Published 2006
| Version v1
Journal article
Standard problem for RELAP5 code validation for VVER-440 reactor unit
- 1. Institut problem bezopasnosti AEhS NAN Ukrainy, Kyiv (Ukraine)
Description
The results of standard problem realization are presented for RELAP5 code validation based on documented Plant data about primary to secondary leak accident occurred at VVER-440 Reactor Unit. Thermalhydraulic model as well as comparative analysis of transient progression are described. Overall conclusions about applicability of RELAP5 code to simulate transients in VVER-440 are stated
Additional details
Additional titles
- Original title (Russian)
- Стандартная проблема валидации кода RELAP5 для энергоблока с реактором ВВЭР-440
Publishing Information
- Journal Title
- Problemi Bezpeki Atomnikh Elektrostantsyij yi Chornobilya
- Journal Volume
- 6
- Journal Page Range
- p. 41-48
- ISSN
- 1813-3584
INIS
- Country of Publication
- Ukraine
- Country of Input or Organization
- Ukraine
- INIS RN
- 38038671
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; LOSS OF COOLANT; MATHEMATICAL MODELS; PRIMARY COOLANT CIRCUITS; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; ROVNO-1 REACTOR; SAFETY ANALYSIS; SECONDARY COOLANT CIRCUITS; STEAM LINES; THERMAL HYDRAULICS; VALIDATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; PIPELINES; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS