TY - GEN
T1 - INITIAL EXPLORATION OF A NOVEL TRANSIENT ARREST SYSTEM INVOLVING FUEL HEATING
AU - Price, Dean Reid ;
AU - Gale, Micah D (ORCID:0000000164514818);
AU - DeHart, Mark D (ORCID:0000000246864301);
AU - Maile, Andrew David ;
AU - Peterson-Droogh, Joshua L (ORCID:000000029181192X)
N1 - Funding Information:
The modeling tools were based on the EPKE solver by Evan Gonzalez. This manuscript has been authored by Battelle Energy Alliance, LLC under Contract No. DE-AC07-05ID14517 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for U.S. Government purposes.
Publisher Copyright:
© 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.
PY - 2022/5
Y1 - 2022/5
N2 - 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.
AB - 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.
KW - Accident Response
KW - Advanced Test Reactor
KW - Reactor Dynamics
KW - System Design
UR - https://www.scopus.com/pages/publications/85184958591
UR - https://www.osti.gov/biblio/1871314-initial-exploration-novel-transient-arrest-system-involving-fuel-heating
U2 - 10.13182/PHYSOR22-37534
DO - 10.13182/PHYSOR22-37534
M3 - Conference contribution
SN - 9780894487873
T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
SP - 864
EP - 872
BT - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
PB - American Nuclear Society
T2 - 2022 International Conference on Physics of Reactors, PHYSOR 2022
Y2 - 15 May 2022 through 20 May 2022
ER -