Improved nodal expansion method for solving neutron diffusion equation in cylindrical geometry-Reference-Cited by-同舟云学术

Improved nodal expansion method for solving neutron diffusion equation in cylindrical geometry

Published:2010-08 Issue:8 Volume:240 Page:1997-2004
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Wang Dengying,Li Fu,Guo Jiong,Wei Jinfeng,Zhang Jingyu,Hao Chen

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference11 articles.

1. A Three-dimensional Transient Neutronics Routine for the TRAC-PF1 Reactor Thermal Hydraulic Computer Code, Thesis;Bandini,1990

2. Analytic function expansion nodal method for multi-group diffusion equations in cylindrical (r, θ, z) geometry;Cho;Nuclear Science and Engineering,2008

3. A comparison between recent advances in cylindrical nodal diffusion methods;Colameco,2008

4. CYNOD: a neutronics code for pebble bed modular reactor coupled transient analysis;Hiruta,2008

5. A nodal expansion method for the neutron diffusion equation in cylindrical geometry;Komlev,1995

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