Uncertainty Analysis of a Numerical Model for Calculating an Effective Source Height

Author:

ONO Hiroki1,SADA Koichi2

Affiliation:

1. Nuclear Risk Research Center, Central Research Institute of Electric Power Industry

2. Central Research Institute of Electric Power Industry

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference16 articles.

1. 1) Nuclear Safety Commission, Genshiryokuanzeniinkaishishinsyu, Taisei-Shuppan Co., Ltd., Tokyo, 374-403, ISBN 978-4-802-82967-0 (2011), [in Japanese].

2. 2) Atomic Energy Society of Japan, Code for Wind Tunnel Experiments to Calculate the Effective Height of Emitting Source for Nuclear Power Facilities Safety Analysis : 2019, Atomic Energy Society of Japan, Tokyo, ISBN 978-4-89047-426-4 (2020), [in Japanese].

3. 3) Atomic Energy Society of Japan, Code for Numerical Model to Calculate the Effective Source Height for Nuclear Power Facilities Safety Analysis : 2011, Atomic Energy Society of Japan, Tokyo, ISBN 978-4-89047-360-1 (2011), [in Japanese].

4. 4) K. Sada, S. Komiyama, T. Michioka, Y. Ichikawa, “Numerical model for atmospheric diffusion analysis and evaluation of effective dose for safety analysis,” Trans. At. Energy Soc. Jpn., 8[2], 184–196 (2009), [in Japanese].

5. 5) D. J. Thomson, “Criteria for the selection of stochastic models of particle trajectories in the turbulent flows,” J. Fluid Mech., 180, 529–556 (1987).

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