Effects of transient fission gas release on rod balloon burst behavior during a loss-of-coolant accident

Greenquist, Ian; Capps, Nathan

doi:10.1016/j.anucene.2023.110213

Effects of transient fission gas release on rod balloon burst behavior during a loss-of-coolant accident

Journal Article · Fri Nov 17 00:00:00 EST 2023 · Annals of Nuclear Energy

DOI:https://doi.org/10.1016/j.anucene.2023.110213· OSTI ID:2224164

Greenquist, Ian ^[1]; Capps, Nathan ^[1]

Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

The US nuclear energy industry is investigating strategies to increase the reactor operating cycle to 24 months, which would result in rod average burnups exceeding the current limit of 62 GWd/tU. To support this goal, multiphysics simulations tools and methodologies are being developed to predict the effects of this change during transient events such as loss-of-coolant accidents (LOCAs). In this work, two cladding burst correlations were used to predict cladding failure. Here, these were coupled with three transient fission gas release (tFGR) models and were implemented in the BISON fuel performance code to quantify any changes in cladding burst behavior during a large-break LOCA. First, a simple linear model was used to perform a sensitivity analysis of a single fuel rod. Second, a tFGR model available in BISON was applied to 281 fuel rods throughout the core. The third model examined was an empirical correlation based on data from the literature.

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE Office of Nuclear Energy (NE), Nuclear Energy Advanced Modeling and Simulation (NEAMS); USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign; USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF)

Grant/Contract Number:: AC05-00OR22725; AC07-05ID14517

OSTI ID:: 2224164

Alternate ID(s):: OSTI ID: 2369973

Journal Information:: Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Vol. 196; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (10)

Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 1: Overview and code coupling strategies Greenquist, Ian; Wysocki, Aaron; Hirschhorn, Jake Annals of Nuclear Energy, Vol. 191 https://doi.org/10.1016/j.anucene.2023.109913	journal	October 2023
Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup conditions Wysocki, Aaron; Hirschhorn, Jake; Greenquist, Ian Annals of Nuclear Energy, Vol. 192 https://doi.org/10.1016/j.anucene.2023.109951	journal	November 2023
Multiphysics analysis of fuel Fragmentation, Relocation, and dispersal Susceptibility–Part 2: High-Burnup Steady-State operating and fuel performance conditions Hirschhorn, Jake; Greenquist, Ian; Wysocki, Aaron Annals of Nuclear Energy, Vol. 192 https://doi.org/10.1016/j.anucene.2023.109952	journal	November 2023
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Empirical and mechanistic transient fission gas release model for high-burnup LOCA conditions Capps, Nathan; Aagesen, Larry; Andersson, David Journal of Nuclear Materials, Vol. 584 https://doi.org/10.1016/j.jnucmat.2023.154557	journal	October 2023
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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