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

I Greenquist, N Capps - Annals of Nuclear Energy, 2024 - Elsevier
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 …

Characterization of modeling and experimental data inconsistencies from burst testing for high-burnup commercial fuel rod applications

N Capps, R Sweet - Journal of Nuclear Materials, 2022 - Elsevier
Fuel fragmentation, relocation, and dispersal are some of the largest issues remaining in the
nuclear industry before rod-average burnup can be increased beyond 62 GWd/tU. The issue …

Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Fuel modeling developments and simulation of integral experiments

G Pastore, KA Gamble, RL Williamson… - Journal of Nuclear …, 2021 - Elsevier
In the first part of this work, we discussed BISON fuel performance code developments for
Zircaloy cladding behavior under loss-of-coolant accident (LOCA) conditions and validation …

[PDF][PDF] SATS Transient Fission Gas Release Test with Irradiated Fuel under Loss of Coolant Accident Conditions

Y Yan, J Harp, C Baldwin, R Morris, N Capps - 2023 - osti.gov
The transient fission gas release (tFGR) during the temperature ramp associated with a loss-
ofcoolant accident (LOCA) in light-water reactors (LWRs) is likely a significant contribution to …

BISON validation to in situ cladding burst test and high-burnup LOCA experiments

N Capps, M Ridley, Y Yan, S Bell, K Kane - Annals of Nuclear Energy, 2023 - Elsevier
The process for developing and qualifying nuclear fuels for commercial nuclear application
requires fundamental material development, characterization, and design; out-of-pile testing …

Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Cladding modeling developments and simulation of separate-effects experiments

G Pastore, RL Williamson, RJ Gardner… - Journal of Nuclear …, 2021 - Elsevier
BISON is a finite-element based, multidimensional fuel performance code developed at
Idaho National Laboratory. In this paper, we present BISON modeling developments for …

Modelling of LOCA Tests with the BISON Fuel Performance Code

RL Williamson, G Pastore, SR Novascone… - 2016 - osti.gov
BISON is a modern finite-element based, multidimensional nuclear fuel performance code
that is under development at Idaho National Laboratory (USA). Recent advances of BISON …

[HTML][HTML] Analytical criteria for fuel fragmentation and burst FGR during a LOCA

G Khvostov - Nuclear Engineering and Technology, 2020 - Elsevier
Analytical criteria for the onset of fuel fragmentation and Burst Fission Gas Release in fuel
rods with ballooned claddings are formulated. On that basis, the GRSW-A model integrated …

Development of a LOCA Experimental Benchmark for BISON-Milestone L2: FMC. P15. 08

G Pastore, KA Gamble, RJ Gardner, JB Tompkins… - 2017 - osti.gov
Since 2013 CASL has been planning and working towards a PWR LOCA Challenge
Problem. Since BISON is the CASL fuel rod simulation platform, it plays a central role in that …

Analysis of FeCrAl cladding performance under loss-of-coolant accident conditions

RT Sweet, G Pastore, BD Wirth - Nuclear Engineering and Design, 2023 - Elsevier
Modeling developments and simulations of iron-chromium-aluminum (FeCrAl) cladding
behavior under loss-of-coolant accident (LOCA) conditions have been performed using the …