An embrittlement rate effect deduced from HFIR that may impact LWR vessel support life expectancy-Reference-Cited by-同舟云学术

An embrittlement rate effect deduced from HFIR that may impact LWR vessel support life expectancy

Published:1989-12 Issue:3 Volume:117 Page:349-355
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Cheverton R.D.,Kam F.B.,Nanstad R.K.,Robinson G.C.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference11 articles.

1. R.D. Cheverton, T.M. Sims HFIR core nuclear design ORNL-4621, ORNL-4621.

2. HFIR pressure cessel and structural components material surveillance program;McWherter;ORNL/TM1372,1966

3. Evaluation of HFIR pressure-vessel integrity considering radiation embrittlement,1988

4. Studies of radiation effects and recovery of notch ductility of pressure vessel steels;Hawthorne,1960

5. Irradiated materials evaluation and reactor pressure vessel surveillance for the Army nuclear power program;Steele;NRL Memorandum Report 1644,1965

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Effects of gamma-induced displacements on HFIR pressure vessel materials;Journal of Nuclear Materials;1994-12

2. Low temperature embrittlement of LWR RPV support structures;International Journal of Pressure Vessels and Piping;1993-01

3. Correlation of mechanical property changes in neutron-irradiated pressure vessel steels on the basis of spectral effects;Journal of Nuclear Materials;1991-01