Development of Mechanistic Source Term Analysis Tool SAS4A-FATE for Lead- and Sodium-Cooled Fast Reactors-Reference-Cited by-同舟云学术

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Development of Mechanistic Source Term Analysis Tool SAS4A-FATE for Lead- and Sodium-Cooled Fast Reactors

Published:2019-04-29 Issue:2 Volume:206 Page:206-217
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Hua T. Q.¹^ORCID,Lee S. J.²,Liao J.³,Moisseytsev A.¹,Ferroni P.³,Karahan A.¹,Paik C. Y.²,Tentner A. M.¹,Sofu T.¹

Affiliation:

1. Argonne National Laboratory, 9700 South Cass Avenue, Lemont, Illinois 60439

2. Fauske & Associates, LLC, 16W070 83rd Street, Burr Ridge, Illinois 60527

3. Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, Pennsylvania 16066

Funder

U.S. Department of Energy

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2019.1598715

Reference14 articles.

1. Energy sustainability and economic stability with Breed and Burn reactors

2. The closed on-site fuel cycle of the brest reactors

3. A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents

4. The Lead Fast Reactor: An Opportunity for the Future?

5. “The SAS4A/SASSYS-1 Safety Analysis Code System,” ANL/NE-16/19, T. H. FANNING, A. J. BRUNETT, and T. SUMNER, Eds. Argonne National Laboratory, Nuclear Engineering Division (Mar. 31, 2017).

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