Results 21 to 30 of about 5,356 (294)
Conditions for translation and scaling invariance of the neutron diffusion equation [PDF]
Progress in Nuclear Energy, 2019 24 pages, 1 table, Accepted in Progress in Nuclear Energy ...
Jesse F. Giron +2 more
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Brazilian Journal of Radiation Sciences, 2021 This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B code. The cell calculation procedure allows determining the nuclear parameters present in the multi-group neutron diffusion equation and for this purpose
Desirée Yael de Sena Tavares +2 more
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A ROBUST SECOND-ORDER MULTIPLE BALANCE METHOD FOR TIME-DEPENDENT NEUTRON TRANSPORT SIMULATIONS [PDF]
EPJ Web of Conferences, 2021 A second-order “Time-Dependent Multiple Balance” (TDMB) method for solving neutron transport problems is introduced and investigated. TDMB consists of solving two coupled equations: (i) the original balance equation (the transport equation integrated ...
Variansyah Ilham +2 more
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Solving the discretised neutron diffusion equations using neural networks
International Journal for Numerical Methods in Engineering, 2023 AbstractThis paper presents a new approach which uses the tools within artificial intelligence (AI) software libraries as an alternative way of solving partial differential equations (PDEs) that have been discretised using standard numerical methods. In particular, we describe how to represent numerical discretisations arising from the finite volume ...
Toby R.F. Phillips +4 more
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Iterative schemes for the neutron diffusion equation
Computers & Mathematics with Applications, 2002 The paper is concerned with the need to provide fast reliable numerical schemes for the solution of neutron diffusion equations arising in the nuclear industry. It is clear that for safety and monitoring purposes there is a need for rapid solution of these equations.
Bru, R. +5 more
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Adaptive time-step control for modal methods to integrate the neutron diffusion equation
Nuclear Engineering and Technology, 2021 The solution of the time-dependent neutron diffusion equation can be approximated using quasi-static methods that factorise the neutronic flux as the product of a time dependent function times a shape function that depends both on space and time.
A. Carreño +3 more
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The solution of two-dimensional neutron diffusion equation with delayed neutrons
Informatica, 2001 Summary: The distribution of the neutron population in a nuclear reactor is described by using transport equations. One of the possible approximations of the neutron transport equation is given by the neutron diffusion equation. The paper presents a numerical solution method for the one group neutron diffusion equation with one group of delayed ...
Sapagovas, Mifodijus +1 more
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Development and Verification of Hexagonal Quasi-diffusion Code Based on Variational Nodal Method
Yuanzineng kexue jishu, 2023 New type reactors usually adopt advanced fuel types and more anisotropic fuel arrangements, the neutron spectrum is very different from that of pressurized water reactor, and the neutron anisotropy is stronger.
ZHUANG Kun;WANG Lianjie;LIU Kun;YAN Jiangtao;SHANG Wen
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Schwarz type preconditioners for the neutron diffusion equation
Journal of Computational and Applied Mathematics, 2017 [EN] Domain decomposition is a mature methodology that has been used to accelerate the convergence of partial differential equations. Even if it was devised as a solver by itself, it is usually employed together with Krylov iterative methods improving its rate of convergence, and providing scalability with respect to the size of the problem.
Antoni Vidal-Ferràndiz +4 more
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Pin-by-pin Calculation of Reactor Core-Based on Quasi-diffusion in Rectangular Grid
Yuanzineng kexue jishu, 2023 Physical calculations of reactor cores are fundamental for reactor core design and nuclear safety analysis. The second generation of core calculation theory and methods based on advanced component homogenization theory and modern coarse grid block ...
YAN Jiangtao;LIU Kun;ZHUANG Kun;WANG Senshan;ZHANG Kaihui;ZHANG Xinxin
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