Heat-up of a partially uncovered PWR fuel rod in the presence of cladding oxidation and steam dissociation-Reference-Cited by-同舟云学术

登录注册会员服务联系我们

Heat-up of a partially uncovered PWR fuel rod in the presence of cladding oxidation and steam dissociation

Published:1988-01 Issue:2 Volume:105 Page:231-242
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Viskanta R.,Mohanty A.K.

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

Reference14 articles.

1. Three Mile Island,1980

2. Heat transfer from a partially uncovered reactor core;Viskanta;Nucl. Engrg. Des.,1985

3. Effects of Zircaloy oxidation and steam dissociation on cooling of a PWR core under conditions simulating uncovered fuel rods;Viskanta,1986

4. A code for predicting the temperature and oxidation of undercooled cores;Abramson,1981

5. An assessment of existing data on zirconium oxidation under hypothetical accident conditions in light water reactors;Baker,1983

同舟云学术

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