The problems of calculation of heat transfer crisis in fuel assemblies of PW reactors based on modern versions of thermohydraulic codes
- 1. Institute for Safety Problems of Nuclear Power Plants, Kyiv (Ukraine)
- 2. GP NTTsnovejshikh tekhnologij, NANU Kyiv (Ukraine)
Description
The article gives an analysis of the adequacy of computer software systems FASCICLE BM-DF and COBRA, which are designed to calculate the main parameters of the safety of water-cooled nuclear reactors. This calculation is based on determining the local thermal-hydraulic parameters of the flow of coolant in the fuel rod assembled elements. In this article introduced the results of the comparison of experiments performed to determine the distribution of the main thermal-hydraulic flow parameters characteristic of subchannels of fuel rod assembled elements with the data for calculating these parameters on the basis of declared computer codes. Particular attention is paid to the analysis of experimental and calculation data, by definition, burnout in rod fuel assembled elements
Additional details
Additional titles
- Original title (Russian)
- Проблемы расчетного определения кризиса теплоотдачи тепловыделяющих сборках реакторов WWER на основе современных версий теплогидравлических кодов
Publishing Information
- Journal Title
- Problemi Bezpeki Atomnikh Elektrostantsyij yi Chornobilya
- Journal Volume
- 22
- Journal Page Range
- p. 34-43
- ISSN
- 1813-3584
INIS
- Country of Publication
- Ukraine
- Country of Input or Organization
- Ukraine
- INIS RN
- 46029275
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CALCULATION METHODS; COMPUTERIZED SIMULATION; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAT TRANSFER; REACTOR SAFETY; THERMAL HYDRAULICS; THERMODYNAMIC PROPERTIES; TWO-PHASE FLOW; WWER TYPE REACTORS
- Descriptors DEC
- ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS