Measurements of Neutron and Gamma-Ray Streaming in a Cavity-Duct System and an Analysis by an Albedo Monte Carlo Method
Author:
Affiliation:
1. Kyoto University, Department of Nuclear Engineering Yoshida-Honmachi, Sakyo-ku, Kyoto 606, Japan
2. The University of Tokyo, Nuclear Engineering Research Laboratory The Faculty of Engineering, Tokai-mura, lbaraki, 319-11, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE82-A20083
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1. Fast neutron shielding and neutron transport studies at YAYOI;Progress in Nuclear Energy;1998-01
2. Radiation Streaming Analysis in the Radial and Tangential Beam Tubes of a TRIGA Research Reactor Using MCNP and Comparison with Measurement;Nuclear Science and Engineering;1995-10
3. Thermalization of Accelerator-produced Neutrons in a Concrete Room;Health Physics;1991-02
4. Development of Radiation Transport Codes for Shielding Analysis;Journal of Nuclear Science and Technology;1989-01
5. Measurements of Backscattered Neutrons and Secondary Gamma-Rays from Stainless Steel and Limestone Concrete for 14-MeV Source Neutrons;Journal of Nuclear Science and Technology;1988-04
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