Single-Level Analysis of the Uranium-233 Fission Cross Section for Neutron Energies Between 6 and 124 eV
Author:
Affiliation:
1. Service d'Etudes de Réacteurs et de Mathématiques Appliqués Centre d'Etudes Nucléaires de Saclay, BP N°2, 91190 Gif-sur-Yvette, France
2. Département de Physique Nucléaire Centre d'Etudes Nucléaires de Saclay, BP N°2, 91190 Gif-sur-Yvette, France
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE74-A23400
Cited by 10 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Neutron Resonance Parameters for U-233 (Uranium);Supplement to Volume I/24;2015
2. High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to1MeV neutron energy;Physical Review C;2009-10-08
3. Neutron Resonance Parameters for U-233 (Uranium);Neutron Resonance Parameters;2009
4. 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
5. 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
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