Transient Convective Delayed Neutron Precursors of 235U for the Molten Salt Reactor Experiment

Kyoung O. Lee; Matthew A. Jessee; Benjamin S. Collins; Zack Taylor; Aaron M. Graham

doi:10.13182/PHYSOR22-37296

Transient Convective Delayed Neutron Precursors of ²³⁵U for the Molten Salt Reactor Experiment

Kyoung O. Lee, Matthew A. Jessee, Benjamin S. Collins, Zack Taylor, Aaron M. Graham

Power Reactor Modeling

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

4 Scopus citations

Abstract

This work investigates the delayed neutron precursors from the fission of ²³⁵U in molten salt reactors. The six delayed neutron groups predict the spatial distribution by the advective transport for radioactive mass transfer in the Molten-Salt Reactor Experiment (MSRE). Mole, using the framework of the Multiphysics Object-Oriented Simulation Environment (MOOSE), was used to compute the delayed neutron concentration of the whole system. This approach can be used for analysis of reactivity in circulating conditions. The effect of delayed neutron concentrations on the static or dynamic behavior of the system in MSRE was analyzed. Using this approach, the pattern and validation of delayed neutron for a range of parameters of interest are reported and discussed herein.

Original language	English
Title of host publication	Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
Publisher	American Nuclear Society
Pages	1328-1337
Number of pages	10
ISBN (Electronic)	9780894487873
DOIs	https://doi.org/10.13182/PHYSOR22-37296
State	Published - 2022
Event	2022 International Conference on Physics of Reactors, PHYSOR 2022 - Pittsburgh, United States Duration: May 15 2022 → May 20 2022

Publication series

Name	Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022

Conference

Conference	2022 International Conference on Physics of Reactors, PHYSOR 2022
Country/Territory	United States
City	Pittsburgh
Period	05/15/22 → 05/20/22

Funding

This work has been carried out in the framework of the NEAMS (Nuclear Energy Advanced Modeling and Simulation) program supported by the United States Department of Energy.

Funders	Funder number
U.S. Department of Energy

Keywords

MSRE
convection
delayed neutrons precursors
uranium-235

Access to Document

10.13182/PHYSOR22-37296

Cite this

Lee, K. O., Jessee, M. A., Collins, B. S., Taylor, Z., & Graham, A. M. (2022). Transient Convective Delayed Neutron Precursors of ²³⁵U for the Molten Salt Reactor Experiment. In Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022 (pp. 1328-1337). (Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022). American Nuclear Society. https://doi.org/10.13182/PHYSOR22-37296

Lee, Kyoung O. ; Jessee, Matthew A. ; Collins, Benjamin S. et al. / Transient Convective Delayed Neutron Precursors of ²³⁵U for the Molten Salt Reactor Experiment. Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. American Nuclear Society, 2022. pp. 1328-1337 (Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022).

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title = "Transient Convective Delayed Neutron Precursors of 235U for the Molten Salt Reactor Experiment",

abstract = "This work investigates the delayed neutron precursors from the fission of 235U in molten salt reactors. The six delayed neutron groups predict the spatial distribution by the advective transport for radioactive mass transfer in the Molten-Salt Reactor Experiment (MSRE). Mole, using the framework of the Multiphysics Object-Oriented Simulation Environment (MOOSE), was used to compute the delayed neutron concentration of the whole system. This approach can be used for analysis of reactivity in circulating conditions. The effect of delayed neutron concentrations on the static or dynamic behavior of the system in MSRE was analyzed. Using this approach, the pattern and validation of delayed neutron for a range of parameters of interest are reported and discussed herein.",

keywords = "MSRE, convection, delayed neutrons precursors, uranium-235",

author = "Lee, {Kyoung O.} and Jessee, {Matthew A.} and Collins, {Benjamin S.} and Zack Taylor and Graham, {Aaron M.}",

note = "Publisher Copyright: {\textcopyright} 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.; 2022 International Conference on Physics of Reactors, PHYSOR 2022 ; Conference date: 15-05-2022 Through 20-05-2022",

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language = "English",

series = "Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022",

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Lee, KO, Jessee, MA, Collins, BS, Taylor, Z & Graham, AM 2022, Transient Convective Delayed Neutron Precursors of ²³⁵U for the Molten Salt Reactor Experiment. in Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022, American Nuclear Society, pp. 1328-1337, 2022 International Conference on Physics of Reactors, PHYSOR 2022, Pittsburgh, United States, 05/15/22. https://doi.org/10.13182/PHYSOR22-37296

Transient Convective Delayed Neutron Precursors of ²³⁵U for the Molten Salt Reactor Experiment. / Lee, Kyoung O.; Jessee, Matthew A.; Collins, Benjamin S. et al.
Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. American Nuclear Society, 2022. p. 1328-1337 (Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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N2 - This work investigates the delayed neutron precursors from the fission of 235U in molten salt reactors. The six delayed neutron groups predict the spatial distribution by the advective transport for radioactive mass transfer in the Molten-Salt Reactor Experiment (MSRE). Mole, using the framework of the Multiphysics Object-Oriented Simulation Environment (MOOSE), was used to compute the delayed neutron concentration of the whole system. This approach can be used for analysis of reactivity in circulating conditions. The effect of delayed neutron concentrations on the static or dynamic behavior of the system in MSRE was analyzed. Using this approach, the pattern and validation of delayed neutron for a range of parameters of interest are reported and discussed herein.

AB - This work investigates the delayed neutron precursors from the fission of 235U in molten salt reactors. The six delayed neutron groups predict the spatial distribution by the advective transport for radioactive mass transfer in the Molten-Salt Reactor Experiment (MSRE). Mole, using the framework of the Multiphysics Object-Oriented Simulation Environment (MOOSE), was used to compute the delayed neutron concentration of the whole system. This approach can be used for analysis of reactivity in circulating conditions. The effect of delayed neutron concentrations on the static or dynamic behavior of the system in MSRE was analyzed. Using this approach, the pattern and validation of delayed neutron for a range of parameters of interest are reported and discussed herein.

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Lee KO, Jessee MA, Collins BS, Taylor Z, Graham AM. Transient Convective Delayed Neutron Precursors of ²³⁵U for the Molten Salt Reactor Experiment. In Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. American Nuclear Society. 2022. p. 1328-1337. (Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022). doi: 10.13182/PHYSOR22-37296