Published September 1995 | Version v1
Report

Overview of CSNI separate effects tests validation matrix

  • 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.