Calculation and Evaluation of Cross Sections and Kerma Factors for Neutrons up to 100 MeV on Carbon-Reference-Cited by-同舟云学术

Calculation and Evaluation of Cross Sections and Kerma Factors for Neutrons up to 100 MeV on Carbon

Published:1996-05 Issue:1 Volume:123 Page:17-37
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Chadwick M. B.¹,Cox L. J.¹,Young P. G.²,Meigooni A.S.³

Affiliation:

1. University of California, Nuclear Data Group, Lawrence Livermore National Laboratory Livermore, California 94550

2. University of California, Theoretical Division, Los Alamos National Laboratory Los Alamos, New Mexico 87545

3. University of Kentucky, Department of Radiation Medicine, Lexington, Kentucky 40536

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE96-A24210

Reference70 articles.

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4. R. J. HOWERTON, UCRL-50400, 27, Rev., Lawrence Livermore National Laboratory (1986).

5. C. Y. FU, E. J. AXTON, and F. G. PEREY, “Description of Evaluation for Natural Carbon Performed for ENDF/B-VI,” Oak Ridge National Laboratory (1989);

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