Published July 1996 | Version v1
Report Open

CSNI Integral test facility validation matrix for the assessment of thermal-hydraulic codes for LWR LOCA and transients

Creators

Description

This report deals with an internationally agreed integral test facility (ITF) matrix for the validation of best estimate thermal-hydraulic computer codes. Firstly, the main physical phenomena that occur during the considered accidents are identified, test types are specified, and test facilities suitable for reproducing these aspects are selected. Secondly, a life of selected experiments carried out in these facilities has been set down. The criteria to achieve the objectives are outlined. 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, including quantitative assessment of uncertainties in the modelling of phenomena by the codes. In addition to this objective, it is an attempt to record information which has been generated around the world over the last 20 years so that it is more accessible to present and future workers in that field than would otherwise be the case

Files

41025222.pdf

Files (21.7 MB)

Name Size Download all
md5:55b6cba7a956a159202837951cb85a93
21.7 MB Preview Download

Additional details

Publishing Information

Imprint Pagination
388 p.
Report number
NEA-CSNI-R--1996-17

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
41025222
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ACCURACY; COMPARATIVE EVALUATIONS; COMPUTER CODES; DATA ANALYSIS; DATA COVARIANCES; ERRORS; LOSS OF COOLANT; NEA; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR OPERATION; REACTOR SAFETY; SAFETY ENGINEERING; SAFETY MARGINS; TEST FACILITIES; THERMAL HYDRAULICS; VALIDATION; VERIFICATION
Descriptors DEC
ACCIDENTS; ENGINEERING; ENRICHED URANIUM REACTORS; EVALUATION; FLUID MECHANICS; HYDRAULICS; INTERNATIONAL ORGANIZATIONS; MECHANICS; OECD; OPERATION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
15 refs.
Secondary number(s)
OCDE-GD--1997-12