Title: Review of molten salt reactor off-gas management considerations

Abstract

Molten salt reactors offer a wide range of potential benefits but pose some unique challenges, particularly for designs that use an unclad liquid salt fuel. This type of fuel will result in the transport of fission gases into the headspace of the reactor where in some designs a cover gas can be circulated to remove certain fission products and maintain an inert atmosphere. The cover gas leaving the reactor core is expected to contain both noble and non-noble gases, aerosols, volatile species, tritium, radionuclides, and their daughters. To remove these radioactive gases, it is necessary to develop a robust off-gas system for molten salt–fueled reactors. Various treatment systems must be staged in series to remove the off-gas constituents from the stream before recirculating the gas back to the headspace of the reactor. Treatment options vary greatly depending on what they are designed to remove from the gas stream. This paper reviews the anticipated composition of a typical molten salt reactor off-gas stream and subsequently the available resources that could be employed to remove these species from the gas stream. An example off-gas system is then detailed, along with important design considerations, exemplifying the necessity for high-fidelity modeling. Lastly, the needmore » for further thermophysical property research and the employment of advanced sensor technology for treatment component testing are discussed.« less

Authors:

Andrews, Hunter B.  ^[1];

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• Search DOE PAGES for ORCID "0000-0002-2091-9415"

McFarlane, Joanna  ^[1];

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• Search DOE PAGES for ORCID "0000-0002-4112-5104"

Chapel, A. Shay ^[1]; Ezell, N. Dianne Bull  ^[1];

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• Search DOE PAGES for ORCID "0000-0001-9334-5822"

Holcomb, David Eugene  ^[1];

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• Search DOE PAGES for ORCID "0000-0001-8263-4661"

de Wet, Dane  ^[1];

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• Search DOE PAGES for ORCID "0000-0002-8697-306X"

Greenwood, Michael S.  ^[1];

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• Search DOE PAGES for ORCID "0000-0003-3348-0736"

Myhre, Kristian G.  ^[1];

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• Search DOE PAGES for ORCID "0000-0002-5947-5743"

Bryan, Samuel A. ^[2]; Lines, Amanda ^[2]; Riley, Brian J.  ^[2];

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• Search DOE PAGES for ORCID "0000-0002-7745-6730"

Felmy, Heather M. ^[2]; Humrickhouse, Paul W. ^[3]

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+ Show Author Affiliations

1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
3. Idaho National Lab. (INL), Idaho Falls, ID (United States)

Publication Date:

Fri Oct 29 00:00:00 EDT 2021

Research Org.:

Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Sponsoring Org.:

USDOE Office of Nuclear Energy (NE)

OSTI Identifier:

1831663

Alternate Identifier(s):

OSTI ID: 1828223; OSTI ID: 1839945

Report Number(s):

PNNL-SA-161213
Journal ID: ISSN 0029-5493; TRN: US2216613

Grant/Contract Number:  

AC05-00OR22725; AC05-76RL01830; AC07-05ID14517

Resource Type:

Accepted Manuscript

Journal Name:

Nuclear Engineering and Design

Additional Journal Information:

Journal Volume: 385; Journal ID: ISSN 0029-5493

Publisher:

Elsevier

Country of Publication:

United States

Language:

English

Subject:

22 GENERAL STUDIES OF NUCLEAR REACTORS; Molten salt reactor; off-gas/cover gas; radionuclide capture; spectroscopic monitoring; source term reduction; online sensing