Published 2014 | Version v1
Book

CSNI separate effects test and integral test facility matrices for validation of best-estimate thermalhydraulic computer codes

Creators

  • 1. Haldenstrasse 35, 5415 Nussbaumen (Switzerland)

Description

Internationally agreed Separate Effects Test (SET) and Integral Test Facility (ITF) matrices for validation of realistic thermal hydraulic system computer codes were established. ITF development is mainly for Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). These matrices were established by sub-groups of the Task Group on Thermal Hydraulic System Behaviour as requested by the OECD/NEA Committee on Safety of Nuclear Installations (CSNI) Principal Working 2 on Coolant System Behaviour. Firstly, the main physical phenomena that occur during considered accidents are identified, test are specified, and test facilities suitable for reproducing these aspects are selected. Secondly, a list of selected experiments carried out in these facilities has been set down. The criteria to achieve the objectives are outlined. In this paper some specific examples from the SET and ITF matrices will also provided. In addition, a short summary on the status of validation matrices for Russian Pressurised Water-cooled and Water-moderated Energy Reactor (WWER) is presented. The matrices will be a guide for code validation, will be a basis for comparisons of code predictions performed with different system codes, and will contribute to the quantification of the range of code model predictions. In addition to this objective, the construction of such a matrix is an attempt to record information which has been generated around the world over the last 30 years, so that it is more accessible to present and future workers in that field than would otherwise be the case. (author)

Part of:
Proceedings of the GCNEP-IAEA course on natural circulation phenomena and passive safety systems in advanced water cooled reactors. V.2

Additional details

Publishing Information

Publisher
Global Centre for Nuclear Energy Partnership
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the GCNEP-IAEA course on natural circulation phenomena and passive safety systems in advanced water cooled reactors. V.2
Imprint Pagination
[522 p.]
Journal Page Range
49 p.

Conference

Title
GCNEP-IAEA course on natural circulation phenomena and passive safety systems in advanced water cooled reactors
Dates
29 Sep - 3 Oct 2014
Place
Mumbai (India)

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
47003022
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
HEAT TRANSFER; LOSS OF COOLANT; NATURAL CONVECTION; TEST FACILITIES; THERMAL HYDRAULICS; WATER MODERATED REACTORS
Descriptors DEC
ACCIDENTS; CONVECTION; ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; REACTOR ACCIDENTS; REACTORS

Optional Information

Notes
13 refs., 12 tabs.