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国产 A508-3钢辐照性能

林赟 宁广胜 张长义 佟振峰 杨文

原子能科学技术2016,Vol.50Issue(2):204-207,4.
原子能科学技术2016,Vol.50Issue(2):204-207,4.DOI:10.7538/yzk.2016.50.02.0204

国产 A508-3钢辐照性能

Mechanical Property of China A508-3 Steel after Neutron Irradiation

林赟 1宁广胜 1张长义 1佟振峰 1杨文1

作者信息

  • 1. 中国原子能科学研究院反应堆工程研究设计所,北京 102413
  • 折叠

摘要

Abstract

Reactor pressure vessel (RPV ) is the critical un‐changeable component of the reactor during its service lifetime , w hich prevents the radioactive leak of the nuclear power plant core .The irradiation test (about 10 × 1019 cm -2 ,E≥1 MeV) of the pres‐sure vessel material of China A508‐3 steel in research reactor was carried out ,and the mechanics performance tests were carried out after the neutron irradiation ,including tensile property and impact property .The results show that the yield strength increases by 83 ,108 and 52 MPa ,and the tensile strength increases by 58 ,61 and 49 MPa at-100 ,20 and 288 ℃ , respectively . The ductile‐brittle transition temperature T41J increases by 68 ℃ ,and the upper shelf energy decreases by 61 J .Meanwhile ,by compa‐ring the property of un‐irradiated and irradiated material ,after irradiated to the level of 60 a service life ,A508‐3 steel still meets the reactor operation requirement .

关键词

A508-3钢/中子辐照/辐照脆化

Key words

A508-3 steel/neutron irradiation/irradiation embrittlement

分类

能源科技

引用本文复制引用

林赟,宁广胜,张长义,佟振峰,杨文..国产 A508-3钢辐照性能[J].原子能科学技术,2016,50(2):204-207,4.

基金项目

国家科技重大专项资助项目(2011ZX06004-002);国家重点基础研究发展计划资助项目 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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