Published 2022 | Version v1
Book

Initial exploration of a novel transient arrest system involving fuel heating

  • 1. Idaho National Laboratory, 1995 Fremont Avenue, PO box 1625, Idaho Falls, ID 83402 (United States)

Description

A preliminary analysis on a novel accident response system to diminish the severity of super- critical 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 compared 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 dollar, it was found that 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. (authors)

Availability note (English)

Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)
Part of:
Proceedings of the international conference on physics of reactors - Physor 2022

Additional details

Publishing Information

Publisher
ANS - American Nuclear Society
Imprint Place
La Grange Park (United States)
ISBN
978-0-89448-787-3
Imprint Title
Proceedings of the international conference on physics of reactors - Physor 2022
Imprint Pagination
3701 p.
Journal Page Range
p. 890-898

Conference

Title
International conference on physics of reactors
Acronym
PHYSOR 2022
Dates
15-20 May 2022
Place
Pittsburg (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
53097008
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ENGINEERED SAFETY SYSTEMS; MITIGATION; ROD EJECTION ACCIDENTS; TESTING
Descriptors DEC
ACCIDENTS; REACTIVITY-INITIATED ACCIDENTS; REACTOR ACCIDENTS

Optional Information

Notes
12 refs.