会议文集


文集名Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
会议名31st International Conference on Nuclear Engineering (ICONE31)
中译名《第三十一届国际核工程会议，卷2》
机构American Society of Mechanical Engineers (ASME)
会议日期4-8 August 2024
会议地点Prague, Czech Republic
出版年2024
馆藏号354061


题名作者出版年
SIMULATION CALCULATION OF THE UTILIZATION RATE OF URANIUM RESOURCES ON THE ADANES FUEL CYCLEXuesong Yan; Yucui Gao; Yaling Zhang; Lei Yang2024
THERMAL CUT-OFF ENERGY FOR ACCURATE ANALYSIS OF PRISMATIC HIGH-TEMPERATURE GAS-COOLED REACTORSatoshi Takeda; Hiroki Koike; Takanori Kitada; Koji Asano; Akio Yamamoto; Kazuya Yamaji2024
INTERNAL NITRIDATION OF NI-BASED SUPERALLOY IN617 DURING AGING AT 950℃Yue Wang; Kejian Li; Hongsheng Zhao; Haitao Wang; Li Shi2024
RESEARCH ON FUEL PEBBLE MODELING METHODS COMPARISON AND EIGENVALUE ANALYSIS OF THE RUNNING-IN PHASE OF HTR-PMQianye Yang; Nan Gui; Jiyuan Tu; Shengyao Jiang2024
FURTHER INVESTIGATION OF NEUTRON NOISE UNDER THE CONDITION OF FUEL FAILURE BASED ON FREQUENCY DOMAIN FINITE ELEMENT METHODBaoxin Yuan; Zihan Chen; Huiyi Lv; Huan Huang; Herong Zeng; Songbao Zhang; Jie Zheng; Dazhi Qian2024
EVALUATION OF EXPANSION REACTIVITY BASED ON REACTIVITY COEFFICIENT FOR SODIUM-COOLED FAST REACTORSatoshi Takeda; Takanori Kitada; Eiji Hoashi; Takafumi Okita2024
HYDROGEN ABSORPTION BEHAVIOR OF THE R-SUS304ULC/Ta/Zr DISSIMILAR METAL JOINT UNDER NaOH IMMERSIONYasuhiro Ishijima; Fumiyoshi Ueno; Hitoshi Abe; Takahiro Igarashi2024
STRUCTURAL DESIGN AND ANALYSIS OF PLATE-TYPE FUEL ASSEMBLY OF RESEARCH REACTORHyun-Jung Kim; Young-Wook Tahk; Dong-Hyun Kim2024
ISOTOPIC MEASUREMENT OF HTR-10 IRRADIATED FUELS BASED ON ANTI-COMPTON GAMMA SPECTROSCOPIC METHODWeijian ZHANG; Haiyan XIAO; Jingang LIANG; Ruihan LI; Liguo ZHANG2024
RESEARCH ON THE DEPENDENCY BETWEEN TRANSURANIC ISOTOPES AND BURNUP IN PEBBLE BED HIGH-TEMPERATURE REACTORSHongjian Zhang; Qing Zhu; Liguo Zhang; Tao Ma2024
NEUTRONICS-MECHANICS COUPLING FOR FAST TRANSIENT SIMULATION IN MOLTEN SALT REACTORSTheo Vidril; Stanislas de Lambert; Nicolas Lelong; Florence Drui; Cyril Patricot; Elsa Merle2024
HYDRODYNAMICS OF HIGH-DENSITY PARTICLES IN A MULTISTAGE FLUIDIZED BED WITH DOWNCOMERSYiming Zhang; Ying Yang; Huan Wang; Shuyue Li; Yongmin Zhang; Xiuhua Wu2024
DEVELOPMENT AND INITIAL ANALYSIS OF A NEUTRON DIFFUSION MODEL FOR TEPLATOR USING COMSOL MULTIPHYSICS SOFTWAREDipanjan Ray; Martin Lovecky; Jiri Zavorka; Radek Skoda2024
FURTHER STUDY OF CHINA'S STRATEGY FOR CLOSED NUCLEAR FUEL CYCLE DEVELOPMENT AGAINST THE CARBON NEUTRALITY TARGETDing Chen; Lei Shi; Jiqiang Su; Yan An; Yihan Wang2024
MULTI-MESH APPROACH FOR GEOMETRY-INDEPENDENT NEUTRONIC/THERMAL-HYDRAULICS COUPLING ANALYSES USING RMC AND ANSYS FLUENTXingyu ZHAO; Guodong LIU; Shanfang HUANG; Qiaoyan CHEN; Hao LUO; Ying HE; Junren HOU; Kan WANG2024
A PRECONDITIONING METHOD BASED ON STRONGLY IMPLICIT PROCEDURE FOR THE MULTI- DIAGONAL EQUATIONBo Tan; Haojie Zhang; Yutong Wen; Ding She2024
OVERVIEW OF TRITIUM-RESISTANT PERFORMANCE OF HEAT TRANSFER TUBE MATERIALS IN REACTORSMengjie Wu; Ziling Zhou; Yu Wang; Zhengzhe Qu; Jing Chen; Feng Xie; Jianzhu Cao; Jiejuan Tong2024
VALIDATION OF DOPPLER REACTIVITY FEEDBACK IN SPERT-III E-CORE WITH THE BEST-ESTIMATE TRANSIENT CODE TRAC TOSHIBA VERSIONTohru Egawa; Mikio Tokashiki; Takamasa Miyaji; Takanori Fukunaga2024
NEUTRONICS STUDY AND CONCEPTUAL DESIGN FOR SMALL SOLIDIUM-COOLED-FAST-REACTOR WITH ANNULAR FUELBin Ye; Ayodeji A. Ala2024
PRELIMINARY INVESTIGATION ON BURST BEHAVIORS OF ZR-BASED CLADDING UNDER SIMULATED LOCA CONDITIONSZhengang Duan; Bo Yuan; Qinglong Wen; Kang Chen2024
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