RMatrix Analysis of the241Pu Neutron Cross Sections in the Thermal to 300-eV Energy Range
Author:
Affiliation:
1. Oak Ridge National Laboratory, Engineering Physics and Mathematics Division P.O. Box 2008, Oak Ridge, Tennessee 37831-6354
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE90-A23767
Reference18 articles.
1. R-Matrix Analysis of the241Pu Cross Sections up to 100 eV
2. High Resolution Measurements of Neutron-Induced Fission Cross Sections for 233U, 235U, 239Pu and 241Pu Below 30 keV
3. Neutron Capture and Fission Cross Sections of Plutonium-241
4. Multilevel Resonance Parameters of Plutonium-241
5. J. A. HARVEY and O. D. SIMPSON, Oak Ridge National Laboratory (1973) (unpublished).
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