Published October 2018 | Version v1
Journal article Metadata-only

Analysis and evaluation for ATWS event by RELAP5-3D

Creators

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

Description

In this study, the RELAP5-3D code with well-maintained plant information was used to analyze the ATWS (anticipated transient without scram) incident for several combinations of reactor core conditions and transient analysis conditions. The condition influences on the predicted plant behavior were examined. The ATWS incidents analyzed occurred during a loss of main feed water accident and a loss of load. These analyses showed that these incidents progress towards convergence without any degradation of the reactor coolant pressure boundary under the conservative reactor core conditions and conservative transient analysis conditions. (author)

Abstract (Japanese)

この研究では,原子力安全システム研究所で既にプラント情報がほぼ整備されているRELAP5-3Dコードを用い,原子炉停止機能喪失(ATWS, Anticipated Transient Without Scram)時の,炉心条件および解析条件の違いによるATWS緩和措置の有効性評価について検討した.起因事象は,主給水流量喪失事象および負荷喪失事象である.解析結果から,保守的な炉心条件に保守的な解析条件を設定した場合でも,原子炉冷却材圧力バウンダリの健全性が損なわれること無く,事象は収束に向うことが分かった.(著者)

Additional details

Additional titles

Original title (Japanese)
ATWS事象のRELAP5-3Dによる解析

Publishing Information

Journal Title
INSS Journal
Journal Volume
25
Journal Page Range
p. 143-148
ISSN
1340-4482

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
50005918
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ATWS; COMPUTER CODES; PRESSURIZERS; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR OPERATION; REACTOR SAFETY; REACTOR SHUTDOWN; REGULATORY GUIDES; RELIEF VALVES; SEVERE ACCIDENTS; STEAM GENERATORS; THERMAL HYDRAULICS; TOTAL LOSS OF FEEDWATER; TRANSIENTS
Descriptors DEC
ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BOILERS; CONTROL EQUIPMENT; CONTROL SYSTEMS; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; OPERATION; POWER REACTORS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; VALVES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs., 9 figs., 7 tabs.