Overview of CSNI separate effects tests validation matrix
Creators
- 1. Paul Scherrer Institute, Villigen (Switzerland)
- 2. Univ. of Pisa (Italy)
- 3. Gesellschaft fuer anlagen und Reaktorsicherheit, (GRS), Garching (Germany)
Description
An internationally agreed separate effects test (SET) Validation Matrix for thermal-hydraulic system codes has been established by a sub-group of the Task Group on Thermal Hydraulic System Behaviour as requested by the OECD/NEA Committee on Safety of Nuclear Installations (SCNI) Principal Working Group No. 2 on Coolant System Behaviour. The construction of such a Matrix is an attempt to collect together in a systematic way the best sets of openly available test data for code validation, assessment and improvement and also for quantitative code assessment with respect to quantification of uncertainties to the modeling of individual phenomena by the codes. The methodology, that has been developed during the process of establishing CSNI-SET validation matrix, was an important outcome of the work on SET matrix. In addition, all the choices which have been made from the 187 identified facilities covering the 67 phenomena will be investigated together with some discussions on the data base
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, Volume 3, Sessions 12-16
- Imprint Pagination
- 1001 p.
- Journal Page Range
- p. 2303-2324.
- Report number
- NUREG/CP--0142-Vol.3
Conference
- Title
- 7. international meeting on nuclear reactor thermal hydraulics.
- Dates
- 10-15 Sep 1995.
- Place
- Saratoga, NY (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27019803
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; HYDRAULICS; OECD; REACTOR SAFETY; SAFETY ANALYSIS; TRANSIENTS; VERIFICATION; WATER COOLED REACTORS
- Descriptors DEC
- INTERNATIONAL ORGANIZATIONS; REACTORS; SAFETY
Optional Information
- Secondary number(s)
- CONF-950904--Vol.3.