An assessment of UO2 and ATF concept fuel performance modeling demands against current experimental capabilities under LOCA conditions

A Probert, J Watson, A Aitkaliyeva - Annals of Nuclear Energy, 2024 - Elsevier
This paper compiles and digitizes the publicly reported data for integral loss of coolant
accident (LOCA) testing so it can be used by both multiphysics modeling and simulation …

Multiphysics analysis of fuel Fragmentation, Relocation, and dispersal Susceptibility–Part 2: High-Burnup Steady-State operating and fuel performance conditions

J Hirschhorn, I Greenquist, A Wysocki, N Capps - Annals of Nuclear Energy, 2023 - Elsevier
The US nuclear industry is pursuing increased cycle lengths and increasing the peak rod-
averaged burnup in an effort to increase the economic viability of the US nuclear fleet …

Coupled decay heat and thermal hydraulic capability for loss-of-coolant accident simulations

AM Graham, A Wysocki, AT Godfrey, N Capps… - … Engineering and Design, 2024 - Elsevier
Abstract The ANSI/ANS-5.1 standard “Decay Heat Power in Light Water Reactors” is a well-
known way to predict the decay heat as a function of time for lightwater reactors. The …

Impact of LWR assembly structural features on cladding burst behavior under LOCA conditions

D Schappel, N Capps - Nuclear Engineering and Design, 2024 - Elsevier
This provides an initial sco** study on clad balloon and burst behavior for burnup
extension of reactor fuel. The associated issues with burnup extension are fuel …

A realistic TRACE PWR LOCA model with application to high-burnup analysis

A Wysocki, N Capps - Annals of Nuclear Energy, 2025 - Elsevier
This paper presents a TRACE model of a postulated large-break loss-of-coolant accident
(LBLOCA) event in a four-loop pressurized water reactor (PWR). The input files have been …

Comparison between Pin-by-Pin Subchannel and System Level Thermal Hydraulic Results for High Burnup Loss-of-Coolant Applications

R Salko Jr, A Wysocki, B Hizoum, N Capps - 2023 - osti.gov
This milestone report summarizes recent work to investigate higher fidelity modeling and
simulation practices for large-break loss-of-coolant accident (LBLOCA) analysis in high …

High-burnup boiling water reactor steady-state operating conditions and fuel performance analysis

N Capps, R Salko, M Asgari, A Wysocki… - Annals of Nuclear …, 2025 - Elsevier
The primary operational costs for existing nuclear reactors are plant operation costs,
maintenance costs, and fuel costs, all of which are influenced by the materials used and the …

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 …

Bayesian statistical model for cladding high-temperature burst under loss-of-coolant accident conditions

Y Tasaki, T Narukawa, Y Udagawa - Journal of Nuclear Science …, 2024 - Taylor & Francis
This study developed a probabilistic determination model with respect to cladding high-
temperature burst conditions based on the Bayesian statistical method to reasonably …