Time–eigenvalue calculations in multi-region Cartesian geometry using Green’s functions

Author:

Kornreich Drew E.,Parsons D. Kent

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Alcouffe, R.E., Baker, R.S., Brinkley, F.W., Marr, D.R., Dell, R.D., Walters, W.F., 1995. DANTSYS: A diffusion accelerated neutral particle transport code system. Los Alamos National Laboratory, LA-12969-M

2. Alcouffe, R.E., Baker, R.S., Dahl, J.A., Turner, S.A., 2000. PARTISN code abstract, Physor 2000 International Topical Meeting: advances in reactor physics and mathematics and computation into the next millennium, Pittsburgh, PA

3. Briesmeister, J.F. (Ed.), 1995. MCNP – a general Monte Carlo code for neutron and photon transport, version 4B, LA-7396-M, Rev. 2. Los Alamos National Laboratory

4. Mononenergetic critical parameters and decay constants for small homogeneous spheres and thin homogeneous slabs;Carlvik;Nuclear Science and Engineering,1968

5. Introduction to the theory of neutron diffusion;Case,1953

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