Measurement of the Neutron Total Cross Section of U233from 0.07 to 10,000 ev
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/NSE63-A17389
Reference7 articles.
1. Breeding Potential of Thermal Reactors
2. Thermal Neutron Cross-Section Measurements of U233, U235, Pu240, U234, and I129with the ORNL Fast Chopper Time-of-Flight Neutron Spectrometer
3. Precision Measurement of the Total Neutron Cross Section ofU233between 0.000818 and 0.0818 ev
4. Slow Neutron Total and Fission Cross Sections ofU233
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1. Progress on the reevaluation and validation of the n+233U neutron cross sections;Annals of Nuclear Energy;2021-12
2. High-Resolution Transmission Measurements of233U Using a Cooled Sample at the TemperatureT= 11 K;Nuclear Science and Engineering;2001-10
3. R-MATRIX ANALYSIS OF NEUTRON EFFECTIVE TOTAL CROSS-SECTION, FISSION CROSS-SECTION AND CAPTURE CROSS-SECTION OF U-233 IN THE ENERGY-RANGE FROM THERMAL TO 150EV;J NUCL SCI TECHNOL;1994
4. 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;Journal of Nuclear Science and Technology;1994-05
5. Nuclear Data Evaluation for U-233;Nuclear Data for Science and Technology;1992
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