Component Category: -Monitoring systems, their circuits and electronics
16 documents found
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Test of In-core Flux Detectors in KNK II
Hoppe, P.;Mitzel, FKernforschungszentrum Karlsruhe GmbH (Germany)
INIS-DE-PSB--010 - English - 1979
Abstract: The development of in-core detectors for Liquid Metal Fast Breeder Reactors (LMFBRs) is still in an early stage, and little operation experience is available. Therefore self-powered neutron and gamma detectors and neutron sensitive ionization chambers -especially developed for LMFBRs- have been tested in the Fast Sodium Cooled Test Reactor KNK II. Seven flux detectors have been installed in the core of KNK II by means of a special test rig. Five of them failed already within the first week during operation in the reactor. Due to measurements of electrical resistances and capacities, sodium penetrating into the detectors or cables probably seems to be the cause. As tests prior to the installation in the core proved the tightness of all detectors, it is suspected that small cracks have developed in the detector casings or in the outer cable sheaths during their exposure to the hot coolant. Two ionization chambers did not show these faults. However, one of them failed because the saturation current plateau disappeared and the other one's sensitivity decreased by a factor of five during the test period. It is suspected that in both cases changes of the filling gas might be involved
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
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
Abstract: The first test of an experimental radionuclide trap was performed at KNK II. The aim was to remove some Zn-65 and Mn-54 from the primary sodium. The 2.3 l trap was filled with stainless steel and nickel pallrings of different sizes and was operated for 100 hours at 312 ''0C and a flow rate of 1.6 m''3 Na/h. On the Ni samples 110 times the amount of Mn-54 and 440 times the amount of Zn-65 have been sorbed compared to stainless steel pallrings of the same size. The activity sorbed was proportional to the surface area
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
Abstract: During a period of two years fuel element test probes (fetp), temperature measurement probes as well as piezoelectric and magnetostrictive sound recorders (psr and msr) have been tested in KNK II/1 under reactor conditions. The probes had been installed in two experimental plugs, which were inserted into the two rotating plugs of the plant. The two fetp, the two msr and all 10 encased thermocouples have endured the test without damage and did work satisfactorily during the whole test period. Five of the twelve three-wire thermocouples failed, the measuring tip of which was directly exposed to the sodium over a length of about 3 mm. The reason for the failure was the ingress of sodium, which in one case moved up inside the insulation for about five meters. In the two psr the oxygen had leaked from the noble-metal casing, causing a decomposition of the Lithium-Niobate slices and consequently the failure of the sound recorders after about 2000 hours of operation. It was possible to prove, that an adjustment of the fetp is possible in the reactor. However the experimental plugs had an unfavourable hydraulic design, so that a proof of the operational efficiency within the error margins was not possible due to velocity fluctuations
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
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
Abstract: This report describes the analysis of the delayed neutron signals before and during the flux tilting campaign to localize the third defected fuel subassembly in KNK II. Including the measurements of the composition of the Xe isotopes, the number of suspect subassemblies could be reduced from 29 to 2. By this way the extent of handling operations for the final location in the fuel handling machine could be reduced drastically. The experience obtained is of importance not only for KNK II and SNR 300, but also in general with respect to the evaluation of alternative location methods less expensive than methods used so far
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
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
Abstract: The simulation of system control of LMFBRs is quite essential for design and licensing of such facilities. This report presents the numerical models for the simulation of controller parts, which have been tested in conjunction with the SSC-L code for the experimental breeder KNK II. The good agreement between calculation and measurement proves the principal usability of the proposed models for the required task. (orig.)
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
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
Abstract: At the Karlsruhe Nuclear Research Center the microcomputer-based reactor protection system MIRA is being developed for the KNK II, a 20 MWe experimental LMFBR. The protection system's objective is individual core outlet temperature surveillance and output of a scram signal as soon as a single outlet temperature leaves the defined safety region. Besides it generates warning messages concerning any anomalies within the protection system itself as well as in the reactor core. These messages are issued to a protocol system which provides the operators with detailed informations on the actual state of the protection system and the reactor core. These informations are given as textual messages on operator console and printer and as diagrams on a colour graphics display. The protocol system helps in detecting cooling disturbances at an early stage and it eases the localization of faults within the protection system, thus providing for a quick repair. After a brief description of the MIRA configuration this paper presents the hardware and software structure of the protocol system and the generated outputs. (author)
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
Abstract: Fuel cladding defects cannot be avoided in nuclear power plant operation. In the worst case they may lead to loop contamination or to local cooling disturbance. Especially in case of the liquid metal cooled fast breeder reactor, continuation of plant operation or power set back calls for an expert who possesses comprehensive knowledge of (a) detection and location of failed subassemblies, (b) behavior of failed subassemblies, and (c) questions of safety of the plant while operated with faulty subassemblies. Since such an expert cannot be permanently available, it is intended to transfer this expert knowledge to the COCOSS 'Consulting Core Surveillance System'. This report gives a description of the status of COCOSS as operated at present at KNK II as a measuring data acquisition and evaluation system. In the final stage of implementation COCOSS - inserted in a large diagnosis system - is to make the same calculations for the reactor operator and to give him the same recommendations as he receives now from an expert commanding of an extensive knowledge in this specialized field. (orig.)
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
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
Abstract: The present report documents the calculational evaluation of the measured activation rates of Fe/Ti-foils and the measured axial and radial distribution of the activity within the Co-probe in the Material Test Element MTE 1 on position 517 of KNK II after irradiation in the first core and in the second core until 517 equivalent full-power days. The evaluation of the different activated isotopes (Co60, Sc46, Mn54) gives consistent results. The values agree well with the results of the design calculations. The axial distribution of the Co-activation also shows very good agreement with the theoretical results. All together, the present evaluation of the neutron dosimetry is a valuable confirmation of the design methods
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
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
Abstract: In the central position of KNK II electrically heated cladding samples are being irradiated under high temperature and inner pressure loadings. Further irradiation samples are in heated and instrumented sodium-filled capsules in a reflector position. In the present report the measuring and control equipment, which is necessary for the operation and surveillance of this irradiation device, and its use are described
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
Continuous post-scram control for KNK II Unterbrechungsfreie Nachscramregelung fuer KNK II
Niebel, HINTERATOM GmbH, Bergisch-Gladbach (Germany)
IA--70.04243.8 - German - 1988
Abstract: On suggestion of the operating utility the present report discusses the feasibility and the expected advantages of a modification of the post-scram control and regulation system of KNK II. In the present procedure several different process controlled phases are passed after each scram, whereas in the alternative concept a continuously working post-scram control is proposed, very similar to the SNR 300 concept. In this concept the coolant flow rates are adapted to the actual situation of the core, such as loading, power history and burnup, thus avoiding the disadvantages of a flow rate control without feedback, as applied in the present KNK II concept. The modification of the post-scram control has to be designed and verified by a series of dynamic analysis, and in parallel to that the electrotechnical planning and realization can be done
Key words: flow rate;fluid flow;knk-2 reactor;reactor control systems;reactor safety;scram
R&D Category: Reactor physics
display the document: 34087393.pdf
Acoustic measurements for boiling detection in the KNK II reactor. Akustische Messungen zur Siededetektion in der KNK II
Aberle, JKernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung;Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Schneller Brueter
KFK--4580 - German - 1989
Abstract: With regard to an integral core surveillance in sodium-cooled breeder reactors acoustic measurement techniques are under development. To determine experimentally the acoustic transfer function of a reactor core and to demonstrate the detectability of local sodium boiling, experiments with a so-called Boiling Generator were carried out in the KNK II reactor. The main part of this Boiling Generator was an electrically heated pin bundle which was equipped with a local blockage to obtain cooling disturbances. The results of the acoustic measurements carried out with the Boiling Generator are presented. Main topic of the evaluation is the determination of the acoustic transfer function between the core and the upper sodium plenum. The signal conditioning necessary prior to this investigation is also explained. Great effort was required to suppress electrical disturbances that superimposed the acoustic signals and which could not be eliminated by the hardware during the experiments. The boiling noise is compared to static and transient parasitical noise which is to be expected in a reactor. Finally the detectability of local boiling using acoustic measurements is considered. Furthermore the chance to localize the boiling region within the reactor core is discussed on the base of the acoustic boiling signals measured in KNK II. (orig.)
Key words: acoustic monitoring;boiling detection;in core instruments;knk-2 reactor;lmfbr type reactors;reactor monitoring systems;sodium
R&D Category: Safety aspects
display the document: 20085700.pdf
A knowledge based on-line diagnostic system for the fast breeder reactor KNKII
Eggert, H.;Scherer, K.P.;Stiller, P. (Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.). Inst. fuer Datenverarbeitung in der Technik)IWGFR--71 - English - 1989
Abstract: In the nuclear research center at Karlsruhe, a diagnostic expert system is developed to supervise a fast breeder process (KNKII). The problem is to detect critical phases in the beginning state before fault propagation. The expert system itself is integrated in a computer network (realized by a local area network), where different computers are involved as special detection systems (for example acoustic noise, temperature noise, covergas monitoring and so on), which produce partial diagnoses, based on intelligent signal processing techniques like pattern recognition. Additional to the detection systems a process computer is integrated as well as a test computer, which simulates hypothetical and real fault data. On the logical top level the expert system manages the partial diagnoses of the detection systems with the operating data of the process computer and to produce a final diagnosis including the explanation part for operator support. The knowledge base is developed by typical Artificial Intelligence tools. Both fact based and rule based knowledge representations are stored in form of flavors and predications. The inference engine operates on a rule based approach. Specific detail knowledge, based on experience about any years, is available to influence the decision process by increasing or decreasing of the generated hypotheses. In a meta knowledge base, a rule master triggers the special domain experts and contributes the tasks to the specific rule complexes. Such a system management guarantees a problem solving strategy, which operates event triggered and situation specific in a local inference domain. (author). 3 refs, 6 figs, 2 tabs
Key words: algorithms;computer networks;expert systems;knk-2 reactor;man-machine systems;on-line systems;reactor monitoring systems;reactor operators
R&D Category: -Analytic and numeric methods
display the document: 21064542.pdf
The KNK II instrumentation for global and local supervision of the reactor core
Steiger, W.OKernkraftwerk-Betriebsgesellschaft mbH, Eggenstein-Leopoldshafen (Germany, F.R.)
INIS-mf--12151 - English - 1990
Abstract: After an introduction into the KNK plant itself, their historical development and their present situation, the instrumentation of the global and local supervision of the KNK II-core as well as the main safety-related i- and c-systems are described. Special emphasis is laid on the instrumentation of the reactor protection systems and the shutdown systems. After that some practices are reported about instrumentation behavior and lessons learned from the operation and maintenance of the above mentioned systems. At last follows a short description of the special instrumentation for the detection of failed fuel subassemblies and of the plant data processing system. (orig.)
Key words: in core instruments;knk-2 reactor;reactor control systems;reactor monitoring systems;reactor protection systems;reactor safety;reactor shutdown
R&D Category: any or undefined
display the document: 21094863.pdf
Background- and simulated leak-noise measurements on ASB-loop, KNK II- and SNR 300-steam generators
Voss, J.;Arnaoutis, N.;Foerster, K.;Moellerfeld, H. (Internationale Atomreaktorbau GmbH (INTERATOM), Bergisch Gladbach (Germany, F.R.))IWGFR--79 - English - 1990
Abstract: During several leak propagation experiments in the ASB sodium loop noise measurements were performed showing the acoustic behaviour of evoluting leaks in a tube bundle section under sodium. Effects like self evolution, secondary leaks and tube ruptures by overheating occurred during these tests and were reflected in the course of acoustic signals. In one of the KNK II steam generators simulated leak noise was detected against background noise throughout the operating power range. Experimental arrangements and results are described. In SNR 300 all of the SGUs are equipped with waveguides and some with accelerometers for background noise measurements. First measurement under isothermal conditions were performed in the past. A gas injection device for acoustic leak simulation is under construction. The design of the experimental acoustic system and first results are presented. (author). 1 ref., 21 figs, 2 tabs
Key words: acoustic monitoring;background noise;experiment planning;knk-2 reactor;leaks;signal-to-noise ratio;simulation;snr reactor;steam generators
R&D Category: Safety aspects
display the document: 22091454.pdf
Progress in the Development of the Consulting Core Surveillance System COCOSS for KNK Weiterentwicklung des Consulting Core Surveillance System COCOSS an der KNK
Hoffmann, GKernforschungszentrum Karlsruhe GmbH (Germany)
PSB--18.01.06P01A - German - 1990
Abstract: A very flexible data collecting and evaluation system is necessary to develop and test methods for detection and localization of fuel subassembly cladding failures in LMFBR's and to make predictions on their further development. For this purpose a new version of COCOSS (Consulting Core Surveillance System) has been developed and installed at KNK II. The new features of COCOSS are described in this report. The measuring system consists of two components, a data acquisition system in the experimenter room of the KNK II and a data evaluation computer in the IRE. The data acquisition computer at the KNK II is connected via a modem line to the evaluation computer. Several I/O-devices for monitoring the evaluation computer and for output of measuring results are connected from the KNK II to IRE with further modem lines. An 'emergency program' for evaluating the measured data is started automatically at the acquisition computer if the data line or the computer at the IRE is not available. By this way continuous data acquisition and evaluation is assured
Key words: computerized control systems;data acquisition systems;evaluated data;failed element detection;fuel element failure;knk-2 reactor;reactor control systems;reactor safety
R&D Category: Reactor physics
display the document: 34086371.pdf
Description of the integral calibration test of the KNK II DND system and safety report Beschreibung des integralen Eichtests des KNK II DND-Systems und Sicherheitsbericht
Schmitz, GKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-IRE--5/325/91 - German - 1991
Abstract: Integral calibration of the DND system of KNK II shall be carried out by inserting a fission product source of a U-Ni alloy into the reactor subassembly positions 100 and 511. Fission product release from this source takes place by recoil. Thus, the release rate can be determined. In this report, both the experimental set-up and the test program are described. Furthermore, it shall be demonstrated that the reactor safety is not adversely affected by this experiment
Key words: delayed neutron analysis;fission product release;fuel assemblies;knk-2 reactor;neutron detection;nickel alloys;reactor operation;reactor safety;safety analysis;uranium alloys
R&D Category: Safety aspects
display the document: 34087747.pdf