assemblies of the first test zone ring of the third core of KNK II and their operational behavior. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of enveloping proofs the respectation of the design targets and criteria is evidenced for the foreseen residence time of 720 equivalent full-power days
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
Abstract: The report describes the assemblies of the driver zones without and with moderator of the third core of KNK II and their operational behavior. The tasks and the design of the assemblies and their individual components are described, and the criteria, methods and results of their design are presented. With the help of enveloping proofs the respectation of the design targets and criteria is evidenced for the foreseen residence time of 720 equivalent full-power days
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
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
Abstract: After the restart of the KNK II reactor in March 1986 following the replacement of a defective fuel assembly, an increased DND-signal and increased fission gas activity in the primary cover gas were observed. Comparisons with a previous small failure (a so-called leaker) indicated the existence of another leaker. During the following months several fission gas burst were observed, and in regular intervals gas probes were taken from the cover gas. This allowed the measurement of the yields of the isotopes Xe131 and Xe134, the ratio of which is different for U235 and Pu239 fission. A comparison of measured and calculated ratios could therefore allow to distinguish between a failure in the Uranium fuel of the driver zone assemblies and the Uranium/Plutonium fuel of the test zone assemblies. The average value of 10 measurements was 0.40
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
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
Abstract: An annular fuel element with replaceable 19-pin test bundles for the Tolerance Enlargement Study TOAST is planned to be operated in the third core of KNK II. Due to different reasons, the up to now used coolant mixing devices in the element head and the element foot had to be revised. Therefore the pressure drops had to be measured again to support the thermal-hydraulic design of this special subassembly and its individual components. Additionally the hydraulic suppression of the test bundle in the annular element had to be demonstrated. In parallel to that, measurements with models of original size were performed in the water circuit of the IRB. The following results can be pointed out: 1. The pressure drop of 0.2 bar of the modified mixing head at nominal flow is comparable to that of the previous design. 2. The measured total pressure drop of the annular element with test bundle is 1.37 bar at nominal flow. It agrees within 3 % with the precalculated value. The sufficiently exact precalculation of the orifices in the test bundle and the coolant partition have been confirmed also by the experiments. 3. The hydraulic suppression of the test bundle in the annular element and consequently of the total subassembly in the core assembly is guaranteed
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
KNK II: Measures to avoid abrasion damages in the test- and driver-subassemblies of the third core KNK II: Massnahmen zur Vermeidung von Verschleissschaeden in den Test- und Treiberelementen des dritten Kerns
Toebbe, H.;Wenk, K.HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07305.8 - German - 1987
Abstract: The fuel assemblies of the third core of KNK II have to be improved due to the experience and the post-irradiation examinations about the fuel element performance in the second core in order to avoid the fuel failure causing abrasion phenomenon. For this purpose modifications at the structural components are proposed and discussed, which are partly alternatively and partly additively suitable to avoid that type of failures of the second core
Key words: abrasion;deposits;fuel element failure;knk-2 reactor;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: 34085722.pdf
Summarizing presentation of non-destructive post-irradiation examinations of the fuel subassembly NY-308 of the KNK II/2 second core Zusammenfassende Darstellung zerstoerungsfreier Nachbestrahlungsuntersuchungen am Brennelement NY-308 der Zweitbeladung KNK II/2
Hess, BINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07324.3 - German - 1987
Abstract: The fuel subassembly NY-308 of the KNK II/2 Test-zone has been irradiated for further 23 equivalent full-power days (efpd) after a fuel pin failure had been detected after 250 efpd. After the necessary reduction of the decay heat, non-destructive post irradiation examinations were performed on that subassembly in the hot cells of the KfK, Karlsruhe. Their results are presented in this report. Main unexpected results were the wear-marks on fuel pin surfaces as a consequence of mechanical interaction between fuel pins and pin spacers and between neighbouring fuel pins. The location and appearance of the cladding failure indicated a causative connection of the local cladding weakening and the defect itself. Despite the continuing operation with the defect fuel pin neither an evident fuel discharge nor a failure propagation occurred. This result is a complete confirmation of the experience with the continuing operation of the defect fuel pin of the first core of KNK II
Key words: fuel element failure;fuel pins;knk-2 reactor;nondestructive testing;post-irradiation examination;reactor cores;reactor operation;spacers;wear
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085724.pdf
Summarizing presentation of non-destructive post-irradiation examinations of the moderated driver subassembly NW-302 of the KNK II/2 second core Zusammenfassende Darstellung zerstoerungsfreier Nachbestrahlungsuntersuchungen am moderierten Treiberelement NW-302 der Zweitbeladung KNK II/2
Hess, BINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07365.* - German - 1987
Abstract: The fuel subassembly NW-302 of the KNK II/2 driver zone has been irradiated for further 48 equivalent full-power days (efpd) after a fuel pin failure had been detected after 310 efpd. After the necessary reduction of the decay heat, non-destructive post irradiation examinations were performed on that subassembly in the hot cells of the KfK, Karlsruhe. Their results are presented in this report. Similarly to the fuel pins of the test zone element NY-308 wear-marks with similar axial intensity distribution were observed on the fuel pin surfaces as a consequence of mechanical interaction between fuel pins and pin spacers. The interaction between neighbouring pins was observed only between fuel pins and not between fuel and moderator pins. Additionally, locally limited rugged deposits were observed on the fuel pins, with smaller extent on the moderator pins. As a consequence of the cladding weakening, two cladding failures occurred during the reactor operation independently from each other. Neither an evident fuel discharge nor a failure propagation occurred, which is a confirmation of the former experience with the continuing operation of defect fuel pins
Key words: fuel element failure;fuel pins;hot cells;knk-2 reactor;nondestructive testing;post-irradiation examination;reactor operation;zirconium hydrides
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085725.pdf
Metallographic examinations of the wear-marks on fuel pins of the KNK II/2 fuel assembly NY-308 Metallographische Untersuchung der Reibmarken an Brennstaeben aus dem KNK II/2 Brennelement NY-308
Patzer, GINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.07415.9 - German - 1987
Abstract: On the fuel pins and pin spacers of the fuel assembly NY-308 of the second core of KNK II pronounced wear marks had been found in the area of the contact points. In order to determine the exact form of the marks, metallographic investigations were performed on two test pieces of fuel pins in the Hot Cells of the KfK Karlsruhe. It was found that the wear marks did show the already observed stratified structure. Next to the unchanged cladding area there is a peripheral zone with modified grain structure, followed by a layer of moved material and finally there is a flake-like zone of accumulated cladding material at the lower end of the wear marks. Longitudinal cuts do not show grain deformations, which could indicate axial friction forces between pin and spacer. The wear marks are rapidly dropping to their maximum depth at the ends and the depth shows a relatively uniform pattern between both. The findings are confirming the picture, that a stirring movement of the fuel pins took place, which caused adhesive wear
Key words: abrasion;cladding;destructive testing;friction;fuel pins;hot cells;knk-2 reactor;metallography;post-irradiation examination;spacers;wear
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34085727.pdf
Final report about the application of fuel element flowmeters in KNK II/2 (WZE 2.02) Abschlussbericht ueber den Einsatz von Brennelement-Durchlussmessern in der KNK II/2 (WZE 2.02)
Blasius, H.-DINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--61.04236.1 - German - 1987
Abstract: The application of fuel element flowmeters in SNR 300 requires the proof that they are working within the specified error tolerances under reactor conditions. Since a first test series was not completely successful due to an insufficiently designed experimental plug, two flowmeters were inserted into modified plugs within a second cycle of experiments. The present report deals with the results of these tests. In view of the measuring task in SNR 300, the experimental results are interpreted and the magnitude as well as the shapes of linearity errors, temperature errors and drifts are described. Disregarding an initial instability of the experimental signals, which was caused by a ferritization of the austenitic cladding steel (1.4948), it has been proved that the flowmeter fulfils the requirements within the specified error tolerances and that it is suitable for application in the SNR-300. With these tests KNK could provide an important result for decisive monitoring components of sodium cooled reactors
Key words: errors;experimental data;flowmeters;fuel elements;knk-2 reactor;reactor monitoring systems;signal conditioning;snr reactor
R&D Category: -Thermo hydraulic monitoring
display the document: 34087389.pdf
Analysis of deposits on the fuel assemblies of the KNK II second core Analyse von Ablagerungen auf den Brennelementen der KNK II Zweitcorebeladung
Kleykamp, H.;Pejsa, R.;Gottschalg, H.D.;Fritzen, R.;Kohnert, WKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.03P32B - German - 1987
Abstract: On the fuel assemblies NY-308-IA and NW-302-IA deposits have been identified via x-ray micro-analysis and x-ray diffraction, which are composed out of Fe-2.5%Cr, (Fe(1-x)Crx)3O4 and Na2CO3. With the help of phase-diagrams and thermodynamic data it could be shown, that the oxide phases have been formed after the unloading from the reactor
Key words: deposits;fuel assemblies;iron alloys;knk-2 reactor;oxides;phase diagrams;sodium carbonates;thermodynamic properties;x-ray diffraction;x-ray emission analysis
R&D Category: any or undefined
display the document: 34087761.pdf
The KNK II/1 fuel assembly NY-205: Compilation of the irradiation history and the fuel and fuel pin fabrication data of the INTERATOM data bank system BESEX Das KNK II/1 Brennelement NY-205: Zusammenstellung des Bestrahlungsverlaufs sowie der Brennstoff- und Brennstabfertigungsdaten aus dem INTERATOM Datenbanksystem BESEX
Patzer, G.;Geier, FINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07463.3 - German - 1988
Abstract: The fuel assembly NY-205 has been irradiated during the first and the second core of KNK II with a total residence time of 832 equivalent full-power days. A maximum burnup of 175.000 MWd/tHM or 18.6 % was reached with a maximum steel damage of 66 dpa-NRT. For the cladding the materials 1.4970 and 1.4981 have been used in different metallurgical conditions, and for the Uranium/Plutonium mixed- oxide fuel the most important variants of the major fabrication parameters had been realized. The assembly will be brought to the Hot Cells of the KfK Karlsruhe for post-irradiation examination in February 1988, so that the knowledge of the fabrication data is of interest for the selection of fuel pins and for the evaluation of the examination results. Therefore this report compiles the fuel and fuel pin fabrication data from the INTERATOM data bank system BESEX and additionally, an overview of the irradiation history of the assembly is given
Key words: burnup extension;cladding;data compilation;fuel assemblies;hot cells;knk-2 reactor;mixed oxide fuels;physical radiation effects;reactor cores;steels
R&D Category: Reactor physics
display the document: 34085729.pdf
Nondestructive post-irradiation examinations on fuel pins of the fuel assembly NY-305 of the second core of KNK II (status of 15.01.1988) Zerstoerungsfreie Nachbestrahlungsuntersuchungen an Brennstaeben des Brennelementes NY-305 des 2. Kerns der KNK II (Stand vom 15.01.1988)
Hess, BINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.07478.6 - German - 1988
Abstract: After detection of a fuel pin defect at 400 equivalent full-power days (efpd), the fuel assembly NY-305 of the KNK II/2 test zone had been operated for further four efpd. After reduction of the decay heat, the assembly was brought to the Hot Cells of the KfK Karlsruhe for nondestructive post-irradiation examinations. A maximum burnup of 6.3 % had been reached. As an overview, this report summarizes the performed work of the nondestructive examinations and gives a first valuation. The mechanical interaction between spacers and fuel pins shows the already known consequences: Local cladding wear in the upper spacer planes and lengtheninged pin-to-pin contacts between the 5th and 7th spacer. The axial intensity distribution of the cladding wear in the height of the spacer and the radial tendency of this wear are corresponding to the prevailing results and can be considered to be typical for this type of interaction
Key words: cladding;failed element detection;fuel assemblies;fuel pins;knk-2 reactor;nondestructive analysis;post-irradiation examination;spacers;wear
R&D Category: Thermo mechanical properties of systems during normal and beyond-design operating regimes and materials science
display the document: 34087379.pdf
KNK II, third core: Design Report of the Mark-II subassemblies of the test zone N-401 to NY-406 and NZ-401 KNK II, dritter Kern: Auslegungsbericht fuer Mark-II Elemente der Testzone N-401 bis NY-406 und NZ-401
Toebbe, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07555.0 - German - 1988
Abstract: The report describes the Mark-II subassemblies of the test zone of the KNK II third core. The design of the subassemblies is justified together with their single components: fuel pin, pin bundle, duct, head, foot and grid-plate insert. Criteria, design methods and design results of the subassemblies and the components are described, and the respectation of the design targets is proved for the foreseen residence time of 720 equivalent full-power days
Key words: calculation methods;design;ducts;fuel elements;fuel pins;knk-2 reactor
R&D Category: Reactor physics
display the document: 34087381.pdf
KNK II, third core: Design Report of the breeder assemblies NR-230R, NR-231R, NR-233D and NR-234D KNK II, dritter Kern: Auslegungsbericht fuer die Brutelemente NR-230R, NR-231R, NR-233D und NR-234D
Ricken, EINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.07630.1 - German - 1988
Abstract: The report describes the blanket assemblies of the third core of KNK II and their operational behavior. The assemblies and their individual components are described and the design criteria, design methods and design results are presented. With the help of enveloping proofs the respectation of the design targets up to the foreseen residence time of 720 equivalent full-power days is evidenced
Key words: breeding blankets;calculation methods;design;fuel assemblies;knk-2 reactor;reactor cores
R&D Category: Reactor physics
display the document: 34087384.pdf
Revised thermal-hydraulic design calculations for the annular fuel element with replaceable test bundles (TOAST) on the test zone position 205 of KNK II/3 Aktualisierte thermohydraulische Rechnungen fuer das Ringelement mit auswechselbaren Testbuendeln (TOAST) auf der Kranzposition 205 der KNK II/3
Norajitra, PKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P20A - German - 1988
Abstract: Annular fuel elements are foreseen in KNK II as carrier elements for irradiation inserts and test bundles. For the third core a reloadable annular element on position 205 is foreseen, in which replaceable 19-pin test bundles (TOAST) shall be irradiated. The present report deals with the thermal-hydraulic design of the annular carrier element and the test bundle. In a former report (Ref. 4) a thermal-hydraulic design including an optimization of the test bundle had been described. Since the boundary conditions for the annular element have changed (modified pin spacing, different power), new design calculations became necessary, which are documented in this report. In can be stated that the new temperatures of the wrapper tubes and of the claddings are smaller than those in the previous design, which means a smaller loading of the components. Furthermore, a smaller assembly temperature rise and larger pressure drops in both bundles are resulting because of the increased mass-flow
Key words: annular fuel elements;design;knk-2 reactor;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies;thermal hydraulics
R&D Category: any or undefined
display the document: 34087754.pdf
Design report for a reloadable annular fuel element NY709 und NY710 Auslegungsbericht fuer ein wiederbeladbares Ringbrennelement NY709 und NY710
Haefner, H.EKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P20C - German - 1988
Abstract: Ring-shaped carrier fuel elements had been inserted already in the second core of the KNK II reactor in positions 100 and 201. This report describes a reloadable oxide annular fuel element with Mark II pins for accommodating oxide 19-pin test bundles in the test zone position 205 in the third core of KNK II and justifies its design concept. The annular element comprises 102 fuel pins of 7.6 mm diameter arranged in three pin rows in a driver wrapper and skirts for fixing the spark-eroded spacers. In order to lower the pin power the fuel stacks have been reduced from 600 to 500 mm for a standby element envisaged for possible future loading. The report deals with the ring element with its components such as the fuel pin, the bundle, the wrappers, the head and the foot, and it describes methods, criteria and results of design. The test bundles housed in the annular carrier element are treated in a separate report. By enveloping proofs the compliance of the design goals is evidenced for the envisaged service life of 720 full power days. The report is based on the INTERATOM design report for the test zone fuel elements of the third KNK II core
Key words: annular fuel elements;fuel assemblies;fuel element clusters;irradiation devices;knk-2 reactor;mixed oxide fuels;reloadable fuel assemblies;replaceable fuel assemblies;testing
R&D Category: any or undefined
display the document: 34087755.pdf
KNK II third core: design report for replaceable 19-pin test bundles TOAST in an annular fuel element of the test zone KNK II dritter Kern: Auslegungsbericht fuer auswechselbare 19-Stab Testbuendel TOAST in einem Ringbrennelement der Testzone
Haefner, H.EKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.02P20D - German - 1988
Abstract: This report describes replaceable 19-pin oxide test bundles (TOAST) in a reloadable oxide ring fuel element at the test zone position 205 in the third KNK II core and provides justification for its design concept. The irradiation experiment is aimed at reducing the fuel pin costs by specifying less strict fabrication tolerances. It is envisaged to irradiate two test bundles with 19 oxide pins each with different parameters in the reloadable carrier fuel element for different durations of 70 and 650 equivalent full-power days, respectively. A third one will serve as stand-by reserve. To lower the pin power for a possible later use, the fuel stacks have been shortened from 600 to 500 mm. The report treats the test bundles with their components and describes methods, criteria and results of design. The ring shaped carrier element is treated separately. Compliance with the design targets is proved for the planned maximum service life of 650 equivalent full-power days by providing comprehensive evidence
Key words: annular fuel elements;design;knk-2 reactor;mixed oxide fuels;reactor experimental facilities;reloadable fuel assemblies;replaceable fuel assemblies
R&D Category: any or undefined
display the document: 34087756.pdf
First results of the THIBO experiments Erste Ergebnisse der THIBO Experimente
Reiser, H.;Schmidt, L.;Deckers, H.;Lehning, H.;Piel, DKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.01.12P98A - German - 1988
Abstract: It is assumed that the wear damages in the fuel assemblies of the second KNK II core are caused by staggering movements of the fuel pins due to azimuthal temperature differences in the fuel claddings. In order to investigate the conditions for the thermal-hydraulically induced fuel pin oscillations, the THIBO experiments are being performed since November 1987 with an electrically heated test pin in the sodium loop of the IMF III. In this report the test facility of the THIBO experiments is described and first results of two experiments are reported. In these experiments temperature fluctuations have been observed, which indicate periodic pin movements due to temperature changes
Key words: cladding;coolant loops;flow stress;fuel pins;knk-2 reactor;mechanical vibrations;oscillations;temperature dependence;temperature gradients;thermal hydraulics
R&D Category: Safety aspects
display the document: 34087769.pdf
Specialist'meeting on KNK II Failed Fuel Element Experience, Organized by AGT 1. Sumary report Spezialisten Besprechung zu Erfahrungen ueber KNK II Brennelement-Versagen, organisiert von AGT1
Plitz, HKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.11.05P37A - German - 1989
Abstract: Since fuel pin failures cannot be excluded in the coarse of operation of sodium cooled fast reactors, it is necessary to understand mechanisms and evolution of failures as well as the relationship of signal size and failure size, in order to allow and recommend operators to derive operating procedures with element failures in the reactor or in internal storages. For this goal, the organizations of the European collaboration on fast breeder R and D are exchanging their experience with fuel failures. The present meeting is one of the meetings on this issue, on which 9 papers on KNK II fuel failures were presented and discussed. The papers are collected in this report
Key words: defects;failed element detection;fuel element failure;international cooperation;knk-2 reactor;reactor safety;ruptures
R&D Category: -Failure and failure propagation mechanisms
display the document: 34086302.pdf
KNK II third core: design report for the annular fuel elements on the central position to accommodate material test inserts NZ 402 and NZ 403 KNK II 3. Kern: Auslegungsbericht fuer die Ringbrennelemente auf der Zentralposition zur Aufnahme von Materialtesteinsaetzen NZ 402 und NZ 403
Schmidt, L.;Mueller, KKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-PSB--01.11.12P06A - German - 1989
Abstract: Since August 1984 irradiation experiments with temperature controlled pressure tube probes are being performed in the central position of KNK II. This is part of a long-term experimental program for the development of irradiation resistant reactor materials, which shall also be continued in the third core. The necessary irradiation channel is provided by a special annular fuel element. The present report describes the annular fuel elements for the third core. Aspects of the subassembly design are considered on the basis of the annular element design for the second core and the standard elements of the third core. Two annular elements NZ 402 and NZ 403 (as reserve) are available. It is demonstrated that the expected loadings will allow an unperturbed operation of the annular elements on the central position of the third core
Key words: annular fuel elements;knk-2 reactor;materials testing;reactor cores;reactor materials
R&D Category: Reactor physics
display the document: 34086304.pdf
Operating experience with failed fuel elements in the Compact Sodium Cooled Research Reactor KNK II
Steiger, W.O. (Kernkraftwerk-Betriebsgesellschaft mbH, Eggenstein-Leopoldshafen (Germany, F.R.))AECL--9926(v.1) - English - 1990
Abstract: The Compact Sodium Cooled Nuclear Reactor KNK is the only fast breeder research and prototype plant in operation in the Federal Republic of Germany. It is mainly used for the testing of fuel elements, components and different instrumentation devices. This paper gives a comprehensive description of more than 10 years of operating experience with KNK fuel elements. During this time a total number of 8 element failures occurred. The development of failures is reported, their prelocation within the core as well as the identification of the defective items in the fuel handling machine by a hot-dry-sipping procedure. A new time saving method to identify defective elements is introduced. Contamination of the primary loops by the fission product Cs 137 and methods to lower this contamination by installing a cesium trap are discussed. Finally some recommendations are given on how to operate the plant if fuel element failures occur
Key words: cesium 137;failed element detection;fuel element failure;fuel elements;knk-2 reactor
R&D Category: Safety aspects
display the document: 22047672.pdf
Fuel and fuel pin behaviour in a high burnup fast breeder fuel subassembly: Results of destructive post-irradiation examinations of the KNK II/1 fuel subassembly NY-205 Brennstoff- und Brennstabverhalten in einem Hochabbrand Schnellbrueter-Brennelement: Ergebnisse aus der zerstoerenden Nachuntersuchung des KNK II/1 Brennelementes NY-205
Patzer, GINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--54.08066.4 - German - 1991
Abstract: The report gives a summarizing overview of the design characteristics, of the irradiation history and of the results of the destructive post-irradiation examinations of the fuel pins of the high-burnup fuel subassembly NY-205 of the KNK II first core. This element was operated for about 10 years and reached a maximum local burnup of 175 MWd/kg(HM) and a maximum neutron dose of 67 dpa-NRT. The main design data of this subassembly agree with those of the SNR 300 Mark-Ia, and it reached more than twice of the burnup and a similar neutron dose as foreseen for the SNR 300 fuel subassemblies
Key words: atomic displacements;burnup extension;burnup;destructive testing;knk-2 reactor;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: 34087386.pdf
Summary representation of the behaviour of the fuel subassembly outlet temperatures in KNK II/2 Zusammenfassende Darstellung zum Verhalten der Brennelementaustrittstemperaturen der KNK II/2
Heinecke, J.;Hess, BSiemens AG, Bereich Energieerzeugung, KWU (Germany)
KWU-BGL-BT--71-92-0055 - German - 1992
Abstract: During the operation of the second core of the fast test reactor KNK II the measured fuel subassembly outlet temperatures showed time dependences which did not agree with the calculated changes due to fuel burnup, reloading of fuel subassemblies and control rod movement. The differences between the measured and pre-calculated changes are illustrated in the present report, and theoretical and experimental investigations for their clarification are described. As a summary it can be stated, that metallic particles in the primary sodium are the origin for the discrepancies. They deposit in the upper part of the fuel pins and the pin spacers, thus causing an increase of the hydraulic resistance of the fuel subassemblies. The calculated temperature changes using theoretical models of the depositing process agreed with the measurements
Key words: burnup;deposits;friction;fuel assemblies;knk-2 reactor;reactor operation;temperature distribution;temperature measurement;thermal hydraulics
R&D Category: Thermo hydraulics in all operating, shut-down and accident regimes
display the document: 34086310.pdf
Irradiation experience with KNK II Fast Breeder Fuel Subassemblies Bestrahlungserfahrungen mit KNK II-Schnellbrueter-Brennelementen
Hess, BSiemens AG, Bereich Energieerzeugung, KWU (Germany)
KWU-BGL-N--22-1993-E001 - German - 1993
Abstract: During the operation of the second core of KNK II fuel pin failures occurred, which were caused by local cladding weakening due to mechanical interaction between fuel pins and pin spacers. The present report gives a summarizing presentation of the consequences of these interactions, of the experimental and theoretical investigations to clarify the reason for the interactions and of measures to reduce their consequences in the extended residence time of the second core of KNK II. This type of interaction is caused by thermo-elastic instabilities of the fuel pin bundle, and its strength depends sensitively on the geometry of the pin bundle and the pin power. Finally, measures are described, which were taken for the fuel subassemblies of the third core of KNK II to avoid the wear causing instabilities
Key words: burnup;fuel element failure;instability;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: 34086311.pdf