从事小型模块化钍基熔盐堆物理设计工作，包括：熔盐堆概念设计，堆芯方案选型研究，熔盐堆燃料循环与燃料管理，堆芯反应性控制与瞬态运行安全，熔盐堆多物理耦合方法与特性研究，如堆芯石墨组件辐照形变核热力耦合行为，熔盐堆内气体、难溶贵金属迁移沉积演化规律研究等。

   

082701-核能科学与工程
070202-粒子物理与原子核物理
082703-核技术及应用

反应堆物理；多物理耦合；核燃料循环

2023-12--中国科学院上海应用物理研究所   研究员
2018-12--2023-12   中国科学院上海应用物理研究所   副研究员
2015-07--2018-12   中国科学院上海应用物理研究所   助理研究员
2010-09--2015-07   中国科学院上海应用物理研究所   博士
2006-09--2010-06   武汉大学物理科学与技术学院   学士

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（1） Effect of molten salt redox states on the chemical behavior of Tellurium: A machine learning molecular dynamics study, Annals of Nuclear Energy, 2026, 第 2 作者  通讯作者
（2） Extension of the formula between reactivity and concentrations of fissile and non-fissile nuclide in the fuel salt for thermal neutron spectrum molten salt reactors, NUCLEAR ENGINEERING AND TECHNOLOGY, 2026, 第 2 作者  通讯作者
（3） Linear relationship between reactivity and the reciprocal of uranium concentration in thermal-spectrum molten salt reactors, Nuclear Science and Techniques, 2026, 第 2 作者  通讯作者
（4） Design of a prismatic CERMET megawatt gas-cooled reactor(PC-MGCR) for deep space exploration, ANNALS OF NUCLEAR ENERGY, 2025, 第 3 作者
（5） Numerical Simulation of Entrained Bubbles Flow in the Shell-Tube Heat Exchanger of MSRs Based on Population Balance Model, International Journal of Energy Research, 2025, 第 2 作者  通讯作者
（6） Thermodynamic Analysis and Optimization of Mobile Nuclear System, ENERGIES, 2025, 第 2 作者
（7） Research on leakage and migration behavior of 87Kr/135mXe in the Molten Salt Reactor containment, PROGRESS IN NUCLEAR ENERGY, 2025, 第 2 作者
（8） Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method, PROGRESS IN NUCLEAR ENERGY, 2025, 第 2 作者  通讯作者
（9） The minimum burnup requirement analysis for molten chlorine-salt fast reactor, NUCLEAR ENGINEERING AND DESIGN, 2025, 第 2 作者
（10） Numerical simulation of noble metal particles deposition in shell-tube heat exchangers of MSRs based on RSM-DPM model, Nuclear Engineering and Design, 2025, 第 2 作者  通讯作者
（11） Research on leakage monitoring and diagnosis of radioactive gas in the molten salt reactors, Nuclear Engineering and Design, 2025, 第 3 作者  通讯作者
（12） 基于 SiC 包覆燃料颗粒的微型反应堆全寿期内的功率分布展平研究, HE JISHU, 2025, 第 2 作者  通讯作者
（13） The decay heat distribution calculation in molten salt reactor experiment based on the nuclide flow-transfer-burnup coupling method, Progress in Nuclear Energy, 2025, 第 2 作者  通讯作者
（14） 反应堆瞬时短周期与反应性引入速率约束问题研究, 核技术, 2024, 第 1 作者
（15） 熔盐堆散体石墨组件堆芯结构变化对核反应性的影响, 核技术, 2024, 第 2 作者  通讯作者
（16） Evaluation of Transport-Burnup Coupling Strategy in Double-Heterogeneity Problem, ENERGIES, 2024, 第 6 作者
（17） Preliminary analysis of the irradiation deformation of a typical molten salt reactor graphite component, PROGRESS IN NUCLEAR ENERGY, 2024, 第 4 作者  通讯作者
（18） THE GENERAL QUADRANT MESHING APPROACH FOR CONSTRUCTIVE SOLID GEOMETRY BASED METHOD OF CHARACTERISTICS, PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 10, ICONE31 2024, 2024, 第 2 作者
（19） Evaluation on 131I production based on molten salt reactor off-gas extraction, ANNALS OF NUCLEAR ENERGY, 2024, 第 4 作者
（20） Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library, SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2024, 第 7 作者
（21） Development and Verification of a Multi-Physics Transport Code of Molten Salt Reactor Fission Products, ENERGIES, 2024, 第 5 作者
（22） Core Optimization for Extending the Graphite Irradiation Lifespan in a Small Modular Thorium-Based Molten Salt Reactor, Journal of Nuclear Engineering, 2024, 第 2 作者  通讯作者
（23） 双面冷却熔盐堆组件热工分析程序开发与验证, 核技术, 2024, 第 3 作者
（24） Plutonium utilization in a small modular molten-salt reactor based on a batch fuel reprocessing scheme, Plutonium utilization in a small modular molten-salt reactor based on a batch fuel reprocessing scheme, NUCLEAR SCIENCE AND TECHNIQUES, 2024, 第 3 作者
（25） Method of characteristics with a new Macro-track transport acceleration for complex general geometry, Annals of Nuclear Energy, 2024, 第 2 作者
（26） Comparative Irradiated Dimensional Change Strain Analyses of Two Types of Graphite Components in a Thorium Molten Salt Reactor, ENERGIES, 2024, 第 4 作者
（27） Neutronics and thermal-hydraulics coupled analysis on dimensional change and lifespan of graphite components in small modular molten salt reactor, NUCLEAR ENGINEERING AND DESIGN, 2024, 第 4 作者  通讯作者
（28） 基于熔盐堆尾气提取的99Mo生产评估, Evaluation of 99Mo production based on molten salt reactor off-gas extraction, 核技术, 2024, 第 2 作者
（29） The Study of Continuous Core Zoning to Extend the Graphite Component Irradiation Lifespan in Molten Salt Reactor, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2024, 第 2 作者  通讯作者
（30） Verification of method of characteristics with general quadrant meshing technique for complex geometry, 31st International Conference on Nuclear Engineering (ICONE31), 2024, 第 2 作者
（31） 水溶液堆中子学优化和提取方式对^（99）Mo生产效率的影响研究, Effect of neutronics optimization and extraction method on the production efficiency of ^(99)Mo in an aqueous reactor, 核技术, 2023, 第 2 作者  通讯作者
（32） Comparative Study on the Neutronic Performance of Thermal and Fast Molten Salt Reactors under Once-Through Fuel Cycle, International Journal of Energy Research, 2023, 第 2 作者  通讯作者
（33） Neutron/Gamma Radial Shielding Design of Main Vessel in a Small Modular Molten Salt Reactor, JOURNAL OF NUCLEAR ENGINEERING, 2023, 第 2 作者  通讯作者
（34） Core nuclear design and heat transfer analysis of a megawatt-level SiC coated particle based vehicular micro reactor, NUCLEAR ENGINEERING AND DESIGN, 2023, 第 2 作者  通讯作者
（35） VOLUME CHANGE ANALYSIS OF PRIMARY LOOP IN A SMALL MODULAR THORIUM -BASED MOLTEN SALT REACTOR, ICONE-29, 2022, 第 1 作者
（36） 熔盐堆间冷回热式氦气轮机热力循环效率分析, Thermodynamic Cycle Efficiency Analysis of MSR Intercooled Recuperated Helium Gas Turbine, 汽轮机技术, 2022, 第 4 作者
（37） Conceptual design and neutronic analysis of a megawatt-level vehicular microreactor based on TRISO fuel particles and S-CO_(2) direct power generation, Conceptual design and neutronic analysis of a megawatt-level vehicular micro reactor based on TRISO fuel particles and S-CO2 direct power generation, NUCLEAR SCIENCE AND TECHNIQUES, 2022, 第 2 作者  通讯作者
（38） Burnup optimization of once-through molten salt reactors using enriched uranium and thorium, Burnup optimization of once-through molten salt reactors using enriched uranium and thorium, 核技术（英文版）, 2022, 第 2 作者  通讯作者
（39） 小型模块化熔盐堆误提棒ATWS事故分析, ATWS accident analysis of rod withdrawal in small modular molten salt reactor, 核技术, 2022, 第 4 作者
（40） 液态燃料氯盐快堆最小需求燃耗分析, Minimum Required Burnup Analysis of Liquid-fueled Molten Chlorine Salt Fast Reactor, 核动力工程, 2022, 第 2 作者
（41） Spent fuel characteristics for thorium-uranium recycle in fluoride-salt-cooled solid-fuel fast reactor, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 2 作者
（42） Representative sampling analysis of radioactive airborne effluent for the stack system in a molten salt reactor, PROGRESS IN NUCLEAR ENERGY, 2021, 第 3 作者
（43） A new structure design to extend graphite assembly lifespan in small modular molten salt reactors, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 3 作者  通讯作者
（44） Study on the production characteristics of I-131 and Sr-90 isotopes in a molten salt reactor, NUCLEAR SCIENCE AND TECHNIQUES, 2021, 第 4 作者
（45） Neutronics Analysis for MSR Cell with Different Fuel Salt Channel Geometry, 2021, 
（46） Thorium-uranium close fuel cycle in fluoride-salt-cooled solid-fuel fast reactor with two recycle strategies, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 2 作者
（47） 后处理效率对熔盐堆燃料循环性能的影响, Influence of reprocessing efficiency on fuel cycle performances for molten salt reactor, 核技术, 2021, 第 4 作者
（48） Neutronic effect of graphite dimensional change in a small modular molten salt reactor, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 1 作者
（49） Neutronics analysis for MSR cell with different fuel salt channel geometries, Neutronics analysis for MSR cell with different fuel salt channel geometries, NUCLEAR SCIENCE AND TECHNIQUES, 2021, 第 5 作者
（50） Preliminary neutron study of a thorium-based molten salt energy amplifier, Preliminary neutron study of a thorium-based molten salt energy amplifier, NUCLEAR SCIENCE AND TECHNIQUES, 2020, 第 4 作者
（51） Study on dynamic characteristics of fission products in 2 MW molten salt reactor, Study on dynamic characteristics of fission products in 2 MW molten salt reactor, NUCLEAR SCIENCE AND TECHNIQUES, 2020, 第 8 作者
（52） 熔盐冷却球床实验堆堆内热源分布计算与分析, Calculation and Analysis of Heat Source in Pebble Bed Fluoride Salt Cooled Test Reactor, 原子能科学技术, 2020, 第 5 作者
（53） Evaluation of 99Mo production in a small modular thorium based molten salt reactor, PROGRESS IN NUCLEAR ENERGY, 2020, 第 2 作者  通讯作者
（54） 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 3 作者
（55） 在线加钚模式下的熔盐堆钍铀燃料可持续性研究, Study on the sustainability of thorium uranium fuel in Molten Salt Reactor under on-line plutonium loading model, 核技术, 2020, 第 2 作者  通讯作者
（56） Core neutronic characterization of a large molten-salt cooled thorium-based solid fuel fast reactor, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2020, 第 2 作者
（57） Study on dynamic characteristics of activated products source term in secondary loop of integrated molten salt reactor, RADIATION PHYSICS AND CHEMISTRY, 2020, 第 8 作者
（58） 小型模块化氟盐冷却高温堆可燃毒物布置方案, Placement scheme of burnable poisons in a small modular fluoride-cooled high temperature reactor, 核技术, 2020, 第 2 作者  通讯作者
（59） Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor, PROGRESS IN NUCLEAR ENERGY, 2019, 第 1 作者
（60） Monte Carlo burnup code development based on multi-group cross section method, PROGRESS IN NUCLEAR ENERGY, 2019, 第 1 作者
（61） Research on the effect of the heavy nuclei amount on the temperature reactivity coefficient in a small modular molten salt reactor, Research on the effect of the heavy nuclei amount on the temperature reactivity coefficient in a small modular molten salt reactor, 核技术:英文版, 2019, 第 2 作者  通讯作者
（62） 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 1 作者
（63） 熔盐实验堆堆芯物理参数研究, Study on core physical parameters for molten salt experimental reactor, 核技术, 2019, 第 7 作者
（64） 熔盐实验堆堆芯结构变化对反应性的影响分析, Effect analysis of core structure changes on reactivity in molten salt experimental reactor, 核技术, 2019, 第 5 作者
（65） 熔盐实验堆备用停堆方案及其可行性分析, Standby shutdown modes and feasibility analysis of molten salt experimental reactor, 核技术, 2019, 第 5 作者
（66） 氟盐冷却高温堆主冷却剂系统16N源项分析, Analysis of 16N Source Term in Primary Coolant System of FHR, 原子能科学技术, 2018, 第 5 作者
（67） 动态参数直接统计方法在TMSR-SF1中的应用, An application of direct statistical method for kinetics parameters in TMSR-SF1, 核技术, 2018, 第 1 作者
（68） 小型模块化熔盐堆控制棒布置的物理分析, Physical Analysis of Control Rods Arrangement in Core of a Small Modular Molten Salt Reactor, 核动力工程, 2018, 第 2 作者
（69） 固态燃料钍基熔盐实验堆燃耗补偿棒位计算, Location calculation of shim rods in thorium molten salt reactor with solid fuel, 核技术, 2018, 第 1 作者
（70） Monte Carlo Burnup Code Development Based on Multigroup Cross Section Method, Progress in Nuclear Energy, 2018, 第 1 作者
（71） Preliminary study on TRUs utilization in a small modular Th-based molten salt reactor (smTMSR), NUCLEAR ENGINEERING AND DESIGN, 2018, 第 2 作者
（72） 放射性气溶胶测量腔室内颗粒输运沉积模拟研究, Simulation and analysis of particles transportion and deposition in radioactive aerosols measuring chamber, 核技术, 2018, 第 5 作者
（73） 正常运行工况熔盐堆主回路衰变热特性研究, Analysis of decay heat in primary loop of molten salt reactor under normal conditions, 核技术, 2018, 
（74） MCNP5在固态燃料熔盐堆功率分布计算的应用, 强激光与粒子束, 2017, 第 3 作者
（75） 基于CITATION-ORIGEN2球床堆平衡态计算程序的实现, Burnup Calculation for Equilibrium Cycle of Pebble-bed Reactor with CITATION-ORIGEN2 Codes, 原子能科学技术, 2017, 第 2 作者
（76） Evaluation of the fraction of delayed photoneutrons for TMSR-SF1, NUCLEAR SCIENCE AND TECHNIQUES, 2017, 第 3 作者
（77） The feasibility research of thorium breeding using fast reactor coolant fluoride salt as a, PROGRESS IN NUCLEAR ENERGY, 2017, 第 2 作者
（78） Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel, NUCLEAR SCIENCE AND TECHNIQUES, 2017, 第 2 作者
（79） 氟盐冷却高温堆主冷却剂放射性源项研究, Study on Radioactive Source Term of Primary Coolant System in Fluoride Salt Cooled High Temperature Reactor, 原子能科学技术, 2017, 第 5 作者
（80） 超级均匀化方法用于球床氟盐冷却高温堆扩散计算, 核技术, 2017, 第 2 作者
（81） Sustainability of thorium-uranium in pebble-bed fluoride salt-cooled high temperature reactor, EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 2016, 第 1 作者
（82） 氟盐冷却球床堆球栅元少群截面计算, Generation of Few-group Cross Sections for Pebble-bed Fluoride-salt-cooled High-temperature Reactors, 原子能科学技术, 2015, 第 2 作者
（83） Uranium utilization with thorium blanket in Pebble Bed Fluoride salt-cooled high temperature reactor, PROGRESS IN NUCLEAR ENERGY, 2015, 第 1 作者
（84） 板型先进高温堆的可燃毒物装载优化, 核技术, 2015, 第 5 作者
（85） 球床高温堆平衡态燃耗计算程序的开发, Development of Burnup Calculation Code for Pebble-bed High Temperature Reactor at Equilibrium State, 原子能科学技术, 2015, 第 1 作者
（86） PB-FHR堆芯活性区体积对冷却剂温度反应性系数影响的研究, Study on the influence of core volume of PB-FHR on coolant temperature reactivity coefficient, 核技术, 2014, 第 4 作者
（87） 氟盐球床堆中钍铀的基本物理参量研究, 核动力工程, 2014, 第 1 作者
（88） 球床氟盐冷却高温堆中6Li摩尔浓度对冷却剂温度反应性系数影响的研究, 核技术, 2014, 第 4 作者

已指导学生

许正昊  硕士研究生  082701-核能科学与工程  

现指导学生

唐嘉诚  硕士研究生  082701-核能科学与工程  

曹金通  博士研究生  082701-核能科学与工程