Published July 2002 | Version v1
Report

Validation of the MELCOR 1.8.5 and SCDAP/RELAP5 codes and review of the MAAP models. Validation problem Quench-6

Description

Validation analyses were performed within the scope of the validation matrix defined previously (see Report UJV--11658-T). This comprised the following steps: (i) Setting up a set of quantitative parameters to evaluate the codes; (ii) performing the validation analyses and their evaluation; (iii) assessment of severity of the differences identified and identification of the probable causes of the discrepancies; (iv) identification of realistic approaches to quality improvement of analyses as made possible by the existing code versions; and (v) proposal and initiation of activities aimed at additional improvement of the codes within the CSARP programme. The report deals with the validation problem Quench-6, whose aim it was to recalculate the problem defined for ISP-45 with the code distributed within the CSARP programme, i.e. SCDAP/RELAP5 Mod. 3.3. (P.A.)

Availability note (English)

Available from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.cz
Part of:
Setting up the validation analysis matrix and preparation of models

Additional details

Additional titles

Original title (Czech)
Validace kodu MELCOR 1.8.5 a SCDAP/RELAP5 a revize modelu MAAP. Validacni uloha Quench-6

Publishing Information

Imprint Pagination
53 p.
Report number
UJV--11780-T

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
37048304
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; M CODES; MATHEMATICAL MODELS; MATRICES; R CODES; REACTOR SAFETY; S CODES; SAFETY ANALYSIS; THERMAL HYDRAULICS; VALIDATION
Descriptors DEC
COMPUTER CODES; FLUID MECHANICS; HYDRAULICS; MECHANICS; SAFETY; SIMULATION; TESTING

Optional Information

Notes
Developed within the State Office for Nuclear Safety project 'Development of methods and tools for the analysis of safety-related processes occurring during severe accidents'. 1 tab., 73 figs., 5 refs.