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Validation of the reactor dynamics code TRAB

Technical Report:

Abstract

The one-dimensional reactor dynamics code TRAB (Transient Analysis code for BWRs) developed at VTT was originally designed for BWR analyses, but it can in its present version be used for various modelling purposes. The core model of TRAB can be used separately for LWR calculations. For PWR modelling the core model of TRAB has been coupled to circuit model SMABRE to form the SMATRA code. The versatile modelling capabilities of TRAB have been utilized also in analyses of e.g. the heating reactor SECURE and the RBMK-type reactor (Chernobyl). The report summarizes the extensive validation of TRAB. TRAB has been validated with benchmark problems, comparative calculations against independent analyses, analyses of start-up experiments of nuclear power plants and real plant transients. Comparative RBMES type reactor calculations have been made against Soviet simulations and the initial power excursion of the Chernobyl reactor accident has also been calculated with TRAB.
Publication Date:
May 01, 1991
Product Type:
Technical Report
Report Number:
VTT-TUTK-729
Reference Number:
SCA: 210100; 990200; PA: AIX-23:008706; SN: 92000619706
Resource Relation:
Other Information: PBD: May 1991
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; BWR TYPE REACTORS; COMPUTERIZED SIMULATION; LWGR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR KINETICS; REACTOR SAFETY; T CODES; TRANSIENTS; VERIFICATION; 210100; 990200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED; MATHEMATICS AND COMPUTERS
OSTI ID:
10104122
Research Organizations:
Valtion Teknillinen Tutkimuskeskus, Espoo (Finland)
Country of Origin:
Finland
Language:
English
Other Identifying Numbers:
Other: ON: DE92612891; ISBN 951-38-3976-1; TRN: FI9100117008706
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
FIN
Size:
32 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Raety, H, Kyrki-Rajamaeki, R, and Rajamaeki, M. Validation of the reactor dynamics code TRAB. Finland: N. p., 1991. Web.
Raety, H, Kyrki-Rajamaeki, R, & Rajamaeki, M. Validation of the reactor dynamics code TRAB. Finland.
Raety, H, Kyrki-Rajamaeki, R, and Rajamaeki, M. 1991. "Validation of the reactor dynamics code TRAB." Finland.
@misc{etde_10104122,
title = {Validation of the reactor dynamics code TRAB}
author = {Raety, H, Kyrki-Rajamaeki, R, and Rajamaeki, M}
abstractNote = {The one-dimensional reactor dynamics code TRAB (Transient Analysis code for BWRs) developed at VTT was originally designed for BWR analyses, but it can in its present version be used for various modelling purposes. The core model of TRAB can be used separately for LWR calculations. For PWR modelling the core model of TRAB has been coupled to circuit model SMABRE to form the SMATRA code. The versatile modelling capabilities of TRAB have been utilized also in analyses of e.g. the heating reactor SECURE and the RBMK-type reactor (Chernobyl). The report summarizes the extensive validation of TRAB. TRAB has been validated with benchmark problems, comparative calculations against independent analyses, analyses of start-up experiments of nuclear power plants and real plant transients. Comparative RBMES type reactor calculations have been made against Soviet simulations and the initial power excursion of the Chernobyl reactor accident has also been calculated with TRAB.}
place = {Finland}
year = {1991}
month = {May}
}