Physics-based multiscale coupling for full core nuclear reactor simulation

DR Gaston, CJ Permann, JW Peterson… - Annals of Nuclear …, 2015 - Elsevier
Numerical simulation of nuclear reactors is a key technology in the quest for improvements
in efficiency, safety, and reliability of both existing and future reactor designs. Historically …

Validating the BISON fuel performance code to integral LWR experiments

RL Williamson, KA Gamble, DM Perez… - … Engineering and Design, 2016 - Elsevier
BISON is a modern finite element-based nuclear fuel performance code that has been under
development at Idaho National Laboratory (INL) since 2009. The code is applicable to both …

Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions

C Deng, Y He, F Xiang, Y Wu, J Zhang, W Tian… - Progress in Nuclear …, 2022 - Elsevier
U 3 Si 2–FeCrAl system has been a promising Accident Tolerant Fuels (ATFs) candidate for
its higher thermal conductivity, higher uranium density and lower oxidation rate. As a part of …

Kriging-based inverse uncertainty quantification of nuclear fuel performance code BISON fission gas release model using time series measurement data

X Wu, T Kozlowski, H Meidani - Reliability Engineering & System Safety, 2018 - Elsevier
In nuclear reactor fuel performance simulation, fission gas release (FGR) and swelling
involve treatment of several complicated and interrelated physical processes, which …

Quantifying deformation during Zry-4 burst testing: a comparison of BISON and a combined in-situ digital image correlation and infrared thermography method

K Kane, S Bell, B Garrison, M Ridley, M Gussev… - Journal of Nuclear …, 2022 - Elsevier
The development and verification of nuclear fuel-cladding performance codes require
extensive testing to establish empirical correlations, necessitating more accelerated testing …

Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON

D Schappel, K Terrani, JJ Powers, LL Snead… - … Engineering and Design, 2018 - Elsevier
Fully ceramic microencapsulated (FCM) fuel is a proposed fuel type for improved accident
performance in LWRs (Light Water Reactors) that involves TRISO (TRistructural-ISOtropic) …

Failure analysis of nuclear transient-tested UN tristructural isotropic fuel particles in a 3D printed SiC matrix

D Schappel, KD Linton, GW Helmreich… - Journal of Nuclear …, 2023 - Elsevier
Fully ceramic microencapsulated fuel elements containing UN tristructural isotropic (TRISO)
fuel particles within a 3D printed SiC matrix were subjected to transient testing with varying …

U3Si2-SiC fuel performance analysis in BISON during normal operation

W Li, K Shirvan - Annals of Nuclear Energy, 2019 - Elsevier
U 3 Si 2-SiC is an accident-tolerant fuel concept currently under development by
Westinghouse that has potential to improve economic performance and safety of light water …

TREAT testing of additively manufactured SiC canisters loaded with high density TRISO fuel for the Transformational Challenge Reactor project

N Woolstenhulme, D Chapman, N Cordes… - Journal of Nuclear …, 2023 - Elsevier
Specimens composed of a novel nuclear fuel architecture underwent testing in the Transient
Reactor Test Facility (TREAT) to investigate their behavior in thermomechanical states only …

[HTML][HTML] Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX

G Zullo, D Pizzocri, A Magni, P Van Uffelen… - Nuclear Engineering …, 2022 - Elsevier
When assessing the radiological consequences of postulated accident scenarios, it is of
primary interest to determine the amount of radioactive fission gas accumulated in the fuel …