Neutron-Induced Fission Cross Section of243Am in the Energy Range from 1 eV to 10 MeV
Author:
Affiliation:
1. Commission of the European Communities, Joint Research Centre, Geel Establishment, Central Bureau for Nuclear Measurements, B-2440 Geel, Belgium
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE88-A23540
Reference24 articles.
1. K. W. ZERREßEN, “Berücksichtigung ungenauer Nuclearer Daten bei der Berechnung der Reduktion von Abfallactiniden durch Bestrahlung,” PhD Thesis, Fakultät für Elektrotechnik, Rheinisch-Westfälische Technische Hochschule, Aachen, FRG (1981).
2. Y. KIKUCHI, “Evaluation of Neutron Nuclear Data for241Am and242Am,” JAERI-M 82-096 (1982) and NEANDC(J)-86/U (1982), Japan Atomic Energy Research Institute.
3. The thermal neutron induced fission cross-section of 243Am
4. Neutron Capture and Fission Cross Section of 243Am in the Energy Range from 5 to 250 keV
5. Measurement of the Neutron-Induced Fission Cross Sections of Americium-241 and Americium-243 Relative to Uranium-235 from 0.2 to 30 MeV
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5. 243Am neutron-induced fission cross section in the fast neutron energy range;Physical Review C;2012-04-19
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