Validation of the reactor dynamics code TRAB

Hanna Räty, Riitta Kyrki-Rajamäki, Rajamäki Markku

Research output: Book/ReportReportProfessional

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 utilised also in analyses of e.g. the heating reactor SECURE and the RBMK-type reactor (Chernobyl). This report summarises 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 RBMK 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. TRAB has been extensively used for analyses of the TVO ABB Atom type BWR reactors and within SMATRA for PWR analyses of the Loviisa VVER-440 reactors and VVER-91 type reactors. TRAB is also used outside VTT both for BWR analyses and, within SMATRA, for PWR analyses by the Finnish Centre for Radiation and Nuclear Safety (STUK) and the Imatran Voima Oy (IVO) power company.
Original languageEnglish
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Number of pages31
ISBN (Print)951-38-3976-1
Publication statusPublished - 1991
MoE publication typeD4 Published development or research report or study

Publication series

NameTutkimuksia, Ydinvoimatekniikan laboratorio
PublisherValtion teknillinen tutkimuskeskus
No.729
ISSN (Print)0358-5077

Fingerprint

Transient analysis
Boiling water reactors
Nuclear power plants
Accidents
Radiation
Heating
Atoms
Networks (circuits)

Keywords

  • validation
  • one-dimensional reactor dynamics
  • space-time kinetics
  • reactor safety analysis
  • reactor accidents
  • thermohydraulics
  • TRAB

Cite this

Räty, H., Kyrki-Rajamäki, R., & Markku, R. (1991). Validation of the reactor dynamics code TRAB. Espoo: VTT Technical Research Centre of Finland. Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports, No. 729
Räty, Hanna ; Kyrki-Rajamäki, Riitta ; Markku, Rajamäki. / Validation of the reactor dynamics code TRAB. Espoo : VTT Technical Research Centre of Finland, 1991. 31 p. (Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports; No. 729).
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Räty, H, Kyrki-Rajamäki, R & Markku, R 1991, Validation of the reactor dynamics code TRAB. Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports, no. 729, VTT Technical Research Centre of Finland, Espoo.

Validation of the reactor dynamics code TRAB. / Räty, Hanna; Kyrki-Rajamäki, Riitta; Markku, Rajamäki.

Espoo : VTT Technical Research Centre of Finland, 1991. 31 p. (Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports; No. 729).

Research output: Book/ReportReportProfessional

TY - BOOK

T1 - Validation of the reactor dynamics code TRAB

AU - Räty, Hanna

AU - Kyrki-Rajamäki, Riitta

AU - Markku, Rajamäki

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N2 - 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 utilised also in analyses of e.g. the heating reactor SECURE and the RBMK-type reactor (Chernobyl). This report summarises 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 RBMK 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. TRAB has been extensively used for analyses of the TVO ABB Atom type BWR reactors and within SMATRA for PWR analyses of the Loviisa VVER-440 reactors and VVER-91 type reactors. TRAB is also used outside VTT both for BWR analyses and, within SMATRA, for PWR analyses by the Finnish Centre for Radiation and Nuclear Safety (STUK) and the Imatran Voima Oy (IVO) power company.

AB - 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 utilised also in analyses of e.g. the heating reactor SECURE and the RBMK-type reactor (Chernobyl). This report summarises 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 RBMK 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. TRAB has been extensively used for analyses of the TVO ABB Atom type BWR reactors and within SMATRA for PWR analyses of the Loviisa VVER-440 reactors and VVER-91 type reactors. TRAB is also used outside VTT both for BWR analyses and, within SMATRA, for PWR analyses by the Finnish Centre for Radiation and Nuclear Safety (STUK) and the Imatran Voima Oy (IVO) power company.

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KW - one-dimensional reactor dynamics

KW - space-time kinetics

KW - reactor safety analysis

KW - reactor accidents

KW - thermohydraulics

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M3 - Report

SN - 951-38-3976-1

T3 - Tutkimuksia, Ydinvoimatekniikan laboratorio

BT - Validation of the reactor dynamics code TRAB

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Räty H, Kyrki-Rajamäki R, Markku R. Validation of the reactor dynamics code TRAB. Espoo: VTT Technical Research Centre of Finland, 1991. 31 p. (Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports; No. 729).