• 文献检索
  • 文档翻译
  • 深度研究
  • 学术资讯
  • Suppr Zotero 插件Zotero 插件
  • 邀请有礼
  • 套餐&价格
  • 历史记录
应用&插件
Suppr Zotero 插件Zotero 插件浏览器插件Mac 客户端Windows 客户端微信小程序
定价
高级版会员购买积分包购买API积分包
服务
文献检索文档翻译深度研究API 文档MCP 服务
关于我们
关于 Suppr公司介绍联系我们用户协议隐私条款
关注我们

Suppr 超能文献

核心技术专利:CN118964589B侵权必究
粤ICP备2023148730 号-1Suppr @ 2026

文献检索

告别复杂PubMed语法,用中文像聊天一样搜索,搜遍4000万医学文献。AI智能推荐,让科研检索更轻松。

立即免费搜索

文件翻译

保留排版,准确专业,支持PDF/Word/PPT等文件格式,支持 12+语言互译。

免费翻译文档

深度研究

AI帮你快速写综述,25分钟生成高质量综述,智能提取关键信息,辅助科研写作。

立即免费体验

Optimization design research for 89Sr production in China Experimental Fast Reactor.

作者信息

Hu Xiao, Chen Xiao-Liang

机构信息

China Institute of Atomic Energy (CIAE), Beijing Funhill, PR China.

China Institute of Atomic Energy (CIAE), Beijing Funhill, PR China.

出版信息

Appl Radiat Isot. 2018 Jul;137:167-171. doi: 10.1016/j.apradiso.2018.03.020. Epub 2018 Mar 28.

DOI:10.1016/j.apradiso.2018.03.020
PMID:29649686
Abstract

As the first sodium cooled fast reactor in China, China Experimental Fast Reactor (CEFR) has many characteristics, such as high power rating, high neutron flux and high neutron leakage as its hard spectrum. These leakage neutrons can be used to produce Sr by fast neutrons (n, p) reaction. By means of some special designs, including designing optimized target assembly, choosing reasonable irradiation location and appropriate irradiation cycle length, in order to improve specific activity of Sr. The MNCP code was used to the calculations coupled ORIGRN2 procedure. The higher activity of Sr can be obtained by these optimization designs, so it is feasible to produce Sr in the fuel region of CEFR.

摘要

相似文献

1
Optimization design research for 89Sr production in China Experimental Fast Reactor.
Appl Radiat Isot. 2018 Jul;137:167-171. doi: 10.1016/j.apradiso.2018.03.020. Epub 2018 Mar 28.
2
Hardening neutron spectrum for advanced actinide transmutation experiments in the ATR.用于先进锕系元素嬗变实验的ATR中的硬化中子能谱。
Radiat Prot Dosimetry. 2005;115(1-4):63-8. doi: 10.1093/rpd/nci167.
3
Feasibility Study to Byproduce Medical Radioisotopes in a Fusion Reactor.在聚变反应堆中生产医用放射性同位素的可行性研究。
Molecules. 2023 Feb 22;28(5):2040. doi: 10.3390/molecules28052040.
4
Study on a new design of Tehran Research Reactor for radionuclide production based on fast neutrons using MCNPX code.基于MCNPX代码对德黑兰研究堆进行快中子放射性核素生产的新设计研究。
Appl Radiat Isot. 2018 Feb;132:67-71. doi: 10.1016/j.apradiso.2017.11.006. Epub 2017 Nov 6.
5
A feasibility study of the Tehran research reactor as a neutron source for BNCT.德黑兰研究堆作为硼中子俘获疗法中子源的可行性研究。
Appl Radiat Isot. 2014 Aug;90:132-7. doi: 10.1016/j.apradiso.2014.03.028. Epub 2014 Apr 5.
6
Radionuclide production using a fast flux reactor.使用快中子通量反应堆生产放射性核素。
Appl Radiat Isot. 2000 Oct;53(4-5):825-7. doi: 10.1016/s0969-8043(00)00236-0.
7
The determination of reactor neutron spectrum-averaged cross-sections in miniature neutron source reactor facility.微型中子源反应堆设施中反应堆中子谱平均截面的测定
Appl Radiat Isot. 2008 Oct;66(10):1377-80. doi: 10.1016/j.apradiso.2008.04.001. Epub 2008 Apr 7.
8
Monte-Carlo calculations for the development of a BNCT neutron source at the Kyiv Research Reactor.用于在基辅研究堆开发硼中子俘获治疗(BNCT)中子源的蒙特卡罗计算。
Appl Radiat Isot. 2004 Nov;61(5):869-73. doi: 10.1016/j.apradiso.2004.05.045.
9
A reaction rate measurement experimental program of China experimental fast reactor.中国实验快堆反应速率测量实验方案
Appl Radiat Isot. 2022 Dec;190:110455. doi: 10.1016/j.apradiso.2022.110455. Epub 2022 Sep 19.
10
Development of a dual phantom technique for measuring the fast neutron component of dose in boron neutron capture therapy.用于测量硼中子俘获疗法中剂量的快中子成分的双体模技术的开发。
Med Phys. 2015 Nov;42(11):6651-7. doi: 10.1118/1.4934243.

引用本文的文献

1
Dissolution of mixed oxide(MOX) fuel in nitric acid:A review.混合氧化物(MOX)燃料在硝酸中的溶解:综述
Heliyon. 2024 Mar 9;10(6):e27502. doi: 10.1016/j.heliyon.2024.e27502. eCollection 2024 Mar 30.