Methodology, status and plans for development and assessment of Cathare code
Description
This paper presents the methodology, status and plans for the development, assessment and uncertainty evaluation of the Cathare code. Cathare is a thermalhydraulic code developed by CEA (DRN), IPSN, EDF and FRAMATOME for PWR safety analysis. First, the status of the code development and assessment is presented. The general strategy used for the development and the assessment of the code is presented. Analytical experiments with separate effect tests, and component tests are used for the development and the validation of closure laws. Successive Revisions of constitutive laws are implemented in successive Versions of the code and assessed. System tests or integral tests are used to validate the general consistency of the Revision. Each delivery of a code Version + Revision is fully assessed and documented. A methodology is being developed to determine the uncertainty on all constitutive laws of the code using calculations of many analytical tests and applying the Discrete Adjoint Sensitivity Method (DASM). At last, the plans for the future developments of the code are presented. They concern the optimization of the code performance through parallel computing - the code will be used for real time full scope plant simulators - the coupling with many other codes (neutronic codes, severe accident codes), the application of the code for containment thermalhydraulics. Also, physical improvements are required in the field of low pressure transients and in the modeling for the 3-D model
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements
- Imprint Pagination
- 824 p.
- Journal Page Range
- p. 72-93.
- Report number
- NUREG/CP--0159
Conference
- Title
- Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements.
- Dates
- 5-8 Nov 1996.
- Place
- Annapolis, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29024716
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; HYDRAULICS; MODIFICATIONS; PWR TYPE REACTORS; SAFETY ANALYSIS; THERMAL ANALYSIS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- NEA/CSNI/R--(97)4; CONF-961192--.