Measurement of Absolute Fission Yields in the Fast Neutron–Induced Fission of Actinides:238U,237Np,238Pu,240Pu,243Am, and244Cm by Track-Etch-cum-Gamma Spectrometry
Author:
Affiliation:
1. Bhaha Atomic Research Centre, Radiochemistry Division, Trombay, Mumbai - 400 085, India
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE00-A2136
Reference51 articles.
1. INTRODUCTION TO NEUTRON PHYSICS OF THERMAL CROSS SECTIONS AND RESONANCE PARAMETERS
2. B. F. RIDER, “Compilation of Fission Products Yields,” NEDO, 12154 3c ENDF-327, Vallecitos Nuclear Centre (1981).
3. Nuclear-charge distribution and delayed-neutron yields for thermal-neutron-induced fission of 235U, 233U, and 239Pu and for spontaneous fission of 252Cf
4. Mass distribution in the reactor neutron fission of 231Pa and 237Np
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