Simulation of the CORA-W2 experiment by modified ICARE2-V2mod1 in the frame of OECD-CSNI ISP-36. Results of a blind calculation
Description
The results are presented of a blind calculation of CORA-W2 Experiment by modified ICARE-V2mod1 performed at the Nuclear Research Institute, Rez in the frame of the OECD-CSNI International Standard Problem (ISP) No. 36. The objective of the ISP-36 was to analyze the heatup and meltdown phase of the CORA-W2 Experiment (containing a WWER-1000 test bundle) performed at KfK Karlsruhe. The thermohydraulic, heat transfer, and chemical interaction models are briefly described used in the ICARE2-V2mod1. Code modifications, nodalization of the CORA-W2 bundle, input parameters and other modeling assumptions are also described. The main code modification consists in the implementation of two recently developed chemical interaction models. Calculated results are presented in the form as required by ISP-36 Specifications. 52 figs., 19 refs
Availability note (English)
Available from Ustav jaderneho vyzkumu Rez a.s., 250 68 Rez, Czech Republic.Additional details
Publishing Information
- Imprint Pagination
- [54 p.].
- Report number
- UJV--10239-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 27037848
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BOUNDARY CONDITIONS; CHEMICAL REACTIONS; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; FLOW MODELS; FUEL ELEMENT CLUSTERS; FUEL RODS; HEAT TRANSFER; I CODES; LOSS OF FLOW; MELTDOWN; TIME DEPENDENCE; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUEL ELEMENTS; MATHEMATICAL MODELS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS