A Core Design of Innovative Breeder BWR

Guo Rui, A. Yamaji, Yun Cai, Xin-sheng Peng
{"title":"A Core Design of Innovative Breeder BWR","authors":"Guo Rui, A. Yamaji, Yun Cai, Xin-sheng Peng","doi":"10.1115/ICONE26-82079","DOIUrl":null,"url":null,"abstract":"High breeding with light water cooling has been studied for decades, though is not easy to be achieved. The main obstacle is the moderating effect of light water, which softens the neutron spectrum. To harden the neutron spectrum and thereby to enhance the fuel utilization or even to achieve breeding with light water cooling, the tight-lattice assembly was proposed and applied to High Conversion LWRs. Nonetheless, none of them achieved high breeding. Until recently, the tightly packed fuel assembly (TPFA) is designed for the purpose of high breeding. The ratio of hydrogen atoms to heavy metal atoms (H/HM) in this assembly is significantly reduced to be less than 0.1. Super Fast Breeding Reactor (Super FBR) adopts TPFA and achieves breeding performance with compound system doubling time (CSDT) of 43 years. In this study, the breeder BWR core also applies TPFA and achieves CSDT of 50 years. BWR is one type of the most extensively built reactors in the world, with abundant operation experience and mature technologies. Breeder BWR is considered to be capable of being incorporated into the current BWR plants with a handful of modifications, thus obtaining optimal economy.","PeriodicalId":65607,"journal":{"name":"International Journal of Plant Engineering and Management","volume":"62 1 1","pages":""},"PeriodicalIF":0.0000,"publicationDate":"2018-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"International Journal of Plant Engineering and Management","FirstCategoryId":"1089","ListUrlMain":"https://doi.org/10.1115/ICONE26-82079","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

High breeding with light water cooling has been studied for decades, though is not easy to be achieved. The main obstacle is the moderating effect of light water, which softens the neutron spectrum. To harden the neutron spectrum and thereby to enhance the fuel utilization or even to achieve breeding with light water cooling, the tight-lattice assembly was proposed and applied to High Conversion LWRs. Nonetheless, none of them achieved high breeding. Until recently, the tightly packed fuel assembly (TPFA) is designed for the purpose of high breeding. The ratio of hydrogen atoms to heavy metal atoms (H/HM) in this assembly is significantly reduced to be less than 0.1. Super Fast Breeding Reactor (Super FBR) adopts TPFA and achieves breeding performance with compound system doubling time (CSDT) of 43 years. In this study, the breeder BWR core also applies TPFA and achieves CSDT of 50 years. BWR is one type of the most extensively built reactors in the world, with abundant operation experience and mature technologies. Breeder BWR is considered to be capable of being incorporated into the current BWR plants with a handful of modifications, thus obtaining optimal economy.
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
新型增殖器BWR的核心设计
高增殖与轻水冷却已经研究了几十年,虽然不容易实现。主要的障碍是轻水的缓和作用,它软化了中子谱。为了强化中子能谱,从而提高燃料利用率,甚至实现轻水冷却增殖,提出了密点阵组件,并将其应用于高转化率轻水堆。尽管如此,它们都没有达到高育种水平。直到最近,紧密包装燃料组件(TPFA)是为高育种目的而设计的。该组件中氢原子与重金属原子的比率(H/HM)显著降低至0.1以下。超级快堆(Super FBR)采用TPFA,实现了43年复合系统倍增时间(CSDT)的增殖性能。在本研究中,增殖堆堆芯也应用了TPFA,实现了50年的CSDT。沸水堆是世界上建造最广泛的反应堆之一,具有丰富的运行经验和成熟的技术。增殖型沸水堆被认为能够通过少量的改造并入现有的沸水堆装置,从而获得最佳的经济性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 去求助
来源期刊
自引率
0.00%
发文量
768
期刊最新文献
Preliminary LOCA Analysis of Heating-Reactor of Advanced Low-Pressurized and Passive Safety System (HAPPY) Estimation of Mitigation Effects of Sodium Nanofluid for SGTR Accidents in SFR Prediction and Sensibility Analysis for Nuclear Safety-Critical Software Reliability of DCS Numerical Study on the Two-Phase Flow for a Gas/Liquid Metal Magnetohydrodynamic Generator Simulated Training Instrument of Nuclear Radiation Reconnaissance Based on an Improved Ellipse Numerical Model
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1