Solution of 3D multigroup, linearly anisotropic scattering, criticality problems by the AN boundary-element response-matrix method

Author:

Giusti V.,Montagnini B.,Ravetto P.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference36 articles.

1. Development and verification of a nodal approach for solving the multigroup SP3 equations;Beckert;Annals of Nuclear Energy,2008

2. Nuclear Reactor Theory;Bell,1970

3. The simplified P3 approximation;Brantley;Nuclear Science and Engineering,2000

4. Brown, F., Barnett, N., 2006. A Tutorial on using MCNP for 1-Group Transport Calculations. LA-UR-07-4594. Los Alamos National Laboratory.

5. Simplified PN and AN methods in neutron transport;Ciolini;Progress in Nuclear Energy,2002

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