Verification of the Neutron Flux of a Modified Zero-Power Reactor Using a Neutron Activation Method
Author:
Affiliation:
1. Chung Cheng Institute of Technology, Department of Mechanical Engineering Tahsi, Taoyuan 335, Taiwan
2. TRR-II Project, Institute of Nuclear Energy Research, Division of Nuclear Fuel and Materials Lungtan, Taoyuan 325, Taiwan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE00-A2125
Reference14 articles.
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4. S. C. LIN and P. W. KAO, “WIMSD/I User’s Manual,” INER-T0836, Institute of Nuclear Energy Research (1985).
5. R. M. BOICOURT, R. E. MacFARLANE, and D. W. MUIR, “The NJOY Nuclear Data Processing System,” LA-9393-M, V1, ENDF-324, Los Alamos National Laboratory (1982).
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