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AbstractAbstract
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1971; 20 p
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AbstractAbstract
[en] A summary is presented of the Skoda JS rod drop reactivity measurements analysis provided during last two years based on control rod worth measurements by the outer ion chambers. Standard analysis based on comparisons of dynamics macrocode MOBY-DICK-SK and experimental data is extended to the 8-th group delayed neutron structure and new features of rod drop process are investigated. (author)
Primary Subject
Source
802 p; ISBN 963-372-616-6; ; 1999; p. 381-393; 9. Symposium of AER; Demaenovska Dolina (Slovakia); 4-8 Oct 1999; 10 refs.
Record Type
Book
Literature Type
Conference; Numerical Data
Country of publication
COMPUTER CODES, CONTROL SYSTEMS, DATA, ENRICHED URANIUM REACTORS, EVALUATION, INFORMATION, MEASURING INSTRUMENTS, METERS, NEUTRON TRANSPORT THEORY, NUMERICAL DATA, POWER REACTORS, PWR TYPE REACTORS, RADIATION DETECTORS, REACTORS, SAFETY, THERMAL REACTORS, TRANSPORT THEORY, WATER COOLED REACTORS, WATER MODERATED REACTORS, WWER TYPE REACTORS
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Veverka, O.; Valenta, V.; Krysl, V.
Skoda, Plzen (Czechoslovakia). Zavod Vystavba Jadernych Elektraren1975
Skoda, Plzen (Czechoslovakia). Zavod Vystavba Jadernych Elektraren1975
AbstractAbstract
[en] The numerical analysis of the boundary condition on a finite circular cylindrical cavity with cylindrical symmetry is given. The physical and mathematical formulation was given in the previous paper ZJE-173. The formulation is given in both the P1-approximation and the diffusion approximation. The P1-approximation of the problem is defined in an effective diffusion model with effective constants and sources. Replacing these effective constants and sources by the usual definitions we obtain the usual diffusion approximation. This formulation is convenient for programming, as the P1-approximation code makes possible its immediate use as a diffusion code. (author)
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Source
1975; 40 p
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Report
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AbstractAbstract
[en] Results are presented of the first three-dimensional hexagonal dynamic AER benchmark problem. Detailed results calculated with dynamics version of code MOBY-DICK-SK (Short Kinetics) for the first dynamic AER benchmark problem are presented. (author)
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Secondary Subject
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766 p; ISBN 963-372-615-8; ; 1998; p. 471-480; 8. Symposium of VVER reactor physics and reactor safety; Bystrice nad Perstejnem (Czech Republic); 21-25 Sep 1998; 4 refs.
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Book
Literature Type
Conference; Numerical Data
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Veverka, O.; Valenta, V.; Krysl, V.
Skoda, Plzen (Czechoslovakia). Zavod Vystavba Jadernych Elektraren1975
Skoda, Plzen (Czechoslovakia). Zavod Vystavba Jadernych Elektraren1975
AbstractAbstract
[en] An analytical formulation of the boundary condition for a circular vacuum-cavity boundary in cylindrical symmetry is given. The boundary condition and the symmetry conditions are considered for both infinite and finite cavity. (Z.M.)
Primary Subject
Source
1975; 33 p
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Report
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INIS VolumeINIS Volume
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Valenta, V.; Veverka, O.; Krysl, V.
Skoda, Plzen (Czechoslovakia). Zavod Vystavba Jadernych Elektraren1971
Skoda, Plzen (Czechoslovakia). Zavod Vystavba Jadernych Elektraren1971
AbstractAbstract
No abstract available
Primary Subject
Source
1971; 60 p
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Report
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AbstractAbstract
[en] In some cases control rod worth efficiencies evaluated by inverse point kinetics from our-core detector currents remarkable differ from direct calculations. Explanation of this effects is given and is supported by the analysis of some VVER-440 rod drop experiments. (author)
Primary Subject
Secondary Subject
Source
766 p; ISBN 963-372-615-8; ; 1998; p. 545-555; 8. Symposium of VVER reactor physics and reactor safety; Bystrice nad Perstejnem (Czech Republic); 21-25 Sep 1998; 7 refs.
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Book
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Conference
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AbstractAbstract
[en] Validation is based on comparisons and analysis of calculational results and experimental values of basic physical parameters of core and it is a basic task which have been performed as a evidence of possibility of use of computer code (with an appropriate library of macroscopic cross sections) for given purposes. Comparison of calculation results and experimental data for the following items is provided: boric acid concentration (statistical analyses for 42 cycles) and some additional start up states; relative power distribution (for selected cycles) Unit 1; reactivity coefficients (for chosen states); control rods worth. Results obtained are discussed and some issues are given. (author)
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Secondary Subject
Source
802 p; ISBN 963-372-616-6; ; 1999; p. 65-77; 9. Symposium of AER; Demaenovska Dolina (Slovakia); 4-8 Oct 1999; 3 refs.
Record Type
Book
Literature Type
Conference; Numerical Data
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Svarny, J.; Krysl, V.; Mikolas, P.; Vacek, J.
Advanced calculational methods for power reactors and LWR core design parameters1992
Advanced calculational methods for power reactors and LWR core design parameters1992
AbstractAbstract
[en] The paper presents the main principles and safety criteria stipulated in the Regulations of the Czechoslovak Atomic Energy Commission and methodology of the Final Safety Analysis Report with the emphasis on the normal operation and impairment of normal operation. The code system that is used in Skoda Plzen for reactor safety analysis for WWER-type reactor is described and a brief a description of WWER core and its mechanical design with basic project principles is given. (author). 9 refs, 1 fig., 2 tabs
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Secondary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 391 p; ISSN 1011-4289; ; Dec 1992; p. 327-333; Technical committee meeting and workshop on LWR core design parameters; Rez (Czechoslovakia); 7-11 Oct 1991
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Krysl, V.; Mikolas, P.; Svarny, J.
Advanced calculational methods for power reactors and LWR core design parameters1992
Advanced calculational methods for power reactors and LWR core design parameters1992
AbstractAbstract
[en] This paper presents an overview of the new library for the Skoda multidimensional static computer program, MOBY-DICK, for core analysis. MOBY-DICK predictive capability was assessed by comparing its predictions of boron concentration and assembly power distributions against appropriate measured data. The first unit of the Kalinin Nuclear Power Plant (NPP) (so called serial version of WWER-1000) represents best documented test for WWER-1000. We have proposed for comparison of MOBY-DICK prediction versus core follow measurement two first cycles of that unit. (author). 4 refs, 2 figs
Primary Subject
Secondary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 391 p; ISSN 1011-4289; ; Dec 1992; p. 385-388; Technical committee meeting and workshop on LWR core design parameters; Rez (Czechoslovakia); 7-11 Oct 1991
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Report
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Conference
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