A Comprehensive Approach to Molten Salt Reactor Source Term Generation and Shielding Analyses

Author:

Carberry Kyle12,Petrovic Bojan1ORCID

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

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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