Results 11 to 20 of about 4,725 (242)
Conditions for translation and scaling invariance of the neutron diffusion equation [PDF]
24 pages, 1 table, Accepted in Progress in Nuclear Energy ...
Jesse F. Giron +2 more
openaire +2 more sources
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
doaj +1 more source
Wavelet-Based Algorithms for Solving Neutron Diffusion Equations. [PDF]
This work develops efficient algorithms for numerically solving the neutron diffusion equation by a wavelet Galerkin method (WGM). One of the main problems encountered in solving neutron diffusion equation using WGM is the treatment of the boundary and interface conditions.
Hesham NASIF +4 more
openaire +1 more source
Solving the discretised neutron diffusion equations using neural networks
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
openaire +3 more sources
Iterative schemes for the neutron diffusion equation
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
openaire +1 more source
Adaptive time-step control for modal methods to integrate the neutron diffusion equation
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
doaj +1 more source
Development and Verification of Hexagonal Quasi-diffusion Code Based on Variational Nodal Method
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
doaj
The solution of two-dimensional neutron diffusion equation with delayed neutrons
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
openaire +2 more sources
Spatial modes for the neutron diffusion equation and their computation [PDF]
[EN] Different spatial modes can be defined for the neutron diffusion equation such as the k; a and c-modes. These modes have been successfully used for the analysis of nuclear reactor characteristics. In this work, these modes are studied using a high order finite element method to discretize the equations and also different methods to solve the ...
Carreño, A.|||0000-0003-2302-1157 +3 more
openaire +3 more sources
Schwarz type preconditioners for the neutron diffusion equation
[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
openaire +4 more sources

