082701-核能科学与工程
082702-核燃料循环与材料
082703-核技术及应用

反应堆物理设计
核燃料循环物理分析
屏蔽材料优化设计

2006-09--2011-07   中国科学院高能物理研究所   理学博士
2002-09--2006-07   山东师范大学   理学学士

   

2019-12~现在, 中国科学院上海应用物理研究所, 副研究员
2012-05~2019-12,中国科学院上海应用物理研究所, 助理研究员
2011-10~2012-05,意大利国家原子物理研究所, 访问学者

   

（1） 中国科学院上海应用物理研究所2021年度三八红旗手, 研究所（学校）, 2021

[1] 李晓晓, 崔德阳, 邹春燕, 任翠兰, 蒋力, 傅瑶, 陈金根, 邹杨, 蔡翔舟. 一种稀土镍合金材料及其建模方法和制备方法. CN116205032A, 2023-06-02.
[2] 李晓晓, 傅瑶, 邹杨, 陈金根, 蔡翔舟. 一种屏蔽体结构及含其的反应堆. CN114914000A, 2022-08-16.
[3] 李晓晓, 傅瑶, 邹杨, 陈金根, 蔡翔舟. 一种屏蔽体结构及含其的反应堆. CN: CN218038586U, 2022-12-13.
[4] 李晓晓, 陈金根, 邹杨, 蔡翔舟. 一种熔盐快堆. CN: CN216311353U, 2022-04-15.
[5] 李晓晓, 陈金根, 邹杨, 蔡翔舟. 一种熔盐快堆. CN: CN114093529A, 2022-02-25.
[6] 李晓晓, 邹杨, 傅瑶, 崔德阳, 戴叶, 陈兴伟, 陈金根, 蔡翔舟. 一种控制单元及含其的控制鼓和控制方法. CN: CN113096835A, 2021-07-09.
[7] 李晓晓, 邹杨, 傅瑶, 崔德阳, 戴叶, 陈兴伟, 陈金根, 蔡翔舟. 一种控制单元及含其的控制鼓. CN: CN214705451U, 2021-11-12.
[8] 李晓晓, 崔德阳, 邹杨, 傅瑶, 陈金根, 蔡翔舟. 一种三流道熔盐堆堆芯结构及三流道熔盐堆系统. CN: CN112259263A, 2021-01-22.
[9] 李晓晓, 邹杨, 傅瑶, 余呈刚, 陈金根, 蔡翔舟. 一种液态燃料熔盐堆的反应性控制方法. CN: CN112151197A, 2020-12-29.
[10] 李晓晓, 余呈刚, 陈金根, 蔡翔舟. 以石墨球为慢化剂的液态燃料熔盐堆以及石墨球更换方法. CN: CN111627571B, 2022-02-08.
[11] 周波, 邹杨, 严睿, 冀锐敏, 马玉雯, 李晓晓, 李冬国. 一种一体化堆本体系统及氯盐堆系统. CN: CN108417277B, 2021-06-11.

   

[1] Li, Xiaoxiao, Cui, Deyang, Zou, Chunyan, Ren, Cuilan, Chen, Jingen. Neutron shielding analysis for a gadolinium doped nickel alloy. MATERIALS TODAY COMMUNICATIONS[J]. 2024, 第 1 作者38: http://dx.doi.org/10.1016/j.mtcomm.2023.107933.
[2] Deyang Cui, Ao Zhang, Xiaoxiao Li, Xiangzhou Cai, Jingen Chen, Yang Zou. An assessment of scenarios for transuranic burning and 233U production in a small molten chloride fast reactor. ANNALS OF NUCLEAR ENERGY[J]. 2023, 第 3 作者185: http://dx.doi.org/10.1016/j.anucene.2023.109719.
[3] Xiaoxiao Li, DeYang Cui, Chunyan Zou, Jianhui Wu, Xiangzhou Cai, Jingen Chen. Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium. Nuclear Science and Techniques[J]. 2023, 第 1 作者34(70): 
[4] Wu, Jianhui, Chen, Jingen, Zou, Chunyan, Li, Xiaoxiao. Accident Modeling and Analysis of Nuclear Reactors. ENERGIES[J]. 2022, 第 4 作者15(16): http://dx.doi.org/10.3390/en15165790.
[5] Li, Xiaoxiao, Cui, Deyang, Hu, Guang, Cai, Xiangzhou, Chen, Jingen. Potential of transuranics transmutation in a thorium-based chloride salt fast reactor. INTERNATIONAL JOURNAL OF ENERGY RESEARCH[J]. 2022, 第 1 作者46(12): 16461-16475, http://dx.doi.org/10.1002/er.8309.
[6] Cui, D Y, Li, X X, Dai, Y, Hu, G, Cai, X Z, Zou, Y, Chen, J G. An improved core design of a 50 kWth heat pipe cooled micro Molten Salt Reactor (micro-MSR). PROGRESS IN NUCLEAR ENERGY[J]. 2022, 第 2 作者151: http://dx.doi.org/10.1016/j.pnucene.2022.104326.
[7] 崔勇, 陈金根, 何帆, 李晓晓, 蔡翔舟. 石墨慢化通道式熔盐堆有效缓发中子份额计算方法研究. 原子能科学技术[J]. 2021, 第 4 作者55(8): 1448-1455, http://dx.chinadoi.cn/10.7538/yzk.2020.youxian.0656.
[8] Cui, D Y, Dai, Y, Cai, X Z, Fu, Y, Li, X X, Zou, Y, Chen, J G. Preconceptual nuclear design of a 50 kWth heat pipe cooled micro molten salt reactor (micro-MSR). PROGRESS IN NUCLEAR ENERGY[J]. 2021, 第 5 作者134: http://dx.doi.org/10.1016/j.pnucene.2021.103670.
[9] 胡光, 崔德阳, 卢林远, 李晓晓, 陈金根, 蔡翔舟. 1MWth火星表面热管熔盐堆堆芯初步中子学设计. 核技术[J]. 2021, 第 4 作者  通讯作者  44(12): 97-106, http://lib.cqvip.com/Qikan/Article/Detail?id=7106224828.
[10] 李晓晓, 余呈刚, 马玉雯, 蔡翔舟, 陈金根, 陈兴伟. 大型氯盐快堆中钍铀及铀钚循环分析. 核技术[J]. 2020, 第 1 作者43(11): 70-79, http://lib.cqvip.com/Qikan/Article/Detail?id=7103216930.
[11] 马玉雯, 陈金根, 余呈刚, 伍建辉, 李晓晓. 小型模块化增殖焚烧快堆MA嬗变性能分析. 核技术[J]. 2020, 第 5 作者43(9): 68-74, http://lib.cqvip.com/Qikan/Article/Detail?id=7102729134.
[12] Li Xiaoxiao, Cui Deyang, Ma Yuwen, Cai Xiangzhou, Chen Jingen. Influence of ~(235)U enrichment on the moderator temperature coefficient of reactivity in a graphite-moderated molten salt reactor. NUCLEAR SCIENCE AND TECHNIQUES[J]. 2019, 第 1 作者30(11): 149-159, http://lib.cqvip.com/Qikan/Article/Detail?id=7100240974.
[13] 于世和, 李晓晓, 刘亚芬, 康旭忠, 杨璞, 冀锐敏, 朱贵凤, 周波, 严睿, 邹杨. 熔盐实验堆堆芯物理参数研究. 核技术[J]. 2019, 第 2 作者42(3): 75-80, http://lib.cqvip.com/Qikan/Article/Detail?id=7001432752.
[14] 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, 第 4 作者132: 391-403, http://dx.doi.org/10.1016/j.anucene.2019.04.043.
[15] 胡继峰, 王小鹤, 李文江, 李晓晓, 韩建龙. 熔盐实验堆核数据引起反应性参数不确定度分析. 核技术[J]. 2019, 第 4 作者42(3): 59-67, http://lib.cqvip.com/Qikan/Article/Detail?id=7001432749.
[16] 房勇汉, 蔡翔舟, 陈金根, 胡继峰, 李晓晓, 余呈刚, 伍建辉, 崔德阳. 钍基氟盐冷却高温堆TRISO包覆燃料颗粒结构优化分析. 核技术[J]. 2019, 第 5 作者42(8): 83-92, http://lib.cqvip.com/Qikan/Article/Detail?id=7002668091.
[17] 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 3. 2018, 第 2 作者http://apps.webofknowledge.com/CitedFullRecord.do?product=UA&colName=WOS&SID=5CCFccWmJJRAuMzNPjj&search_mode=CitedFullRecord&isickref=WOS:000461265300050.
[18] 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, 第 6 作者120: 100-107, https://www.webofscience.com/wos/woscc/full-record/WOS:000441485700009.
[19] Fang, Y H, Li, X X, Yu, C G, Chen, J G, Cai, X Z. Fuel pebble optimization for the thorium-fueled Pebble Bed Fluoride salt-cooled high-temperature reactor (PB-TFHR). PROGRESS IN NUCLEAR ENERGY[J]. 2018, 第 2 作者108: 179-187, http://dx.doi.org/10.1016/j.pnucene.2018.05.013.
[20] 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, 第 5 作者52(11): 1994-2000, http://lib.cqvip.com/Qikan/Article/Detail?id=7000915301.
[21] 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, 第 3 作者117: 343-349, http://dx.doi.org/10.1016/j.anucene.2018.03.041.
[22] 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, 第 1 作者  通讯作者  29(8): 126-135, http://lib.cqvip.com/Qikan/Article/Detail?id=675982266.
[23] Cui, D Y, Li, X X, Xia, S P, Zhao, X C, Yu, C G, Chen, J G, Cai, X Z. Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium. PROGRESS IN NUCLEAR ENERGY[J]. 2018, 第 2 作者104: 75-84, http://dx.doi.org/10.1016/j.pnucene.2017.09.003.
[24] De-Yang Cui, Shao-Peng Xia, Xiao-Xiao Li, Xiang-Zhou Cai, Jin-Gen Chen. Transition toward thorium fuel cycle in a molten salt reactor by using plutonium. 核技术：英文版[J]. 2017, 第 3 作者28(10): 103-112, http://lib.cqvip.com/Qikan/Article/Detail?id=673573702.
[25] 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, 第 2 作者99: 335-344, http://dx.doi.org/10.1016/j.anucene.2016.09.025.
[26] 李晓晓, 伍建辉, 余呈刚, 邹春燕, 蔡翔舟, 陈金根. 小型模块化熔盐堆钍利用方案. 原子核物理评论[J]. 2017, 第 1 作者34(3): 672-676, http://lib.cqvip.com/Qikan/Article/Detail?id=673750702.
[27] 冀锐敏, 严睿, 李晓晓, 戴叶, 刘桂民, 邹杨. 球形燃料元件中包覆颗粒的分布效应研究. 核技术[J]. 2017, 第 3 作者40(10): "74-80", 
[28] Cui, DeYang, Xia, ShaoPeng, Li, XiaoXiao, Cai, XiangZhou, Chen, JinGen. Transition toward thorium fuel cycle in a molten salt reactor by using plutonium. NUCLEAR SCIENCE AND TECHNIQUES[J]. 2017, 第 3 作者28(10): http://lib.cqvip.com/Qikan/Article/Detail?id=673573702.
[29] 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, 第 5 作者85: 11-16, http://ir.sinap.ac.cn/handle/331007/24877.
[30] Yu, Chenggang, Li, Xiaoxiao, Cai, Xiangzhou, Zou, Chunyan, Ma, Yuwen, Han, Jianlong, Chen, Jingen. Analysis of minor actinides transmutation for a Molten Salt Fast Reactor. ANNALS OF NUCLEAR ENERGY[J]. 2015, 第 2 作者85: 597-604, http://dx.doi.org/10.1016/j.anucene.2015.06.014.
[31] Ma, Y W, Li, X X, Cai, X Z, Yu, C G, Zou, C Y, Han, J L, Chen, J G. Startup and burnup strategy for Th-U/U-Pu fuel cycles in an EM2 reactor. PROGRESS IN NUCLEAR ENERGY[J]. 2015, 第 2 作者85: 764-770, http://ir.sinap.ac.cn/handle/331007/25046.
[32] Zou, C Y, Cai, X Z, Jiang, D Z, Yu, C G, Li, X X, Ma, Y W, Han, J L, Chen, J G. Optimization of temperature coefficient and breeding ratio for a graphite-moderated molten salt reactor. NUCLEAR ENGINEERING AND DESIGN[J]. 2015, 第 5 作者281: 114-120, http://dx.doi.org/10.1016/j.nucengdes.2014.11.022.
[33] Li, X X, Cai, X Z, Jiang, D Z, Ma, Y W, Huang, J F, Zou, C Y, Yu, C G, Han, J L, Chen, J G. Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor. PROGRESS IN NUCLEAR ENERGY[J]. 2015, 第 1 作者78: 285-290, http://ir.sinap.ac.cn/handle/331007/24395.
[34] 陈亮, 陈金根, 李晓晓, 蔡翔舟, 孙建友, 蒋大真, 姚泽恩. 不同燃料组合在液态氟盐冷却高温堆中的物理性能研究. 核技术[J]. 2014, 第 3 作者37(3): 56-60, http://www.hjs.sinap.ac.cn/thesisDetails#10.11889/j.0253-3219.2014.hjs.37.030601.
[35] Xiaoxiao Li, Deyang Cui, Chunyan Zou, Cuilan Ren, Jingen Chen. Neutron shielding analysis for a gadolinium doped nickel alloy. MATERIALS TODAY COMMUNICATIONS. 第 1 作者http://dx.doi.org/10.1016/j.mtcomm.2023.107933.

   

（ 1 ） 高中子屏蔽高强韧稀土镍合金设计与制备技术, 参与, 国家任务, 2021-12--2025-11
（ 2 ） 熔盐堆复杂多物理耦合机制及方法研究, 参与, 国家任务, 2022-01--2025-12
（ 3 ） 固有安全一体化小型氟盐冷却高温堆技术研究, 参与, 国家任务, 2020-11--2023-10