Analytical Representation of Some Fast-Neutron Cross Sections Useful in Dosimetry
Author:
Affiliation:
1. Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE75-A26794
Cited by 16 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. Computation of cross sections and dose conversion factors for criticality accident dosimetry;Radiation Protection Dosimetry;2004-08-01
2. Neutron Cross Sections for the 93Nb(n, n')93mNb and 199Hg(n, n')199mHg Reactions Compiled in JENDL Dosimetry File.;Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan;1997
3. Nuclear data sheets update for A = 108;Nuclear Data Sheets;1991-01
4. Measurement of the fission cross-section ratio for237Np/235U around 14 MeV neutron energies;Acta Physica Hungarica;1989-06
5. Head phantom experiment and calculation for boron neutron capture therapy;Physics in Medicine and Biology;1988-06-01
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