Published October 2022 | Version v1
Journal article Metadata-only

The development status of RELAP

Creators

  • 1. Institute of Nuclear Safety System, Inc., Institute of Nuclear Technology, Mihama, Fukui (Japan)
  • 2. CSA of Japan Co., Ltd., Tokyo (Japan)

Description

This research was started with the aim of understanding the effects of the version upgrade of the accident analysis code RELAP5-3D on the analysis results obtained. In this report, we summarize our investigation of the contents of the version upgrade and our understanding of the effects on the analysis results while utilizing past analysis experiences of the main steam line break (MSLB) event and the anticipated transient without scram (ATWS) event. Using this information, we prepare the analysis platform of RELAP5-3D. (author)

Availability note (English)

Available from http://www.inss.co.jp/research/inss/journal29/

Abstract (Japanese)

許認可解析にも用いられている事故解析コード RELAP5-3D のバージョンアップ内容が解析に与える影響を把握することを目的とし、本研究は開始された.本研究では、RELAP5-3D のバージョンアップに伴う改良点の内容の精査検討を行い、主蒸気管破断(MSLB)事象やスクラム失敗事象(ATWS)事象といった過去の解析経験を活用しながら、解析結果への影響を把握するとともに、当社の RELAP5-3D 解析基盤を整備した.本稿は、これまで実施してきた研究成果についてまとめたものである.(著者)

Additional details

Additional titles

Original title (Japanese)
RELAP の開発状況

Identifiers

URL
http://www.inss.co.jp/research/inss/journal29/;

Publishing Information

Journal Title
INSS Journal
Journal Volume
29
Journal Page Range
p. 276-286
ISSN
1340-4482

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
54069078
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
AFTER-HEAT; ATWS; CRITICAL CURRENT; HEAT TRANSFER; LOSS OF COOLANT; PRESSURE DROP; R CODES; REACTOR ACCIDENT SIMULATION; REACTOR KINETICS; STEAM GENERATORS; STEAM LINE BREAK ACCIDENTS; VOID FRACTION
Descriptors DEC
ACCIDENTS; BOILERS; COMPUTER CODES; CURRENTS; ELECTRIC CURRENTS; ENERGY TRANSFER; KINETICS; REACTOR ACCIDENTS; SIMULATION; VAPOR GENERATORS

Optional Information

Notes
7 refs., 23 figs., 3 tabs.