CANDU堆

作品数:62被引量:58H指数:4
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相关领域:核科学技术电气工程更多>>
相关作者:谢仲生霍小东樊申申森刘志宾更多>>
相关机构:西安交通大学秦山第三核电有限公司上海交通大学上海核工程研究设计院更多>>
相关期刊:《核科学与工程》《核安全》《核技术》《核标准计量与质量》更多>>
相关基金:国家教育部博士点基金国际原子能机构基金更多>>
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Computational analysis of neutronic effects of ThO_2 rods loaded in CANDU 6 fuel assemblies被引量:1
《Nuclear Science and Techniques》2016年第4期14-20,共7页Seyed Mohammad Mirvakili Zohreh Gholamzadeh Seyed Amir Hossein Feghhi 
Thorium as a suitable fertile with higher natural resources in comparison with uranium resources has been remarkably considered by different nuclear energy user countries in the last decades. Its prominent features su...
关键词:CANDU堆 中子泄漏 燃料组件 稳定杆 计算 核反应堆 燃烧时间 自然资源 
Simulation of quenching in horizontal geometry channel被引量:3
《Nuclear Science and Techniques》2010年第6期370-374,共5页Yuan Jingtian Tong Lili Cao Xuewu 
Supported by grant of Doctoral Fund of Ministry of Education of China(20090073110034)
Two tests of refilling and reflooding in the horizontal geometry channel under different pressure conditions,respectively,are conducted to understand the thermal hydraulics behavior during a LOCA in the CANDU reactor....
关键词:水平测试 通道测试 模型模拟 几何 淬火 CANDU堆 压力条件 热工水力 
Analysis of severe core damage accident progression for the heavy water reactor
《Nuclear Science and Techniques》2010年第4期251-256,共6页TONG Lili YUAN Kai YUAN Jingtian CAO Xuewu 
In this study,the severe accident progression analysis of generic Canadian deuterium uranium reactor 6 was preliminarily provided using an integrated severe accident analysis code.The selected accident sequences were ...
关键词:重水反应堆 损坏事故 蒸汽发生器 堆芯 CANDU堆 严重事故 热传输系统 事故分析 
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