Thermal Neutron Cross-Section Measurements of U233, U235, Pu240, U234, and I129with the ORNL Fast Chopper Time-of-Flight Neutron Spectrometer
Author:
Affiliation:
1. Oak Ridge National Laboratory, Oak Ridge, Tennessee
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE60-A25786
Reference15 articles.
1. Thermal Neutron Absorption Cross Sections of Boron and Gold
2. Neutron Scattering Cross Section ofU233
3. Total Neutron Cross Sections of U233 and U235 from 0.02 to 0.08 ev
4. BNL 325, 2nd ed. Brookhaven National Laboratory (1958).
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