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] 伍建辉, 蔡翔舟, 陈金根, 邹春燕, 余呈刚, 邹杨, 赵宏凯. 熔盐堆堆芯及熔盐堆系统. CN: CN113936820A, 2022-01-14.
[2] 郁海燕, 朱贵凤, 邹杨, 严睿, 康旭忠, 邹春燕. 一种熔盐堆径向屏蔽结构及含其的熔盐堆. CN: CN113851233A, 2021-12-28.
[3] 邹春燕, 伍建辉, 余呈刚, 陈金根, 邹杨, 蔡翔舟. 一种液态熔盐堆生产Cf-252的系统及方法. CN: CN113851246A, 2021-12-28.
[4] 朱贵凤, 邹杨, 严睿, 郭威, 陈金根, 康旭忠, 邹春燕, 马玉雯, 周波. 一种熔盐堆及其运行方法. CN: CN113744900A, 2021-12-03.
[5] 朱贵凤, 邹杨, 严睿, 康旭忠, 陈金根, 邹春燕, 余呈刚, 周波. 放射性同位素生产装置. CN: CN113539540A, 2021-10-22.
[6] 余呈刚, 朱贵凤, 邹春燕, 康旭忠, 伍建辉, 严睿, 陈金根, 邹杨, 蔡翔舟. 一种液态熔盐堆生产Mo-99的方法以及系统. CN: CN112863725A, 2021-05-28.
[7] 余呈刚, 吴辰, 邹春燕, 王小鹤, 陈金根, 邹杨, 蔡翔舟. 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. CN: CN112863726A, 2021-05-28.
[8] 邹春燕, 余呈刚, 伍建辉, 陈金根, 蔡翔舟, 邹杨. 液态熔盐堆超铀燃料运行固有安全性的改善方法. CN: CN111627570A, 2020-09-04.
[9] 邹春燕, 余呈刚, 伍建辉, 陈金根, 蔡翔舟, 邹杨. 超铀燃料及其制备方法和嬗变方法. CN: CN111627569A, 2020-09-04.
[10] 邹春燕, 邹杨, 陈金根, 朱贵凤, 郭威. 液态熔盐堆嬗变超铀元素的方法. CN: CN110444311A, 2019-11-12.
[11] 伍建辉, 陈金根, 马玉雯, 邹春燕, 余呈刚. 重水慢化熔盐堆堆芯及重水慢化熔盐堆系统. CN: CN108511088A, 2018-09-07.
[12] 朱贵凤, 邹杨, 邹春燕, 康旭忠, 陈金根, 严睿, 谈蒙露. 一种熔盐堆钍燃料循环利用方法. CN: CN108389634A, 2018-08-10.
[13] 朱贵凤, 邹杨, 康旭忠, 戴叶, 周波, 严睿, 邹春燕. 一种熔盐堆堆芯. CN: CN108389632A, 2018-08-10.
[14] 邹春燕, 邹杨, 朱贵凤, 康旭忠, 陈金根, 严睿, 谈蒙露. 一种熔盐堆生产U-233的方法. CN: CN108389638A, 2018-08-10.
[15] 朱贵凤, 邹杨, 康旭忠, 邹春燕, 严睿, 张金红, 周波. 一种熔盐堆上腔室. CN: CN108206065A, 2018-06-26.

出版信息

   
发表论文
[1] Chunyan Zou, Chenggang Yu, Jun Zhou, Shuning Chen, Shaopeng Xia, Yang Zou, Xiangzhou Cai, Jianhui Wu, Jingen Chen. Impacts of core parameters on the capability of Cf-252 production in an MSR. ANNALS OF NUCLEAR ENERGY. 2023, 184: http://dx.doi.org/10.1016/j.anucene.2023.109699.
[2] Wu, Jianhui, Chen, Jingen, Zou, Chunyan, Yu, Chenggang, Cai, Xiangzhou, Zhang, Yapeng, 伍建辉. Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium. ANNALS OF NUCLEAR ENERGY[J]. 2022, 165: http://dx.doi.org/10.1016/j.anucene.2021.108638.
[3] Chen, Shuning, Zhang, Ao, Zou, Chunyan, Chen, Jingen. Impacts of power density on the breeding performance of molten salt reactors. INTERNATIONAL JOURNAL OF ENERGY RESEARCH[J]. 2022, 46(13): 18609-18623, [4] 伍建辉, 余呈刚, 邹春燕, 马玉雯, 贾国斌, 蔡翔舟, 陈金根. 新型重水慢化熔盐堆堆芯优化设计. 核技术[J]. 2021, 44(8): 78-86, http://lib.cqvip.com/Qikan/Article/Detail?id=7105352437.
[5] Zou, Chunyan, Yu, Chenggang, Wu, Jianhui, Cai, Xiangzhou, Chen, Jingen. Parametric study on minor actinides transmutation in a graphite-moderated thorium-based molten salt reactors. INTERNATIONAL JOURNAL OF ENERGY RESEARCH[J]. 2021, 45(5): 7840-7850, https://www.webofscience.com/wos/woscc/full-record/WOS:000604033000001.
[6] Wu Jianhui, Ma Yuwen, Yu Chenggang, Zou Chunyan, Cai Xiangzhou, Chen Jingen. Nuclear non-proliferation review and improving proliferation resistance assessment in the future. INTERNATIONAL JOURNAL OF ENERGY RESEARCH[J]. 2021, 45(8): 11399-11422, http://dx.doi.org/10.1002/er.5486.
[7] Zou, Chunyan, Yu, Chenggang, Wu, Jianhui, Cai, Xiangzhou, Chen, Jingen. Ameliorating the positive temperature feedback coefficient for an MSR fueled with transuranic elements. ANNALS OF NUCLEAR ENERGY[J]. 2021, 160: http://dx.doi.org/10.1016/j.anucene.2021.108325.
[8] Wu, Chen, Yu, Chenggang, Zhang, Ao, Zou, Chunyan, Ma, Yuwen, Wu, Jianhui, Cai, Xiangzhou, Chen, Jingen. Analyses of production capacity of Sr-89 and Sr-90 in the 2 MW molten salt reactor. APPLIED RADIATION AND ISOTOPES[J]. 2021, 173: http://dx.doi.org/10.1016/j.apradiso.2021.109714.
[9] 邹春燕, 伍建辉, 余呈刚, 朱贵凤, 蔡翔舟, 邹杨, 陈金根. 后处理效率对熔盐堆燃料循环性能的影响. 核技术[J]. 2021, 44(10): 48-54, http://lib.cqvip.com/Qikan/Article/Detail?id=7105773714.
[10] Zhu, Guifeng, Guo, Wei, Kang, Xuzhong, Zou, Chunyan, Zou, Yang, Yan, Rui, Dai, Ye. Neutronic effect of graphite dimensional change in a small modular molten salt reactor. INTERNATIONAL JOURNAL OF ENERGY RESEARCH[J]. 2021, 45(8): 11976-11991, http://dx.doi.org/10.1002/er.5964.
[11] 韩冬, 邹春燕, 蔡翔舟, 陈金根. 钍基气冷快堆中^233U与^239Pu的增殖性能研究. 核技术[J]. 2020, 43(10): 84-90, http://lib.cqvip.com/Qikan/Article/Detail?id=7102963982.
[12] KunFeng Ma, ChengGang Yu, XiangZhou Cai, ChunYan Zou, JinGen Chen. Transmutation of 129I in a single-fluid double-zone thorium molten salt reactor. 核技术:英文版[J]. 2020, 31(1): 94-101, http://lib.cqvip.com/Qikan/Article/Detail?id=7100844232.
[13] 邹春燕, 余呈刚, 朱贵凤, 郭威, 蔡翔舟, 陈金根, 邹杨. 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. 核技术[J]. 2020, 43(12): 74-83, http://lib.cqvip.com/Qikan/Article/Detail?id=7103464045.
[14] Ma, KunFeng, Yu, ChengGang, Cai, XiangZhou, Zou, ChunYan, Chen, JinGen. Transmutation of I-129 in a single-fluid double-zone thorium molten salt reactor. NUCLEAR SCIENCE AND TECHNIQUES[J]. 2020, 31(1): https://www.webofscience.com/wos/woscc/full-record/WOS:000513179300003.
[15] 胡继峰, 王小鹤, 邹春燕, 韩建龙, 陈金根. 基于灵敏度对比分析SCALE 6.1自带库与CENDL-TMSR-V1数据库. 原子能科学技术[J]. 2020, 54(8): 1453-1459, http://lib.cqvip.com/Qikan/Article/Detail?id=7102436465.
[16] Chenggang Yu, Chunyan Zou, Chen Wu, Jianhui Wu, Xiangzhou Cai, Jingen Chen. Sustainable supply of 99Mo source in a 2MW molten salt reactor using low-enriched uranium. APPLIED RADIATION AND ISOTOPES. 2020, 160: http://dx.doi.org/10.1016/j.apradiso.2020.109134.
[17] Zou, Chunyan, Yu, Chenggang, Wu, Jianhui, Cai, Xiangzhou, Chen, Jingen. Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode. ANNALS OF NUCLEAR ENERGY[J]. 2020, 138: http://dx.doi.org/10.1016/j.anucene.2019.107163.
[18] Jun Zhou, Jingen Chen, Jianhui Wu, Shaopeng Xia, Chunyan Zou. Influence of 7Li enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra. PROGRESS IN NUCLEAR ENERGY. 2020, 120: http://dx.doi.org/10.1016/j.pnucene.2019.103213.
[19] Yu, Chenggang, Wang, Xiaohe, Wu, Chen, Zou, Chunyan, Wu, Jianhui, Cai, Xiangzhou, Chen, Jingen. Supply of I-131 in a 2 MW molten salt reactor with different production methods. APPLIED RADIATION AND ISOTOPES[J]. 2020, 166: http://dx.doi.org/10.1016/j.apradiso.2020.109350.
[20] Yu, Chenggang, Zou, Chunyan, Wu, Chen, Wu, Jianhui, Cai, Xiangzhou, Chen, Jingen. Sustainable supply of Mo-99 source in a 2 MW molten salt reactor using low-enriched uranium. APPLIED RADIATION AND ISOTOPES[J]. 2020, 160: https://www.webofscience.com/wos/woscc/full-record/WOS:000528842400031.
[21] Zhou, Jun, Chen, Jingen, Wu, Jianhui, Xia, Shaopeng, Zou, Chunyan. Influence of Li-7 enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra. PROGRESS IN NUCLEAR ENERGY[J]. 2020, 120: https://www.webofscience.com/wos/woscc/full-record/WOS:000514024300008.
[22] Zhang, Ao, Zou, Chunyan, Wu, Jianhui, Xia, Shaopeng, Yu, Chenggang, Chen, Jingen. Radiotoxicity of minor actinides in thermal, epithermal and fast TMSRs with very high burnup. ANNALS OF NUCLEAR ENERGY[J]. 2020, 137: http://dx.doi.org/10.1016/j.anucene.2019.107162.
[23] Zhu, Guifeng, Zou, Yang, Yan, Rui, Tan, Menglu, Zou, Chunyan, Kang, Xuzhong, Chen, Jingen, Guo, Wei, Dai, Ye. 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[J]. 2019, 43(11): 5775-5787, https://www.webofscience.com/wos/woscc/full-record/WOS:000478494500001.
[24] 周俊, 陈金根, 余呈刚, 邹春燕. FLi/FLiBe盐中^7Li富集度对熔盐快堆钍铀转换性能的影响研究. 核技术[J]. 2019, 42(11): 75-82, http://lib.cqvip.com/Qikan/Article/Detail?id=7100244086.
[25] Wu, Jianhui, Chen, Jingen, Kang, Xuzhong, Li, Xiaoxiao, Yu, Chenggang, Zou, Chunyan, Cai, Xiangzhou. A novel concept for a molten salt reactor moderated by heavy water. ANNALS OF NUCLEAR ENERGY[J]. 2019, 132: 391-403, http://dx.doi.org/10.1016/j.anucene.2019.04.043.
[26] Yu, Chenggang, Wu, Jianhui, Zou, Chunyan, Cai, Xiangzhou, Ma, Yuwen, Chen, Jingen. Thorium utilization in a small modular molten salt reactor with progressive fuel cycle modes. INTERNATIONAL JOURNAL OF ENERGY RESEARCH[J]. 2019, 43(8): 3628-3639, https://www.webofscience.com/wos/woscc/full-record/WOS:000471071800037.
[27] Jianhui Wu, Jingen Chen, Chenggang Yu, Chunyan Zou, Yuwen Ma, Xiaoxiao Li, Xiangzhou Cai. 149Sm evolution behavior in a small modular molten salt reactor. ANNALS OF NUCLEAR ENERGY. 2018, 120: 100-107, http://dx.doi.org/10.1016/j.anucene.2018.05.037.
[28] Tang, Haibo, Han, Jianlong, Li, XiaoXiao, Zou, Chunyan, Cai, Xiangzhou, Chen, Jingen. Development and application of optimal burnup estimation methodology for pebble bed reactor. ANNALS OF NUCLEAR ENERGY[J]. 2018, 117: 343-349, http://dx.doi.org/10.1016/j.anucene.2018.03.041.
[29] Li, XiaoXiao, Ma, YuWen, Yu, ChengGang, Zou, ChunYan, Cai, XiangZhou, Chen, JinGen. Effects of fuel salt composition on fuel salt temperature coefficient (FSTC) for an under-moderated molten salt reactor (MSR). NUCLEAR SCIENCE AND TECHNIQUES[J]. 2018, 29(8): 126-135, http://lib.cqvip.com/Qikan/Article/Detail?id=675982266.
[30] Wu Jianhui, Li Xiaoxiao, Hu Jifeng, Chen Jingen, Yu Chenggang, Zou Chunyan, Cai Xiangzhou, ASME. INFLUENCE OF XE-135 DYNAMIC BEHAVIOR ON CORE OPERATION SAFETY FOR A MOLTEN SALT REACTOR. PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 3null. 2018, http://apps.webofknowledge.com/CitedFullRecord.do?product=UA&colName=WOS&SID=5CCFccWmJJRAuMzNPjj&search_mode=CitedFullRecord&isickref=WOS:000461265300050.
[31] Zou, C Y, Cai, C Z, Yu, C G, Wu, J H, Chen, J G. Transition to thorium fuel cycle for TMSR. NUCLEAR ENGINEERING AND DESIGN[J]. 2018, 330: 420-428, http://dx.doi.org/10.1016/j.nucengdes.2018.01.033.
[32] Yu, Chenggang, He, Long, Zou, Chunyan, Ma, Yuwen, Cai, Xiangzhou, Wu, Jianhui, Chen, Jingen. Th-U breeding performance in a Channel-type molten salt Fast reactor with different starting fuels. ANNALS OF NUCLEAR ENERGY[J]. 2018, 122: 91-100, http://dx.doi.org/10.1016/j.anucene.2018.08.003.
[33] Wu, Jianhui, Chen, Jingen, Yu, Chenggang, Zou, Chunyan, Ma, Yuwen, Li, Xiaoxiao, Cai, Xiangzhou. Sm-149 evolution behavior in a small modular molten salt reactor. ANNALS OF NUCLEAR ENERGY[J]. 2018, 120: 100-107, https://www.webofscience.com/wos/woscc/full-record/WOS:000441485700009.
[34] 余呈刚, 邹春燕, 伍建辉, 蔡翔舟, 陈金根. 基于SCALE的熔盐堆添料与后处理系统分析程序开发及验证. 原子能科学技术[J]. 2018, 52(12): 2136-2142, http://lib.cqvip.com/Qikan/Article/Detail?id=676857617.
[35] 马玉雯, 陈金根, 蔡翔舟, 伍建辉, 李晓晓, 余呈刚, 邹春燕, 杨璞. 小型模块化钍基熔盐堆防核扩散性能初步定量评估. 原子能科学技术[J]. 2018, 52(11): 1994-2000, http://lib.cqvip.com/Qikan/Article/Detail?id=7000915301.
[36] Zou, Chunyan, Zhu, Guifeng, Yu, Chenggang, Zou, Yang, Chen, Jingen. Preliminary study on TRUs utilization in a small modular Th-based molten salt reactor (smTMSR). NUCLEAR ENGINEERING AND DESIGN[J]. 2018, 339: 75-82, http://dx.doi.org/10.1016/j.nucengdes.2018.08.026.
[37] Wu, Jianhui, Guo, Chen, Cai, Xiangzhou, Yu, Chenggang, Zou, Chunyan, Han, Jianlong, Chen, Jingen. Flow effect on I-135 and Xe-135 evolution behavior in a molten salt reactor. NUCLEAR ENGINEERING AND DESIGN[J]. 2017, 314: 318-325, http://dx.doi.org/10.1016/j.nucengdes.2017.01.019.
[38] Yu, Chenggang, Li, Xiaoxiao, Cai, Xiangzhou, Zou, Chunyan, Ma, Yuwen, Wu, Jianhui, Han, Jianlong, Chen, Jingen. Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor. ANNALS OF NUCLEAR ENERGY[J]. 2017, 99: 335-344, http://dx.doi.org/10.1016/j.anucene.2016.09.025.
[39] Jianhui Wu, Chen Guo, Xiangzhou Cai, Chenggang Yu, Chunyan Zou, Jianlong Han, Jingen Chen. Flow effect on 135I and 135Xe evolution behavior in a molten salt reactor. NUCLEAR ENGINEERING AND DESIGN. 2017, 314: 318-325, http://dx.doi.org/10.1016/j.nucengdes.2017.01.019.
[40] Chen Jingen. Optimization of temperature coefficient and breeding ratio ratiofor a graphite-moderated molten salt reactor. Nuclear Engineering and Design. 2015, [41] Huang, Jinfeng, Han, Jianlong, Cai, Xiangzhou, Ma, Yuwen, Li, Xiaoxiao, Zou, Chunyan, Yu, Chenggang, Chen, Jingen. Breed-and-burn strategy in a fast reactor with optimized starter fuel. PROGRESS IN NUCLEAR ENERGY[J]. 2015, 85: 11-16, http://ir.sinap.ac.cn/handle/331007/24877.
[42] 邹春燕, 陈金根, 蔡翔舟, 蒋大真, 郭锐, 陈堃, 郭威, 胡碧涛. 轻水堆乏燃料和钍燃料在ACR-700利用的探索. 原子能科学技术[J]. 2013, 47(6): 1008-1012, http://lib.cqvip.com/Qikan/Article/Detail?id=46791326.
[43] 李晓恒, 陈金根, 蔡翔舟, 蒋大真, 郭威, 陈堃, 郭锐, 邹春燕, 张鸿飞. 2400MW先进高温堆的临界与燃耗计算. 原子能科学技术[J]. 2012, 46(B09): 379-382, http://lib.cqvip.com/Qikan/Article/Detail?id=43885111.
[44] Chen Wu, Chenggang Yu, Ao Zhang, Chunyan Zou, Yuwen Ma, Jianhui Wu, Xiangzhou Cai, Jingen Chen. Analyses of production capacity of 89Sr and 90Sr in the 2 MW molten salt reactor. APPLIED RADIATION AND ISOTOPES. http://dx.doi.org/10.1016/j.apradiso.2021.109714.

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