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Uncertainty Analysis of Reactor Structure Material Activation Calculation Induced From Nuclear Data
Frontiers in Energy Research, 2022 Highly accurate activation calculations are the basis of radiation protection optimization design, and the accuracy of activation calculations depends on nuclear data.
Wu Jiebo +7 more
doaj +3 more sources
Development and validation of reactor nuclear design code CORCA-3D
Nuclear Engineering and Technology, 2019 The advanced node core code CORCA-3D is one of the independent developed codes of NPIC for the nuclear reactor core design. CORCA-3D code can calculate the few-group cross section, solve the 3D diffusion equations, consider the thermal-hydraulic feedback,
Ping An +5 more
doaj +3 more sources
Verification and validation of SuperMC3.2 with heavy water reactor model DCA [PDF]
Nuclear Technology and Radiation Protection, 2020 The super multi-functional calculation program for nuclear design and safety evaluation is a general, intelligent, accurate and precise simulation software system for the nuclear design and safety evaluations.
Gan Quan +4 more
doaj +1 more source
A New Numerical Nuclear Reactor Neutronics Code SHARK
Frontiers in Energy Research, 2021 In order to establish the next-generation reactor physics calculation method based on the numerical nuclear reactor technology and realize high-fidelity modeling and calculation, a new numerical nuclear reactor neutronics code SHARK is developed.
Chen Zhao +9 more
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Effects of different nuclear evaluation data on the RMC keff calculation [PDF]
EPJ Web of Conferences, 2020 Neutron cross section data is the basis of nuclear reactor physical calculation and has a decisive influence on the accuracy of calculation results. AFA3Gassemble is widely used in nuclear power plants.
Wenxin Zhang +3 more
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Evaluation of fast fission factor in a typical pool type research reactor [PDF]
Journal of Nuclear Research and Applications, 2022 One of the important factors of a nuclear reactor core is the fast fission factor. This paper calculates this parameter based on space and energy-dependent method using the PTRAC card of MCNPX code. Tehran research reactor (TRR) is taken as a case study,
M. Arkani, S. Khakshournia
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Mesh-based activation analysis for structural materials in nuclear reactor
He jishu, 2022 BackgroundNuclear reactor structural material activation analysis is an important part of nuclear reactor radiation safety analysis. The traditional cell-based activation analysis method can not describe the non-uniform spatial activation effect inside ...
LI Leiming +6 more
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Trudy Odesskogo Politehničeskogo Universiteta, 2019 The VVER reactor investigation is an important goal for Ukrainian nuclear energy. Different deterministic and stochastic codes are using for this purpose.
Володимир Іванович Гулік +3 more
doaj +5 more sources
CEA-JSI Experimental Benchmark for validation of the modeling of neutron and gamma-ray detection instrumentation used in the JSI TRIGA reactor [PDF]
EPJ Web of Conferences, 2021 Constant improvements of the computational power and methods as well as demands of accurate and reliable measurements for reactor operation and safety require a continuous upgrade of the instrumentation.
Fausser Clément +18 more
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Sensitivity and uncertainty analysis of BEAVRS core keff
He jishu, 2022 BackgroundThe uncertainty calculation of nuclear data plays an important role in reactor core physics.PurposeThis study aims to search nuclear reaction cross section that has the greatest influence on keff calculation results so as to reduce engineering ...
QIN Kaiwen +5 more
doaj +1 more source