Fuel performance evaluation of two high burnup PWR core designs during normal operation, control rod withdrawal, and control rod ejection scenarios

Author:

Lindsay Isabelle O.ORCID,Fox MasonORCID,Sweet Ryan T.ORCID,Capps Nathan,Brown Nicholas R.ORCID

Funder

U.S. Department of Energy

Office of Nuclear Energy

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

Reference42 articles.

1. Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation;Barani;J. Nucl. Mater.,2020

2. Bibilashvili, Yu K, AV Kuleshov, OV Milovanov, EN Mikheev, VV Novikov, SG Popov, VN Proselkov, YUV PIMENOV, and YUG GODIN. 2004. 'Investigation of thermal-physical and mechanical properties of uranium-gadolinium oxide fuel', Advanced fuel pellet materials and designs for water cooled reactors, Proceedings: 85.

3. Brassfield, H C, J F White, L Sjodahl, and J T Bittel. 1968. “Recommended property and reaction kinetics data for use in evaluating a light-water-cooled reactor loss-of-coolant incident involving zircaloy-4- OR 304-SS-CLAD UO{sub 2}.” In, Medium: ED; Size: Pages: 89. United States.

4. Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON;Bratton;Nucl. Technol.,2017

5. The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors;Brown;Ann. Nucl. Energy,2017

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

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