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Title: U.S. Sodium Fast Reactor Codes and Methods: Current Capabilities and Path Forward

Abstract

The United States has extensive experience with the design, construction, and operation of sodium cooled fast reactors (SFRs) over the last six decades. Despite the closure of various facilities, the U.S. continues to dedicate research and development (R&D) efforts to the design of innovative experimental, prototype, and commercial facilities. Accordingly, in support of the rich operating history and ongoing design efforts, the U.S. has been developing and maintaining a series of tools with capabilities that envelope all facets of SFR design and safety analyses. This paper provides an overview of the current U.S. SFR analysis toolset, including codes such as SAS4A/SASSYS-1, MC2-3, SE2-ANL, PERSENT, NUBOW-3D, and LIFE-METAL, as well as the higher-fidelity tools (e.g. PROTEUS) being integrated into the toolset. Current capabilities of the codes are described and key ongoing development efforts are highlighted for some codes.

Authors:
;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy
OSTI Identifier:
1393835
DOE Contract Number:
AC02-06CH11357
Resource Type:
Conference
Resource Relation:
Conference: 2017 International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17), 06/26/17 - 06/29/17, Yekaterinburg, RU
Country of Publication:
United States
Language:
English
Subject:
safety codes; severe accident modeling

Citation Formats

Brunett, A. J., and Fanning, T. H. U.S. Sodium Fast Reactor Codes and Methods: Current Capabilities and Path Forward. United States: N. p., 2017. Web.
Brunett, A. J., & Fanning, T. H. U.S. Sodium Fast Reactor Codes and Methods: Current Capabilities and Path Forward. United States.
Brunett, A. J., and Fanning, T. H. Mon . "U.S. Sodium Fast Reactor Codes and Methods: Current Capabilities and Path Forward". United States. doi:. https://www.osti.gov/servlets/purl/1393835.
@article{osti_1393835,
title = {U.S. Sodium Fast Reactor Codes and Methods: Current Capabilities and Path Forward},
author = {Brunett, A. J. and Fanning, T. H.},
abstractNote = {The United States has extensive experience with the design, construction, and operation of sodium cooled fast reactors (SFRs) over the last six decades. Despite the closure of various facilities, the U.S. continues to dedicate research and development (R&D) efforts to the design of innovative experimental, prototype, and commercial facilities. Accordingly, in support of the rich operating history and ongoing design efforts, the U.S. has been developing and maintaining a series of tools with capabilities that envelope all facets of SFR design and safety analyses. This paper provides an overview of the current U.S. SFR analysis toolset, including codes such as SAS4A/SASSYS-1, MC2-3, SE2-ANL, PERSENT, NUBOW-3D, and LIFE-METAL, as well as the higher-fidelity tools (e.g. PROTEUS) being integrated into the toolset. Current capabilities of the codes are described and key ongoing development efforts are highlighted for some codes.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jun 26 00:00:00 EDT 2017},
month = {Mon Jun 26 00:00:00 EDT 2017}
}

Conference:
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