Modeling of the Molten Salt Reactor Experiment with SCALE

Author:

Bostelmann F.1ORCID,Skutnik S. E.1ORCID,Walker E. D.1ORCID,Ilas G.1ORCID,Wieselquist W. A.1ORCID

Affiliation:

1. Oak Ridge National Laboratory, P.O. Box 2008, Building 5700, Oak Ridge, Tennessee 37831-6170

Funder

U.S. Nuclear Regulatory Commission

Publisher

Informa UK Limited

Subject

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

Reference33 articles.

1. R. C. ROBERTSON, “MSRE Design and Operations Report Part I: Description of Reactor Design,” ORNL-TM-0728, Oak Ridge National Laboratory (1965).

2. D. SHEN et al. “Molten-Salt Reactor Experiment (MSRE) Zero-Power First Critical Experiment with U-235,” MSRE-MSR-EXP-001, Organisation for Economic Co-operation and Development, Nuclear Energy Agency (2019).

3. “SCALE Code System, Version 6.2.4,” ORNL/TM-2005/39, W. A. WIESELQUIST, R. A. LEFEBVRE, and M. A. JESSEE, Eds., Oak Ridge National Laboratory (2020); https://www.ornl.gov/file/scale-62-manual/display

4. E. M. SAYLOR et al. “Criticality Safety Validation of SCALE 6.2.2,” ORNL/TM-2018/884, Oak Ridge National Laboratory (2018); https://www.osti.gov/servlets/purl/1479759

5. Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors

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