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Comparison of U3Si2 and U-10Mo LEU-Fueled Reactor Cores for the Preconceptual NIST Neutron Source Design

Published

Author(s)

Osman Celikten, Abdullah Weiss, Dagistan Sahin

Abstract

The National Institute of Standards and Technology (NIST) Center for Neutron Research (NCNR) is one of the primary U.S. national research facilities that hosts thousands of visiting domestic and international scientists/researchers for various research projects. The National Bureau of Standards Reactor (NBSR) has been operational more than 50 years, but due to increasing outage times and costly maintenance, a new replacement reactor, namely the NIST Neutron Source (NNS), is being planned by the NCNR to replace the aging NBSR. The preliminary conceptual design of the NNS core was based on Material Test Reactor (MTR) plate type U-10Mo fuel; however, due to recent difficulties and unknown timeline for the certification of U-10Mo fuel in the U.S., NCNR is investigating the possibility of using low-enriched uranium silicide dispersion (U3Si2/Al) as alternative fuel material. In this paper, the neutronics performance of low-enriched U3Si2/Al fuel and U-10Mo fuel are compared with the objective of identifying the dimensions of U3Si2/Al fuel plates that can yield similar neutronics behavior to the current U-10Mo fuel plates without modifying overall assembly size. Hence, the main objective of the NNS is to provide neutrons for the two cold sources located around the core, and the current compact core design delivers more neutron intensity and brightness for the cold neutron sources. Neutron transport analyses follow an optimization process for minimizing the difference between the ∞ of the silicide plates to the U-10Mo, maximizing the coolant channel thickness and 235U content inside the assembly. Results show correlations between the fuel-to-coolant area ratio and the reactivity worth characteristics of the U-10Mo and U3Si2/Al plates in the NNS.
Conference Dates
May 21-26, 2023
Conference Location
Kyoto, JP
Conference Title
the 2023 30th International Conference on Nuclear Engineering ICONE30

Keywords

U3Si2, U-10Mo, LEU-FUELED REACTOR CORE, NIST NEUTRON SOURCE

Citation

Celikten, O. , Weiss, A. and Sahin, D. (2023), Comparison of U3Si2 and U-10Mo LEU-Fueled Reactor Cores for the Preconceptual NIST Neutron Source Design, the 2023 30th International Conference on Nuclear Engineering ICONE30, Kyoto, JP, [online], https://tsapps.nist.gov/publication/get_pdf.cfm?pub_id=936313 (Accessed July 20, 2024)

Issues

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Created May 21, 2023, Updated March 15, 2024