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Title: A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor

Abstract

A mechanistic source term (MST) calculation attempts to realistically assess the transport and release of radionuclides from a reactor system to the environment during a specific accident sequence. The U.S. Nuclear Regulatory Commission (NRC) has repeatedly stated its expectation that advanced reactor vendors will utilize an MST during the U.S. reactor licensing process. As part of a project to examine possible impediments to sodium fast reactor (SFR) licensing in the U.S., an analysis was conducted regarding the current capabilities to perform an MST for a metal fuel SFR. The purpose of the project was to identify and prioritize any gaps in current computational tools, and the associated database, for the accurate assessment of an MST. The results of the study demonstrate that an SFR MST is possible with current tools and data, but several gaps exist that may lead to possibly unacceptable levels of uncertainty, depending on the goals of the MST analysis.

Authors:
; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy
OSTI Identifier:
1365801
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

Citation Formats

Grabaskas, David, Bucknor, Matthew, and Jerden, James. A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor. United States: N. p., 2017. Web.
Grabaskas, David, Bucknor, Matthew, & Jerden, James. A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor. United States.
Grabaskas, David, Bucknor, Matthew, and Jerden, James. Mon . "A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor". United States. doi:. https://www.osti.gov/servlets/purl/1365801.
@article{osti_1365801,
title = {A Mechanistic Source Term Calculation for a Metal Fuel Sodium Fast Reactor},
author = {Grabaskas, David and Bucknor, Matthew and Jerden, James},
abstractNote = {A mechanistic source term (MST) calculation attempts to realistically assess the transport and release of radionuclides from a reactor system to the environment during a specific accident sequence. The U.S. Nuclear Regulatory Commission (NRC) has repeatedly stated its expectation that advanced reactor vendors will utilize an MST during the U.S. reactor licensing process. As part of a project to examine possible impediments to sodium fast reactor (SFR) licensing in the U.S., an analysis was conducted regarding the current capabilities to perform an MST for a metal fuel SFR. The purpose of the project was to identify and prioritize any gaps in current computational tools, and the associated database, for the accurate assessment of an MST. The results of the study demonstrate that an SFR MST is possible with current tools and data, but several gaps exist that may lead to possibly unacceptable levels of uncertainty, depending on the goals of the MST analysis.},
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:
Other availability
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