Normalization and Minimum Values of the239Pu Fission Cross Section
Author:
Affiliation:
1. Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6354
2. Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, lbaraki-ken, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE93-A28526
Reference11 articles.
1. Subthreshold Fission Cross Section of240Pu and the Fission Cross Sections of235U and239Pu
2. High-Resolution Fission Cross-Section Measurements of235U and239Pu
3. RMatrix Analysis of239Pu Neutron Cross Sections in the Energy Range up to 1000 eV
4. P. G. YOUNG, L. W. WESTON, and W. P. POENITZ, “ENDF/B-VI Data File for239Pu(Mat 9437),” ENDF-201, Brookhaven National Laboratorys.
5. R. Q. WRIGHT, Oak Ridge National Laboratory, Private Communication (1991).
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