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INITIAL EXPLORATION OF A NOVEL TRANSIENT ARREST SYSTEM INVOLVING FUEL HEATING

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

A preliminary analysis on a novel accident response system to diminish the severity of supercritical transients was conducted. The novel accident response system, called the instant shock arrest system, involves using electricity to heat the nuclear fuel at the onset of a large accidental reactivity insertion. This system is specifically designed for reactors with metallic fuel, such that the fuel is capable of conducting electricity, and being resistively heated. A reactor dynamics model of the advanced test reactor was created using the point kinetics equations and a linear reactivity feedback model to simulate how the system would effect the maximum fuel temperatures experienced during the transient. Transients with the instant shock arrest system were compare to those without it. It was found that the instant shock arrest system initially heated the fuel more than the unaffected transient but the negative reactivity inserted from such heating was enough to lower the maximum fuel temperature experienced during the transient. After simulating six different accident scenarios with reactivity insertions ranging from 0.5 \$ to 1.3 \$, it was found that the an optimal system response could reduce peak fuel temperatures during the transient by 3.5\% to 5\%. Furthermore, discussion was given on how the optimal system response could be obtained using relatively simple numerical optimization algorithms due to the smoothness of the optimization problem.
Original languageEnglish
Title of host publicationProceedings of the International Conference on Physics of Reactors, PHYSOR 2022
PublisherAmerican Nuclear Society
Pages864-872
Number of pages9
ISBN (Electronic)9780894487873
ISBN (Print)9780894487873
DOIs
StatePublished - May 2022
Event2022 International Conference on Physics of Reactors, PHYSOR 2022 - Pittsburgh, United States
Duration: May 15 2022May 20 2022

Publication series

NameProceedings of the International Conference on Physics of Reactors, PHYSOR 2022

Conference

Conference2022 International Conference on Physics of Reactors, PHYSOR 2022
Country/TerritoryUnited States
CityPittsburgh
Period05/15/2205/20/22

Keywords

  • Accident Response
  • Advanced Test Reactor
  • Reactor Dynamics
  • System Design

INL Publication Number

  • INL/CON-21-64554
  • 130623

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