New High-Resolution Fission Cross-Section Measurements of233U in the 0.4-eV to 700-keV Energy Range
Author:
Affiliation:
1. Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6354
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE00-A2130
Reference12 articles.
1. see also IAEA-NDS-150 Rev. 99/3, International Atomic Energy Agency (Mar. 1999).
2. Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2
3. R-Matrix Analysis of Neutron Effective Total Cross Section, Fission Cross Section and Capture Cross Section of233U in the Energy Range from Thermal to 150eV
4. Absolute neutron capture yield calibration
5. Measurement of the Neutron Fission and Capture Cross Sections for 233U in the Energy Region 0.4 to 2000 eV
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