TY - GEN
T1 - An Adaptive Model for Decay Heat Estimation Using Scram Curves
AU - Nikitin, Evgeny
AU - Fridman, Emil
AU - Ponomarev, Alexander
N1 - Publisher Copyright:
© 2024 AMERICAN NUCLEAR SOCIETY. All rights reserved.
PY - 2024/1/1
Y1 - 2024/1/1
N2 - This study introduces an adaptive model for estimating decay heat in nuclear reactors, particularly during transient scenarios with steadily reducing reactor power.Traditional approaches to decay heat calculation often rely on extensive nuclide tracking or standardized procedures.The former approach can be resource-intensive, requiring detailed tracking of a multitude of nuclides, while the latter often has limited applicability.The adaptive model proposed in this paper offers an alternative solution that circumvents these challenges by utilizing precalculated decay heat curves from scram scenarios.This methodology allows for on-the-fly decay heat calculation during simulation, adapting to varying power levels without the need for detailed nuclide tracking.The paper provides a description of the adaptive model, including its mathematical framework and operational procedure.The model's test case is developed using the IAEA benchmark exercise related to the loss of flow without scram test conducted at the Fast Flux Test Facility, a sodium-cooled fast reactor.The model is verified through single assembly calculations, where it demonstrates high accuracy in comparison to the depletion solver of the Monte Carlo code Serpent.This demonstrates the model's potential as a promising alternative for decay heat estimation in the analysis of accident scenarios.
AB - This study introduces an adaptive model for estimating decay heat in nuclear reactors, particularly during transient scenarios with steadily reducing reactor power.Traditional approaches to decay heat calculation often rely on extensive nuclide tracking or standardized procedures.The former approach can be resource-intensive, requiring detailed tracking of a multitude of nuclides, while the latter often has limited applicability.The adaptive model proposed in this paper offers an alternative solution that circumvents these challenges by utilizing precalculated decay heat curves from scram scenarios.This methodology allows for on-the-fly decay heat calculation during simulation, adapting to varying power levels without the need for detailed nuclide tracking.The paper provides a description of the adaptive model, including its mathematical framework and operational procedure.The model's test case is developed using the IAEA benchmark exercise related to the loss of flow without scram test conducted at the Fast Flux Test Facility, a sodium-cooled fast reactor.The model is verified through single assembly calculations, where it demonstrates high accuracy in comparison to the depletion solver of the Monte Carlo code Serpent.This demonstrates the model's potential as a promising alternative for decay heat estimation in the analysis of accident scenarios.
KW - DYN3D
KW - Decay heat
KW - SFR
KW - Serpent
KW - ULOF
UR - https://www.scopus.com/pages/publications/85202814325
U2 - 10.13182/PHYSOR24-45196
DO - 10.13182/PHYSOR24-45196
M3 - Conference contribution
AN - SCOPUS:85202814325
T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024
SP - 1838
EP - 1844
BT - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024
PB - American Nuclear Society
T2 - 2024 International Conference on Physics of Reactors, PHYSOR 2024
Y2 - 21 April 2024 through 24 April 2024
ER -