Separation of Flux/Dose Contributions from Multiple Transport Pathways in Monte Carlo Shielding Analyses of a Consolidated Interim Spent Nuclear Fuel Storage Facility-Reference-Cited by-同舟云学术

Separation of Flux/Dose Contributions from Multiple Transport Pathways in Monte Carlo Shielding Analyses of a Consolidated Interim Spent Nuclear Fuel Storage Facility

Published:2021-08-31 Issue: Volume: Page:1-12
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Lai P. C.¹,Sheu R. J.¹²^ORCID

Affiliation:

1. National Tsing Hua University, Institute of Nuclear Engineering and Science, Hsinchu 300, Taiwan, R.O.C.

2. National Tsing Hua University, Department of Engineering and System Science, Hsinchu 300, Taiwan, R.O.C.

Funder

Fuel Cycle and Materials Administration of Atomic Energy Council in Taiwan

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2021.1938486

Reference19 articles.

1. “Spent Fuel Storage Status,” Atomic Energy Council (Oct. 31, 2020); https://www.aec.gov.tw/english/Radioactive-Waste-Management/Spent-Fuel-Management-148.html (accessed Nov. 29, 2020).

2. “Safety Analysis Report for the Independent Spent Fuel Storage Installation in Chinshan Nuclear Power Plant,” Taiwan Power Company (2012); in Chinese.

3. TAIWAN POWER COMPANY, “Decommissioning Plan for Chinshan Nuclear Power Plant,” Taiwan Power Company (2015); in Chinese.

4. TAIWAN POWER COMPANY, “Environmental Impact Assessment for Chinshan Nuclear Power Plant Decommissioning Plan,” Taiwan Power Company (2019); in Chinese.

5. “MCNP User’s Manual—Code Version 6.2,” C. J. WERNER Ed., LA-UR-17-29981, Los Alamos National Laboratory (2017).

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