Assessment of neutron kerma coefficients and its calculation methodologies using recent basic ENDF-6 libraries-Reference-Cited by-同舟云学术

Assessment of neutron kerma coefficients and its calculation methodologies using recent basic ENDF-6 libraries

Published:2020-04 Issue: Volume:360 Page:110519
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Saha Uttiyoarnab,Devan K.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference46 articles.

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4. A consistent set of neutron kerma coefficients from thermal to 150 MeV for biologically important materials;Chadwick;Med. Phys.,1999

5. ENDF/B-VII.1 Nuclear data for science and technology: cross sections, covariances, fission product yields and decay data;Chadwick;Nucl. Data Sheets,2011

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