Published September 1986 | Version v1
Journal article Metadata-only

Thermal-hydraulic transient characteristics of ship-propulsion reactor investigated through safety analysis

Creators

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

Description

Thermal-hydraulic behaviors in the reactor of Nuclear Ship "Mutsu" were investigated through safety evaluation of operational transients by using RETRAN and COBRA-IV codes. The results were compared to the transient behaviors of typical commercial PWR and the characteristics of transient thermal-hydraulic behaviors in ship-loaded reactor were figured out. "Mutsu" reactor has larger thermal margin than commercial PWR because it is designed to be used as ship-propulsion power source in the load-following operation mode. This margin makes transient behavior in general milder than in commercial PWR but high opening pressure set point of main-steam safety valves leads poor heat-sink condition after reactor trip. The effects of other small-sized components are also investigated. The findings in the paper will be helpful in the design of future advanced reactor for nuclear ship. (author)

Availability note (English)

Available from DOI: https://doi.org/10.3327/jaesj.28.838

Abstract (Japanese)

原子力船「むつ」原子炉について日本原子力研究所が実施した安全評価解析の中、運転時異常過渡における原子炉熱水力挙動に関する解析結果を陸上発電用PWRの場合と対比して特徴を指摘した。「むつ」原子炉は負荷追従運転を前提としているため大きな熱的余裕を持つ一方、無用の弁開閉を避けるため逃し弁、安全弁設定圧が高い。解析結果は、これらの特徴を反映して、温度、圧力の変化率DNBRの面では発電用PWRよりも穏やかであるが、原子炉停止後の2次系ヒートシンク効果が弱く、1次系温度、圧力の長期的上昇を伴うことを示している。また、舶用炉に必然的な小型化による過渡変化への影響を考案した。これらの特徴は舶用炉独特のものであり、本報による過渡熱水力挙動の知見は、将来の改良用炉設計にも役立つものである。(著者)

Additional details

Additional titles

Original title (Japanese)
舶用炉過渡熱水力事象の安全評価解析

Identifiers

DOI
10.3327/jaesj.28.838;

Publishing Information

Journal Title
Nippon Genshiryoku Gakkai-Shi
Journal Volume
28
Journal Issue
9
Journal Page Range
p. 838-849
ISSN
0004-7120
CODEN
NGEGAL

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
54003907
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
C CODES; HYDRAULICS; LOSS OF COOLANT; LOSS OF FLOW; MUTSU REACTOR; R CODES; REACTOR SAFETY; THERMODYNAMIC PROPERTIES; TRANSIENT OVERPOWER ACCIDENTS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; MECHANICS; PHYSICAL PROPERTIES; POWER REACTORS; PROPULSION REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SHIP PROPULSION REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
This record replaces 18061944