Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms-Reference-Cited by-同舟云学术

Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms

Published:2023-06-21 Issue:10 Volume:197 Page:2723-2741
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Gelbard Fred¹^ORCID,Beeny Bradley A.¹,Humphries Larry L.¹,Wagner Kenneth C.¹,Albright Lucas I.¹,Poschmann Max²^ORCID,Piro Markus H. A.²^ORCID

Affiliation:

1. Sandia National Laboratories, 1515 Eubank SE, Albuquerque, New Mexico 87123

2. Ontario Tech University, 2000 Simcoe St. N., Oshawa, Ontario, Canada

Funder

by National Technology & Engineering Solutions of Sandia, LLC

Office of Nuclear Energy

U.S. Nuclear Regulatory Commission

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2022.2161277

Reference57 articles.

1. L. L. HUMPHRIES et al. “MELCOR Computer Code Manuals, Vol. 2: Reference Manual, Version 2.2.18019,” SAND2021-0241 O, Sandia National Laboratories (2021).

2. L. L. HUMPHRIES et al. “MELCOR Computer Code Manuals, Vol. 1: Primer and Users’ Guide, Version 2.2.18019,” SAND2021-0726 O, Sandia National Laboratories (2021).

3. Understanding and Pathways to Avoid Major Fuel Failures and Radionuclide Releases in Fluoride Salt–Cooled High-Temperature Reactor Severe Accidents

4. The chemistry and thermodynamics of molten salt reactor fuels

5. Molten-Salt Reactor Chemistry

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