The multi-group integro-differential equations of the neutron diffusion kinetics. Solutions with the progressive polynomial approximation in multi-slab geometry

Annals of Nuclear Energy

Volumn 37, Issue 5, 2010, Pages 766-770

  Quintero Leyva, Barbaro ^a  

^a NONE   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

FINITE-DIFFERENCE ALGORITHMS; GROUP MODELS; INITIAL CONDITIONS; MULTI-GROUP; NEUTRON DIFFUSION; NON-ITERATIVE ALGORITHMS; SLAB GEOMETRY;

DIFFUSION; INFORMATION RETRIEVAL; INTEGRODIFFERENTIAL EQUATIONS; NEUTRONS; NUCLEAR PROPULSION; NUCLEAR REACTORS;

POLYNOMIAL APPROXIMATION;

EID: 77950296202     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2010.02.005     Document Type: Article

References (6)

1. Adams, C.H., Stacey Jr., W.M., 1967-RAUMZEIT - a program to solve coupled time-dependent neutron diffusion equations in one space dimension. KAPL-M-6728.
2. Aviles, B.N. et al., 1991. A variable timestep generalized Runge-Kutta method for the numerical integration of the space-time diffusion equations. KAPL-4731.
3. Duderstadt J.J., and Hamilton L.J. Nuclear Reactor Analysis (1976), John Wiley & Sons
4. National Energy Software Center, 1985. Benchmark problem book. ANL-7416-supplement 3.
5. Pollard, J.P., 1977. AUS Diffusion Module POW checkout. 1-and-2-dimensional kinetics calculations. AAEC/387.
6. Quintero-Leyva B. On the numerical solution of the integro-differential equation of the point kinetics of nuclear reactors. Annals of Nuclear Energy 36 (2009) 1280-1284