R&D Category: -Analytic and numeric methods
6 documents found
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INTERATOM Program: Program DLS
GroenefeldInternationale Atomreaktorbau G.m.b.H. (INTERATOM), Bensberg/Koeln (Germany, F.R.)
ORNL-tr--4007 - English - 1976
Abstract: Input for the two-dimensional shielding code DLS is explained in detail. Rotationally symmetrical geometries with gaps or other cavities can be investigated conveniently with this code. The calculation of the upper axial shield of the KNK-II reactor with the DLS code is included by way of example
Key words: cavities;computer codes;d codes;fortran;knk-2 reactor;neutron transport;shielding;two-dimensional calculations
Components Category: Reactor components
display the document: 08305027.pdf
Transfer functions between the central fuel temperature, the cladding temperature and the power of fuel assemblies Uebertragungsfunktionen zwischen der zentralen Brennstofftemperatur und der Huellrohrtemperatur sowie der Leistung von Brennelementen
Ferranti, P.;Mitzel, FKernforschungszentrum Karlsruhe GmbH (Germany)
KFK-INR--01.24.9/3 - German - 1977
Abstract: For the analysis of experiments, in which the heat transfer between fuel and cladding shall be deduced from the variations of the central fuel temperature, the surrounding cladding temperature and the power, the transfer functions between these parameters are required. They have been calculated in the frame of a formerly applied model. The provision of a special version of an existing computer program allowed the numerical calculation. Input data description and test sample are given
Key words: boiling detection;calculation methods;fuel elements;heat transfer;in core instruments;knk-2 reactor;temperature monitoring;transfer functions
Components Category: --Fuel and cladding
display the document: 34087742.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
Components Category: -Monitoring systems, their circuits and electronics
display the document: 17062681.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
Components Category: -Monitoring systems, their circuits and electronics
display the document: 21064542.pdf
IAMBUS, a computer code for the design and performance prediction of fast breeder fuel rods
Toebbe, HINTERATOM GmbH, Bergisch Gladbach (Germany)
IA--54.08000.1 - English - 1990
Abstract: IAMBUS is a computer code for the thermal and mechanical design, in-pile performance prediction and post-irradiation analysis of fast breeder fuel rods. The code deals with steady, non-steady and transient operating conditions and enables to predict in-pile behavior of fuel rods in power reactors as well as in experimental rigs. Great effort went into the development of a realistic account of non-steady fuel rod operating conditions. The main emphasis is placed on characterizing the mechanical interaction taking place between the cladding tube and the fuel as a result of contact pressure and friction forces, with due consideration of axial and radial crack configuration within the fuel as well as the gradual transition at the elastic/plastic interface in respect to fuel behavior. IAMBUS can be readily adapted to various fuel and cladding materials. The specific models and material correlations of the reference version deal with the actual in-pile behavior and physical properties of the KNK II and SNR 300 related fuel rod design, confirmed by comparison of the fuel performance model with post-irradiation data. The comparison comprises steady, non-steady and transient irradiation experiments within the German/Belgian fuel rod irradiation program. The code is further validated by comparison of model predictions with post-irradiation data of standard fuel and breeder rods of Phenix and PFR as well as selected LWR fuel rods in non-steady operating conditions
Key words: cracks;friction;fuel assemblies;fuel rods;fuel-cladding interactions;i codes;international cooperation;knk-2 reactor;mechanical properties;snr reactor;steady-state conditions;thermal analysis;transients
Components Category: --Fuel pins
display the document: 34087385.pdf
Resolution of the transport equation in CRONOS code. Resolution de l'equation de transport dans le code CRONOS
Fedon-Magnaud, CCEA Centre d'Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie
CEA-N--2751 - French - 1994
Abstract: The general ideas which are applied to introduce the resolution of the neutron transport equation in CRONOS code are given in this paper. They are: - the even parity formulation. - the symmetry boundary treatment. - an angle condensation acceleration. The first qualifying results are also presented. (author). 15 refs., 14 figs., 9 tab
Key words: benchmarks;c codes;control elements;fbr type reactors;finite difference method;finite element method;knk-2 reactor;marshak boundary conditions;neutron diffusion equation;neutron flux;neutron transport;quadratures;reactor cores;reflection;three-dimensional calculations;two-dimensional calculations
Components Category: any or undefined
display the document: 27058440.pdf