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中国科学院上海应用物理研究所机构知识库
Knowledge Management System Of Shanghai Institute of Applied Physics, CAS
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中科院上海应用物理... [20]
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Sensitivity/uncertainty comparison and similarity analysis between TMSR-LF1 and MSR models
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2020, 卷号: 122, 页码: -
Authors:
Liu, YF
;
Yan, R
;
Zou, Y
;
Yu, SH
;
Zhou, B
;
Kang, XZ
;
Hu, JF
;
Cai, XZ
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View/Download:41/9
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Submit date:2021/09/06
NUCLEAR-SCIENCE
SALT
CORE
LR-0
SENSITIVITY
CRITICALITY
LIBRARY
DESIGN
Evaluation of Mo-99 production in a small modular thorium based molten salt reactor
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2020, 卷号: 124, 页码: -
Authors:
Kang, XZ
;
Zhu, GF
;
Yan, R
;
Liu, YF
;
Zou, Y
;
Dai, Y
;
Cai, XZ
Adobe PDF(895Kb)
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Submit date:2021/09/06
Influence of Li-7 enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2020, 卷号: 120, 页码: -
Authors:
Zhou, J
;
Chen, JG
;
Wu, JH
;
Xia, SP
;
Zou, CY
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View/Download:34/7
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Submit date:2021/09/06
CYCLE
Dynamic analysis for a 2 MW liquid-fueled molten salt reactor
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2020, 卷号: 126, 页码: -
Authors:
Cui, Y
;
Cui, L
;
Xia, SP
;
Chen, JG
;
Cai, XZ
Adobe PDF(2567Kb)
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Submit date:2021/09/06
DELAYED NEUTRON FRACTION
CYCLE
CODE
Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2019, 卷号: 114, 期号: -, 页码: 84—90
Authors:
Zhu, GF
;
Liu, SJ
;
Zou, Y
;
Yan, R
;
Tan, ML
;
Kang, XZ
;
Li, MH
;
Zhou, B
;
Dai, Y
Adobe PDF(3067Kb)
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View/Download:106/28
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Submit date:2019/12/30
URANIA FUEL
CORE
Monte Carlo burnup code development based on multi-group cross section method
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2019, 卷号: 110, 期号: -, 页码: 24—29
Authors:
Zhu, GF
;
Yan, R
;
Dai, M
;
Yu, SH
;
Kang, XZ
;
Yu, XH
;
Cai, XZ
;
Liu, GM
;
Zou, Y
Adobe PDF(2163Kb)
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View/Download:102/20
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Submit date:2019/12/30
NUCLEAR-DATA
Study on background shielding for a compact photoneutron source
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2019, 卷号: 115, 页码: 74-79
Authors:
Wang, XH
;
Liu, LX
;
Hu, JF
;
Han, JL
;
Yang, P
;
Zhang, GL
;
Wang, NX
;
Cai, XZ
;
Wang, HW
;
Chen, JG
Adobe PDF(2143Kb)
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Submit date:2020/10/16
NEUTRON SOURCE
DESIGN
Preparation, shielding properties and mechanism of a novel neutron shielding material made from natural Szaibelyite resource
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 106, 期号: -, 页码: 140-145
Authors:
Dong, MG
;
Xue, XX
;
Li, ZF
;
Yang, H
;
Sayyed, MI
;
Elbashir, BO
Adobe PDF(998Kb)
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Submit date:2019/12/17
GAMMA-RAY
COLEMANITE
CONCRETE
COMPOSITES
NUMBER
RUBBER
CHINA
TESTS
ORES
Optimization of Th-U fuel breeding based on a single-fluid double-zone thorium molten salt reactor
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 108, 期号: -, 页码: 144-151
Authors:
Li, GC
;
Cong, P
;
Yu, CG
;
Zou, Y
;
Sun, JY
;
Chen, JG
;
Xu, HJ
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Adobe PDF(2633Kb)
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View/Download:90/25
  |  
Submit date:2019/12/17
ADVANTAGES
DESIGN
CYCLE
MSR
Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings
期刊论文
PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 109, 期号: -, 页码: 171-179
Authors:
Sun, KC
;
Wilson, J
;
Hauptman, S
;
Ji, RM
;
Dave, AJ
;
Zou, Y
;
Hu, LW
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View/Download:67/10
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Submit date:2019/12/17
REACTOR
PACKING