基本信息
邹春燕  女  硕导  中国科学院上海应用物理研究所
电子邮件: zouchunyan@sinap.ac.cn
通信地址: 上海市嘉定区嘉罗公路2019号
邮政编码:

招生信息

   
招生专业
082701-核能科学与工程
招生方向
核燃料循环分析
反应堆物理设计与分析

教育背景

2017-09--2020-06   中国科学院上海应用物理研究所   工学博士
2009-09--2012-06   兰州大学核科学与技术学院   理学硕士
2005-09--2009-06   兰州大学核科学与技术学院   理学学士

工作经历

   
工作简历
2020-01~2021-06,中国科学院上海应用物理研究所, 副研究员
2015-01~2019-12,中国科学院上海应用物理研究所, 助理研究员
2012-06~2014-12,中国科学院上海应用物理研究所, 实习研究员

专利与奖励

   
专利成果
( 1 ) 一种液态熔盐堆生产Mo-99的方法以及系统, 发明专利, 2021, 第 3 作者, 专利号: CN112863725A

( 2 ) 一种液态熔盐堆生产高活度比Sr-89和Sr-90的方法以及系统, 发明专利, 2021, 第 3 作者, 专利号: CN112863726A

( 3 ) 液态熔盐堆超铀燃料运行固有安全性的改善方法, 发明专利, 2020, 第 1 作者, 专利号: CN111627570A

( 4 ) 超铀燃料及其制备方法和嬗变方法, 发明专利, 2020, 第 1 作者, 专利号: CN111627569A

( 5 ) 一种熔盐堆生产U-233的方法, 专利授权, 2020, 第 1 作者, 专利号: CN108389638B

( 6 ) 液态熔盐堆嬗变超铀元素的方法, 发明专利, 2019, 第 1 作者, 专利号: CN110444311A

( 7 ) 一种熔盐堆堆芯, 专利授权, 2019, 第 7 作者, 专利号: CN108389632B

( 8 ) 一种熔盐堆上腔室, 专利授权, 2019, 第 4 作者, 专利号: CN108206065B

( 9 ) 重水慢化熔盐堆堆芯及重水慢化熔盐堆系统, 发明专利, 2018, 第 4 作者, 专利号: CN108511088A

( 10 ) 一种熔盐堆钍燃料循环利用方法, 发明专利, 2018, 第 3 作者, 专利号: CN108389634A

出版信息

   
发表论文
(1) Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium, ANNALS OF NUCLEAR ENERGY, 2022, 第 3 作者
(2) 新型重水慢化熔盐堆堆芯优化设计, Core design optimization for a novel heavy water moderated molten salt reactor, 核技术, 2021, 第 3 作者
(3) Parametric study on minor actinides transmutation in a graphite-moderated thorium-based molten salt reactors, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 1 作者
(4) Nuclear non-proliferation review and improving proliferation resistance assessment in the future, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 4 作者
(5) Ameliorating the positive temperature feedback coefficient for an MSR fueled with transuranic elements, ANNALS OF NUCLEAR ENERGY, 2021, 第 1 作者
(6) Analyses of production capacity of Sr-89 and Sr-90 in the 2 MW molten salt reactor, APPLIED RADIATION AND ISOTOPES, 2021, 第 4 作者
(7) Neutronic effect of graphite dimensional change in a small modular molten salt reactor, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 4 作者
(8) 钍基气冷快堆中^233U与^239Pu的增殖性能研究, Analysis of breeding performance for thorium-based gas-cooled fast reactor started by ^233U and ^239Pu, 核技术, 2020, 第 2 作者
(9) Transmutation of 129I in a single-fluid double-zone thorium molten salt reactor, Transmutation of 129I in a single-fluid double-zone thorium molten salt reactor, 核技术:英文版, 2020, 第 4 作者
(10) 利用超铀核素启动的小型模块化钍基熔盐堆中子学性能研究, Neutronic performances of small modular thorium-based molten salt reactor starting with TRUs, 核技术, 2020, 第 1 作者
(11) Transmutation of I-129 in a single-fluid double-zone thorium molten salt reactor, NUCLEAR SCIENCE AND TECHNIQUES, 2020, 通讯作者
(12) 利用超铀元素(TRU)启动的熔盐热堆钍铀循环过渡 及嬗变性能研究, Study on thorium fuel cycle transition and transmutation in a thermal Molten Salt Reactor started with TRU, 2020, 第 1 作者
(13) 基于灵敏度对比分析SCALE 6.1自带库与CENDL-TMSR-V1数据库, Comparison between SCALE 6.1 Built-in Library and CENDL-TMSR-V1 Library with Sensitivity Analysis, 原子能科学技术, 2020, 第 3 作者
(14) Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode, ANNALS OF NUCLEAR ENERGY, 2020, 第 1 作者
(15) Sustainable supply of 99Mo source in a 2MW molten salt reactor using low-enriched uranium, Applied Radiation and Isotopes, 2020, 第 2 作者
(16) Influence of 7Li enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra, Progress in Nuclear Energy, 2020, 第 5 作者
(17) Supply of I-131 in a 2MW molten salt reactor with different production methods, APPLIED RADIATION AND ISOTOPES, 2020, 第 4 作者
(18) Sustainable supply of Mo-99 source in a 2 MW molten salt reactor using low-enriched uranium, APPLIED RADIATION AND ISOTOPES, 2020, 第 2 作者
(19) Radiotoxicity of minor actinides in thermal, epithermal and fast TMSRs with very high burnup, ANNALS OF NUCLEAR ENERGY, 2020, 通讯作者
(20) Influence of Li-7 enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra, PROGRESS IN NUCLEAR ENERGY, 2020, 通讯作者
(21) Low enriched uranium and thorium fuel utilization under once-through and offline reprocessing scenarios in small modular molten salt reactor, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2019, 第 5 作者
(22) FLi/FLiBe盐中^7Li富集度对熔盐快堆钍铀转换性能的影响研究, Influence of ^7Li enrichment in FLi/FLiBe on Th-U conversion performance for molten salt fast reactor, 核技术, 2019, 第 4 作者
(23) A novel concept for a molten salt reactor moderated by heavy water, ANNALS OF NUCLEAR ENERGY, 2019, 第 6 作者
(24) Thorium utilization in a small modular molten salt reactor with progressive fuel cycle modes, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2019, 第 3 作者
(25) Transition to thorium fuel cycle for TMSR, NUCLEAR ENGINEERING AND DESIGN, 2018, 
(26) Th-U breeding performance in a Channel-type molten salt Fast reactor with different starting fuels, ANNALS OF NUCLEAR ENERGY, 2018, 第 3 作者
(27) Sm-149 evolution behavior in a small modular molten salt reactor, ANNALS OF NUCLEAR ENERGY, 2018, 第 4 作者
(28) 基于SCALE的熔盐堆添料与后处理系统分析程序开发及验证, Development and Verification of Molten Salt Reactor Refueling and Reprocessing System Analysis Code Based on SCALE, 原子能科学技术, 2018, 第 2 作者
(29) 小型模块化钍基熔盐堆防核扩散性能初步定量评估, Preliminary Quantitative Proliferation Resistance Assessment of Small Modular Thorium Based MSR, 原子能科学技术, 2018, 第 7 作者
(30) Preliminary study on TRUs utilization in a small modular Th-based molten salt reactor (smTMSR), NUCLEAR ENGINEERING AND DESIGN, 2018, 第 1 作者
(31) 149Sm evolution behavior in a small modular molten salt reactor, Annals of Nuclear Energy, 2018, 第 4 作者
(32) Effects of fuel salt composition on fuel salt temperature coefficient(FSTC) for an under-moderated molten salt reactor(MSR), Effects of fuel salt composition on fuel salt temperature coefficient(FSTC) for an under-moderated molten salt reactor(MSR), NUCLEAR SCIENCE AND TECHNIQUES, 2018, 第 4 作者
(33) Development and application of optimal burnup estimation methodology for pebble bed reactor, ANNALS OF NUCLEAR ENERGY, 2018, 第 4 作者
(34) Flow effect on I-135 and Xe-135 evolution behavior in a molten salt reactor, NUCLEAR ENGINEERING AND DESIGN, 2017, 第 5 作者
(35) Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor, ANNALS OF NUCLEAR ENERGY, 2017, 第 4 作者
(36) Flow effect on 135I and 135Xe evolution behavior in a molten salt reactor, Nuclear Engineering and Design, 2017, 第 5 作者
(37) Optimization of temperature coefficient and breeding ratio ratiofor a graphite-moderated molten salt reactor, Nuclear Engineering and Design, 2015, 
(38) Breed-and-burn strategy in a fast reactor with optimized starter fuel, PROGRESS IN NUCLEAR ENERGY, 2015, 第 6 作者
(39) 轻水堆乏燃料和钍燃料在ACR-700利用的探索, Investigation of Potential Utilization for Light Water Reactor Spent Fuel and Thorium Fuel in ACR-700, 原子能科学技术, 2013, 第 1 作者
(40) 2400MW先进高温堆的临界与燃耗计算, Criticality and Burnup Analysis of 2 400 MW AHTR, 原子能科学技术, 2012, 第 8 作者
(41) Analyses of production capacity of 89Sr and 90Sr in the 2 MW molten salt reactor, Applied Radiation and Isotopes, 第 4 作者

科研活动

   
科研项目
( 1 ) 深燃耗运行模式下熔盐堆嬗变次锕系核素机理研究, 负责人, 国家任务, 2021-01--2023-12
( 2 ) 闭式燃料循环性能研究, 负责人, 中国科学院计划, 2022-01--2026-12
参与会议
(1)Th-U fuel cycle for MSR in China   2019-05-20
(2)Preliminary Analysis of Thorium Based Molten Salt Reactors started with TRU   2016-09-18
(3)Preliminary Analysis of Self-breeding and Radioactivity on TMSR   2013-07-29

指导学生

现指导学生

王楷龙  硕士研究生  082701-核能科学与工程