Published October 2011
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Criticality safety analysis of spent fuel storage for NPP Mochovce using MCNP5
- 1. Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Institute of Nuclear and Physical Engineering, 812 19 Bratislava (Slovakia)
- 2. SE a.s., NPP Mochovce (Slovakia)
Description
The paper presents results of nuclear criticality safety analysis of spent fuel storage for the first and second unit of NPP Mochovce. The spent fuel storage pool (compact and reserve grid) was modeled using the Monte Carlo code MCNP5. Conservative approach was applied and calculation of keff values was performed for normal and various postulated emergency conditions in order to evaluate the final maximal keff values. The requirement of current safety regulations to ensure 5% subcriticality was met except one especially conservative case. (Authors)
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Additional details
Publishing Information
- Publisher
- Kiadja and KFKI Atomenergia Kutatointezet
- Imprint Place
- Budapest (Hungary)
- ISBN
- 978-963-372-646-4
- Imprint Title
- Proceedings of the twenty-first symposium of atomic energy research on WWER physics and reactor safety
- Imprint Pagination
- 700 p.
- Journal Page Range
- p. 1-12
- Report number
- INIS-SK--2011-029
Conference
- Title
- 21. Atomic Energy Research Symposium on WWER Physics and Reactor Safety
- Dates
- 19-23 Sep 2011
- Place
- Dresden (Germany)
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Slovakia
- INIS RN
- 42105738
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BENCHMARKS; COMPUTER CALCULATIONS; CRITICALITY; DATA COVARIANCES; ENRICHMENT; ERRORS; GADOLINIUM; HEXAGONAL CONFIGURATION; ISOTOPE RATIO; MOCHOVCE-1 REACTOR; MOCHOVCE-2 REACTOR; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NUMERICAL DATA; RADIATION ACCIDENTS; REACTIVITY; REACTIVITY COEFFICIENTS; SAFETY ANALYSIS; SPENT FUEL STORAGE; VALIDATION
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; CONFIGURATION; DATA; DIMENSIONLESS NUMBERS; ELEMENTS; ENRICHED URANIUM REACTORS; INFORMATION; METALS; POWER REACTORS; PWR TYPE REACTORS; RARE EARTHS; REACTORS; STORAGE; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 14 figs.; 5 tabs; 7 refs. Imprint:Also published on CDROM 124 MBytes in PDF format