Dose Rate Measurements and Calculation of TN-12/2 Packages

Author:

Taniuchi Hiroaki1,Matsuda Fumio2

Affiliation:

1. Kobe Steel Ltd. 2-3-1 Shinhama, Arai-cho, Takasago, 676-8670 Japan

2. Transnuclear Ltd. 5-9-12 Kitashinagawa, Shinagawa-ku, Tokyo, 141-8688 Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference6 articles.

1. “MCNP—A General Monte Carlo N-Particle Transport Code, Version 4A,” LA-12625, J. F. BRIESMEISTER, Ed. Los Alamos National Laboratory (1993).

2. A. G. CROFF, “A User’s Manual for the ORIGEN2 Computer Code,” ORNL/TM-7175, Oak Ridge National Laboratory (1980).

3. S. B. LUDWIG and J. P. RENIER, “Standard- and Extended-Burnup PWR and BWR Reactor Models for the ORI-GEN2 Computer Code,” ORNL/TM-11018, Oak Ridge National Laboratory (1989).

4. Technique to Calculate Surface Dose-Rate Profiles by Monte Carlo Method.

5. “Neutron and Gamma-Ray Flux-to-Dose-Rate Factors,” ANSI/ANS-6.1.1-1977, American Nuclear Society (1977).

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