SCAR - Post-Accident Simulator SIPA with safety analysis code CATHARE-2 and PWR cold shutdown state simulation
Creators
- 1. CEA Grenoble, 38 (France). Dept. de Thermohydraulique et de Physique
- 2. Electricite de France, 75 - Paris (France)
- 3. Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France)
Description
The use of Cathare in the simulators of pressurized water reactors has been effective since the beginning of the nineties. Scar project is the second stage of the Cathare strategy for the simulators, its main objective is the extension of the field of simulation to the accident situations in cold shutdown states. Work was carried out in 3 major areas: modelling, optimization and integration in the simulator. Throughout the project, the developments were part of a 3 stages validation strategy: -) elementary tests of the developments of new model on the N4 (1450 MW PWR); -) analytical tests and systems to ensure non regression of the validation of the physical laws of the Cathare code during the modifications carried out within the optimization stage; and -) overall tests of the SIPA-CP1 (900 MW PWR) simulator, controlled automatically by programmed scenarios including the transients which are carried out in PWR, the transients of the Regulatory Guides and the accident transients
Availability note (English)
Available from INIS in electronic formFiles
35106313.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- INIS-FR--2675
Conference
- Title
- International conference on supercomputing in nuclear applications SNA'2003
- Dates
- 22-24 Sep 2003
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 35106313
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SIMULATORS; VALIDATION
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; POWER REACTORS; REACTORS; SIMULATION; SIMULATORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS