International Evaluation of Neutron Cross Section Standards-Reference-Cited by-同舟云学术

International Evaluation of Neutron Cross Section Standards

Published:2009-12 Issue:12 Volume:110 Page:3215-3324
ISSN:0090-3752
Container-title:Nuclear Data Sheets
language:en
Short-container-title:Nuclear Data Sheets

Author:

Carlson A.D.,Pronyaev V.G.,Smith D.L.,Larson N.M.,Chen Zhenpeng,Hale G.M.,Hambsch F.-J.,Gai E.V.,Oh Soo-Youl,Badikov S.A.,Kawano T.,Hofmann H.M.,Vonach H.,Tagesen S.

Publisher

Elsevier BV

Subject

Nuclear and High Energy Physics

Reference146 articles.

1. ENDF/B-VII. 0: Next Generation Nuclear Data Library for Nuclear Science and Technology;Chadwick;Nucl. Data Sheets,2006

2. A.D. Carlson, “The ENDF/B Standards, “Proc. 35thAnniversary Symposium of the Cross Section Evaluation Working Group, Brookhaven National Laboratory Report BNL-52675, November 2001

3. M.K. Drake., “ENDF/B-III Cross Section Measurement Standards,” Brookhaven National Laboratory Report BNL-17188, July 1972

4. B.A. Magurno, “ENDF/B-IV Dosimetry File,” Brookhaven National Laboratory Report BNL-NCS-50446, April 1975

5. A.D. Carlson, and M.R. Bhat. “ENDF/B-V Cross Section Measurement Standards,” Brookhaven National Laboratory Report BNL-NCS-51619, October 1982

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