TY - GEN
T1 - Transient Analysis of a Micro-reactor using the DireWolf Code Suite
AU - Roskoff, Nathan
AU - Kucukboyaci, Vefa
AU - Levinsky, Alex
AU - Laboure, Vincent
AU - Harter, Jackson
AU - Zabriskie, Adam
AU - Charlot, Lise
N1 - Funding Information:
This work was supported by the DOE ARPA-E MEITNER award (DE-FOA-0001798). This research made use of the resources of the High-Performance Computing Center at Idaho National Laboratory, which is supported by the Office of Nuclear Energy of the U.S. Department of Energy and the Nuclear Science User Facilities under Contract No. DEAC07-05ID14517.
Publisher Copyright:
© 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.
PY - 2022/5
Y1 - 2022/5
N2 - Transient analyses of heat pipe micro-reactors are necessary to ensure that hypothetical accident scenarios do not comprise reactor safety. Due to its small size and reliance on heat-pipes for cooling, the micro-reactor design introduced in this paper is a tightly coupled system which requires multi-physics tools to accurately model transient events. Idaho National Laboratory's DireWolf code suite based on the MOOSE framework is tailor-built to model heat-pipe reactors. This paper demonstrates DireWolf's ability to simulate the coupled thermal-neutronics transient behavior of a heat-pipe micro-reactor. The transient events presented here include an inadvertent rotation of all control drums simultaneously and a sudden complete rotation of a single control drum. A detailed description of each event is provided along with simulation results, including time dependent power and temperature distributions, and discussion.
AB - Transient analyses of heat pipe micro-reactors are necessary to ensure that hypothetical accident scenarios do not comprise reactor safety. Due to its small size and reliance on heat-pipes for cooling, the micro-reactor design introduced in this paper is a tightly coupled system which requires multi-physics tools to accurately model transient events. Idaho National Laboratory's DireWolf code suite based on the MOOSE framework is tailor-built to model heat-pipe reactors. This paper demonstrates DireWolf's ability to simulate the coupled thermal-neutronics transient behavior of a heat-pipe micro-reactor. The transient events presented here include an inadvertent rotation of all control drums simultaneously and a sudden complete rotation of a single control drum. A detailed description of each event is provided along with simulation results, including time dependent power and temperature distributions, and discussion.
KW - Direwolf
KW - micro-reactor
KW - multi-physics analyses
UR - https://www.scopus.com/pages/publications/85184961892
UR - https://www.osti.gov/biblio/1875119
U2 - 10.13182/PHYSOR22-37531
DO - 10.13182/PHYSOR22-37531
M3 - Conference contribution
SN - 9780894487873
T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
SP - 48
EP - 57
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 -