On some one-speed neutron transport problems revisited and reformulated-Reference-Cited by-同舟云学术

On some one-speed neutron transport problems revisited and reformulated

Published:2001-05 Issue:8 Volume:28 Page:755-776
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Williams M.M.R.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference23 articles.

1. Evaluation of the neutron flux depression factor via integral transform method;Boffi;Nuclear Science and Engineering,1978

2. Bond, G.R., 1968. The Computational Merits of the Singular Eigenfunction Expansion Method, MSc thesis, Department of Nuclear Engineering, North Carolina State University.

3. Neutron transport in two dissimilar media with anisotrpic scattering;Burkart;Nuclear Science and Engineering,1976

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

5. One-speed neutron transport problems-part II;Carroll;Nuclear Science and Engineering,1973

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