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Title: Evaluation of Flowing Salt Irradiation Facilities with High Neutron Flux

Abstract

There is significant current interest in the commercial power industry in developing nuclear reactor concepts using molten salt as a coolant or as a fuel-bearing medium and coolant. The Molten Salt Reactor Experiment (MSRE), which was performed at Oak Ridge National Laboratory from 1964-1969, established the feasibility of this reactor design and performed some of the early work in qualifying appropriate structural materials and coolant salts. However, modern versions of this design often incorporate aspects that are beyond the design basis of the MSRE. For example, some designs intend to operate at a higher temperature, use a different structural material, or a different salt altogether. These new designs will eventually require irradiation testing in a variety of reactors and conditions. This document specifically evaluates the possibilities and requirements associated with the most difficult of these conditions: a flowing salt irradiation under high neutron flux.


Citation Formats

McDuffee, Joel Lee, Cetiner, Nesrin Ozgan, Ezell, N. Dianne Bull, Qualls, A. L., and Thoms, Kenneth R. Evaluation of Flowing Salt Irradiation Facilities with High Neutron Flux. United States: N. p., 2018. Web. doi:10.2172/1474548.
McDuffee, Joel Lee, Cetiner, Nesrin Ozgan, Ezell, N. Dianne Bull, Qualls, A. L., & Thoms, Kenneth R. Evaluation of Flowing Salt Irradiation Facilities with High Neutron Flux. United States. doi:10.2172/1474548.
McDuffee, Joel Lee, Cetiner, Nesrin Ozgan, Ezell, N. Dianne Bull, Qualls, A. L., and Thoms, Kenneth R. Wed . "Evaluation of Flowing Salt Irradiation Facilities with High Neutron Flux". United States. doi:10.2172/1474548. https://www.osti.gov/servlets/purl/1474548.
@article{osti_1474548,
title = {Evaluation of Flowing Salt Irradiation Facilities with High Neutron Flux},
author = {McDuffee, Joel Lee and Cetiner, Nesrin Ozgan and Ezell, N. Dianne Bull and Qualls, A. L. and Thoms, Kenneth R.},
abstractNote = {There is significant current interest in the commercial power industry in developing nuclear reactor concepts using molten salt as a coolant or as a fuel-bearing medium and coolant. The Molten Salt Reactor Experiment (MSRE), which was performed at Oak Ridge National Laboratory from 1964-1969, established the feasibility of this reactor design and performed some of the early work in qualifying appropriate structural materials and coolant salts. However, modern versions of this design often incorporate aspects that are beyond the design basis of the MSRE. For example, some designs intend to operate at a higher temperature, use a different structural material, or a different salt altogether. These new designs will eventually require irradiation testing in a variety of reactors and conditions. This document specifically evaluates the possibilities and requirements associated with the most difficult of these conditions: a flowing salt irradiation under high neutron flux.},
doi = {10.2172/1474548},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {8}
}

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