R-Matrix Analysis of238U High-Resolution Neutron Transmissions and Capture Cross Sections in the Energy Range 0 to 20 keV
Author:
Affiliation:
1. Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831
2. Centre d’Etudes de Cadarache, St. Paul-lez-Durance 13108, France
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE161-131
Reference47 articles.
1. M. G. SOWERBY and M. MOXON, “Summary of the Work of the NEANDC Task Force on U-238,” NEANDC-313U, Nuclear Energy Agency Nuclear Data Center (1994).
2. High energy resolution measurement of the 238U neutron capture yield from 1 to 100 keV
3. N. M. LARSON, “Updated Users’ Guide for SAMMY,” ORNL-9179/R7 (ENDF-364R1), Oak Ridge National Laboratory (2006).
4. Precise Measurement and Analysis of Neutron Transmission Through Uranium-238
5. Measurement and Resonance Analysis of Neutron Transmission Through Uranium-238
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