A Comprehensive Approach to Molten Salt Reactor Source Term Generation and Shielding Analyses
Author:
Affiliation:
1. Georgia Institute of Technology, 770 State Street NW, Atlanta, Georgia 303320405
2. United States Military Academy, 606 Thayer Road, West Point, New York 10996
Funder
NEXTRA
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295450.2023.2229181
Reference25 articles.
1. R. D. MOSTELLER, “Bibliography of MCNP Verification & Validation: 1990-2003,” LA-UR-03-9032, Los Alamos National Laboratory (2003).
2. E. M. SAYLOR et al. “Criticality Safety Validation of SCALE 6.2.2,” ORNL/TM-2018/884, Oak Ridge National Laboratory (Oct. 2018).
3. Modeling of the Molten Salt Reactor Experiment with SCALE
4. The Serpent Monte Carlo code: Status, development and applications in 2013
5. SCALE Code System
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