版权说明 操作指南
首页 > 成果 > 详情

Preliminary study on physical characteristics of single-pass super-critical water-cooled reactor core

认领
导出
下载 Link by DOI
反馈
分享
QQ微信 微博
成果类型:
期刊论文
作者:
Wang, Mingyue;Huang, Liping;Zhang, Qian;Seidl, Marcus;Liu, Zijing;...
通讯作者:
Wang, Xiang
作者机构:
[Huang, Liping; Wang, Mingyue; Wang, Xiang; Zhang, Qian] Harbin Engn Univ, Coll Nucl Sci & Technol, Harbin 150001, Heilongjiang, Peoples R China.
[Seidl, Marcus] Tech Univ Munich, Dept Nucl Engn, Garching, Germany.
[Liu, Zijing] Univ South China, Dept Nucl Sci & Technol, Hengyang, Peoples R China.
通讯机构:
[Wang, Xiang] H
Harbin Engn Univ, Coll Nucl Sci & Technol, Harbin 150001, Heilongjiang, Peoples R China.
语种:
英文
关键词:
Assembly;Cladding (coating);Coolants;Cooling water;Neutron spectrometers;Nuclear fuels;Oxide minerals;Reactor cores;Sensitivity analysis;Thoria;Uranium dioxide;Water cooling systems;Cladding material;Fast neutron spectrums;Fuel compositions;Fundamental research;Physical characteristics;Power distributions;Pressurized water;System characteristics;Pressurized water reactors
期刊:
International Journal of Energy Research
ISSN:
0363-907X
年:
2021
卷:
45
期:
8
页码:
11807-11821
基金类别:
Natural Science Foundation of Heilongjiang Province, Grant/Award Number: YQ2019A001; Postdoctoral Funding of Heilongjiang Province, Grant/Award Number: 02150830601; Scientific Research Foundation for Selected Returned Overseas Chinese Scholars of Heilongjiang Province, Grant/Award Number: 159150130003 Funding information This work was supported by the Natural Science Foundation of Heilongjiang Province, China (Grant No. YQ2019A001), the Postdoctoral Funding of Heilongjiang Province (Grant No. 02150830601), and the Scientific Research Foundation for Selected Returned Overseas Chinese Scholars of Heilongjiang Province (Grant No. 159150130003). We thank LetPub for its linguistic assistance during the preparation of this manuscript.
机构署名:
本校为其他机构
院系归属:
核科学技术学院
摘要:
The super-critical water-cooled reactor (SCWR) is one of six types of Gen-IV reactors. Based on the current mature pressurized water reactor technology, it has several advantages, including high conversion ratio, high breeding of nuclear fuel, high thermal efficiency, and a simplified system. However, due to the combination of water coolant and fast neutron spectrum, there is a need to address safety problems caused by the positive void coefficient. The purpose of this paper is to give a study on physical characteristics for the reactor core. H...

反馈

验证码:
看不清楚,换一个
确定
取消

成果认领

标题:
用户 作者 通讯作者
请选择
请选择
确定
取消

提示

该栏目需要登录且有访问权限才可以访问

如果您有访问权限,请直接 登录访问

如果您没有访问权限,请联系管理员申请开通

管理员联系邮箱:yun@hnwdkj.com