Irradiation Embrittlement of lower copper reactor pressure vessel steels

SUZUKI Masahide; NISHIYAMA Yutaka

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Irradiation Embrittlement of lower copper reactor pressure vessel steels

机译：低铜反应堆压力容器钢的辐照脆化

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来源
《金属》 |2001年第8期|共4页
作者
SUZUKI Masahide; NISHIYAMA Yutaka;
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原文格式 PDF
正文语种 jpn
中图分类金属材料;冶金工业;
关键词
copper; pressure vessel steel; irradiation embrittlement;

机译：铜;压力容器钢;辐照脆化;
入库时间 2022-08-19 08:10:26

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专利

1. Irradiation Embrittlement of lower copper reactor pressure vessel steels [J] . SUZUKI Masahide, NISHIYAMA Yutaka 金属 . 2001,第8期

机译：低铜反应堆压力容器钢的辐照脆化
2. Conservative estimations of irradiation embrittlement of reactor pressure vessel steels for WWER-1000 lifetime prediction [J] . Nikolai Petrovich Anosov, Vladimir Nikolaevich Skorobogatykh, Lyubov Yuryevna Gordyuk, Multidiscipline modeling in materials and structures . 2019,第1期

机译：WWER-1000寿命预测的反应堆压力容器钢辐射脆化的保守估计
3. Effect of the bainitic and martensitic microstructures on the hardening and embrittlement under neutron irradiation of a reactor pressure vessel steel [J] . Marini B., Averty X., Wident P., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2015,第Null期

机译：贝氏体和马氏体组织对反应堆压力容器钢中子辐照下硬化和脆化的影响
4. Effects of Neutron Dose, Dose Rate, and Irradiation Temperature on the Irradiation Embrittlement of a Low-Copper Reactor Pressure Vessel Steel [C] . Ryuta Kasada, Takeshi Kudo, Akihiko Kimura, International symposium on effects of radiation on materials . 2006

机译：中子剂量，剂量率和辐照温度对低铜反应堆压力容器钢辐照脆化的影响
5. Kinetics of irradiation embrittlement and the post-irradiation annealing of nuclear reactor pressure vessel steels [D] . Mader, Erik Vance 1995

机译：核反应堆压力容器钢的辐照脆化动力学和辐照后退火
6. On the Elevated Temperature Thermal Stability of Nanoscale Mn-Ni-Si Precipitates Formed at Lower Temperature in Highly Irradiated Reactor Pressure Vessel Steels [O] . N. Almirall, P. B. Wells, H. Ke, -1

机译：高辐照反应堆压力容器钢中较低温度下形成的纳米Mn-Ni-Si沉淀物的高温热稳定性研究
7. IRRADIATION INDUCED-HARDENING AND EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEELS AS REVEALED BY ATOMIC LEVEL SIMULATIONS [O] . A. AlAsqalani 2018

机译：原子水平模拟所揭示的辐照诱导 - 反应器压力容器钢的脆化和脆化
8. Irradiation Embrittlement of Reactor Pressure Vessel Steels (Report on Analysis of the Behaviour of Advanced Reactor Pressure Vessel Steel under Neutron Irradiation) [R] . Sivaramakrishnan, K. S., Chatterjee, S., Anantharaman, S., 1984

机译：反应堆压力容器钢的辐照脆化（中子辐照下先进反应堆压力容器钢性能分析报告）

Irradiation Embrittlement of lower copper reactor pressure vessel steels

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