Preliminary design evaluation of a natural circulation molten salt irradiation loop

Sandesh Bhaskar; Abdalla Abou-Jaoude

doi:10.13182/T30882

Preliminary design evaluation of a natural circulation molten salt irradiation loop

Sandesh Bhaskar
, Abdalla Abou-Jaoude

Research output: Contribution to journal › Conference article › peer-review

3 Scopus citations

Abstract

Many promising Molten Salt Reactor (MSR) concepts under development rely on relatively untested salt compositions. Irradiation data will likely be necessary for the licensing of these concepts. A feasibility study is currently underway at Idaho National Laboratory to establish the possibility of hosting a compact molten salt irradiation loop inside the Advanced Test Reactor (ATR). A case study for a uranium-fueled chloride-based salt is examined in this paper. Thermal hydraulic simulations are conducted using the system code, SAM, to scope the achievable natural circulating velocities and inform design decisions.

Original language	English
Pages (from-to)	1895-1896
Number of pages	2
Journal	Transactions of the American Nuclear Society
Volume	121
Early online date	Nov 2019
DOIs	https://doi.org/10.13182/T30882
State	Published - Nov 2019
Event	2019 Transactions of the American Nuclear Society, ANS 2019 - Washington, United States Duration: Nov 17 2019 → Nov 21 2019

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title = "Preliminary design evaluation of a natural circulation molten salt irradiation loop",

abstract = "Many promising Molten Salt Reactor (MSR) concepts under development rely on relatively untested salt compositions. Irradiation data will likely be necessary for the licensing of these concepts. A feasibility study is currently underway at Idaho National Laboratory to establish the possibility of hosting a compact molten salt irradiation loop inside the Advanced Test Reactor (ATR). A case study for a uranium-fueled chloride-based salt is examined in this paper. Thermal hydraulic simulations are conducted using the system code, SAM, to scope the achievable natural circulating velocities and inform design decisions.",

author = "Sandesh Bhaskar and Abdalla Abou-Jaoude",

note = "Funding Information: The work is supported through the INL Laboratory Directed Research \& Development (LDRD) Program under DOE Idaho Operations Office Contract DE-AC07-05ID14517. Publisher Copyright: {\textcopyright} 2019 American Nuclear Society. All rights reserved.; 2019 Transactions of the American Nuclear Society, ANS 2019 ; Conference date: 17-11-2019 Through 21-11-2019",

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AU - Bhaskar, Sandesh

AU - Abou-Jaoude, Abdalla

N1 - Funding Information: The work is supported through the INL Laboratory Directed Research & Development (LDRD) Program under DOE Idaho Operations Office Contract DE-AC07-05ID14517. Publisher Copyright: © 2019 American Nuclear Society. All rights reserved.

PY - 2019/11

Y1 - 2019/11

N2 - Many promising Molten Salt Reactor (MSR) concepts under development rely on relatively untested salt compositions. Irradiation data will likely be necessary for the licensing of these concepts. A feasibility study is currently underway at Idaho National Laboratory to establish the possibility of hosting a compact molten salt irradiation loop inside the Advanced Test Reactor (ATR). A case study for a uranium-fueled chloride-based salt is examined in this paper. Thermal hydraulic simulations are conducted using the system code, SAM, to scope the achievable natural circulating velocities and inform design decisions.

AB - Many promising Molten Salt Reactor (MSR) concepts under development rely on relatively untested salt compositions. Irradiation data will likely be necessary for the licensing of these concepts. A feasibility study is currently underway at Idaho National Laboratory to establish the possibility of hosting a compact molten salt irradiation loop inside the Advanced Test Reactor (ATR). A case study for a uranium-fueled chloride-based salt is examined in this paper. Thermal hydraulic simulations are conducted using the system code, SAM, to scope the achievable natural circulating velocities and inform design decisions.

UR - https://www.scopus.com/pages/publications/85092151899

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DO - 10.13182/T30882

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JF - Transactions of the American Nuclear Society

T2 - 2019 Transactions of the American Nuclear Society, ANS 2019

Y2 - 17 November 2019 through 21 November 2019

ER -

Preliminary design evaluation of a natural circulation molten salt irradiation loop

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