Results 121 to 130 of about 25,004 (172)
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Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting
Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, 2022In the reactor, the main purpose of radial shielding was to protect the internal structure and staff from radiation damage. The good shielding material must have both a high elastic scattering cross-section and a high absorption cross-section to reduce
Rui Li, Shichang Liu
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Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, 2022
In order to improve the accuracy of fast reactor physical analysis, two libraries with 1968-group neutron and 21-group photon were generated based on ENDF/B-VIII.0 and ENDF/B-VII.1 data by using NJOY2016.
Teng Zhang +5 more
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In order to improve the accuracy of fast reactor physical analysis, two libraries with 1968-group neutron and 21-group photon were generated based on ENDF/B-VIII.0 and ENDF/B-VII.1 data by using NJOY2016.
Teng Zhang +5 more
semanticscholar +1 more source
Numerical Simulation of Reactor Neutron Noise Based on Discrete Ordinate Finite Element Method
Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, 2022At present, the technology of reactor neutron noise is developing rapidly, which can not only be used to measure some intrinsic parameters of the reactor core, but also be used for core fault diagnosis. The theoretical solution of reactor neutron noise
Bao-Xin Yuan +9 more
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Annals of Nuclear Energy, 2018
Abstract In this paper, the neutron noise based on transport theory and diffusion noise theory using Green’s function technique is calculated. As the neutron noise is used for core diagnostic, surveillance and monitoring, calculation of neutron noise precisely can play an important role in monitoring and safety.
Mona Bahrami, Naser Vosoughi
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Abstract In this paper, the neutron noise based on transport theory and diffusion noise theory using Green’s function technique is calculated. As the neutron noise is used for core diagnostic, surveillance and monitoring, calculation of neutron noise precisely can play an important role in monitoring and safety.
Mona Bahrami, Naser Vosoughi
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Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018
In this paper the application of the virtual element method (VEM) to the multigroup, neutron diffusion equation will be presented. The VEM is a recently developed Bubnov-Galerkin spatial discretisation method based largely on the mimetic finite ...
J. Ferguson, J. Kópházi, M. D. Eaton
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In this paper the application of the virtual element method (VEM) to the multigroup, neutron diffusion equation will be presented. The VEM is a recently developed Bubnov-Galerkin spatial discretisation method based largely on the mimetic finite ...
J. Ferguson, J. Kópházi, M. D. Eaton
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Fast Sub-Grid Scale Finite Element Method for the First Order Neutron Transport Equation
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018This paper presents a fast sub-grid scale (SGS) finite element method for the first order neutron transport equation. The spherical harmonics method is adopted for the angular discretization.
Chao Fang +3 more
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A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018Deep penetration problems exist widely in reactor applications, such as SPRR300 (Swimming Pool Research Reactor 300), a light water moderated, enriched uranium fueled research reactor in China. Deterministic transport theory is intrinsically suitable for
Wankui Yang +5 more
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Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018
Until recently, interior penalty methods have been applied to elliptic operators using an approach based on the mass matrix of finite elements that possess a constant Jacobian.
S. G. Wilson +3 more
semanticscholar +1 more source
Until recently, interior penalty methods have been applied to elliptic operators using an approach based on the mass matrix of finite elements that possess a constant Jacobian.
S. G. Wilson +3 more
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Isogeometric Multi-Level Iterative Solution Algorithms With Applications in Nuclear Reactor Physics
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018The efficient solution of the neutron diffusion equation for large scale whole core calculations is of paramount importance; especially if the detailed pin-level power distribution and reaction rates are required.
C. Latimer, J. Kópházi, M. D. Eaton
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Preliminary Neutron Simulation of Ceramic Fast Reactor
Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, 2018In this paper, preliminary neutron physical properties of ceramic fast reactor (CFR) are simulated and analyzed. The CFR core consists of ceramic materials, including nuclear fuels, coolants, structural materials, reflective and absorption materials ...
Xue-song Yan +4 more
semanticscholar +1 more source