A Method to Evaluate the Maximum Allowable Temperature of Spent Fuel in Dry Storage During a Postulated Accident
Author:
Affiliation:
1. Central Research Institute of Electric Power Industry 2-11-1 Iwato-kita, Komae-shi, Tokyo 210, Japan
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT91-A34532
Reference10 articles.
1. L. D. BLACKBURN, D. G. FARWICK, S. R. FIELD, L. A. JAMES, and R. A. MOEN, “Maximum Allowable Temperature for Storage of Spent Nuclear Reactor Fuel,” HEDL-TME 78-37, Hanford Engineering Development Laboratory (1978).
2. Prediction of Maximum Allowable Temperatures for Dry Storage of Zircaloy-Clad Spent Fuel in Inert Atmosphere
3. M. MAYUZUMI, “A Method for Evaluating the Max-imum Allowable Temperature of PWR Fuel Under Dry Storage Condition,” CRIEPI Report No. T88034, Central Research Institute of Electric Power Industry (1989) (in Japanese).
4. Accelerated High-Temperature Tests with Spent PWR and BWR Fuel Rods Under Dry Storage Conditions
5. LWR Spent Fuel Storage Behaviour
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. Short-term rupture studies of Zircaloy-4 and Nb-modified Zircaloy-4 tubing using closed-end internal pressurization;Nuclear Engineering and Design;2004-03
2. The internal pressurization creep of Zr alloys for spent-fuel dry storage feasibility;JOM;2000-09
3. Creep studies for zircaloy life prediction in water reactors;JOM;1999-10
1.学者识别学者识别
2.学术分析学术分析
3.人才评估人才评估
"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370
www.globalauthorid.com
TOP
Copyright © 2019-2024 北京同舟云网络信息技术有限公司 京公网安备11010802033243号 京ICP备18003416号-3