Hydrogen in zirconium alloys: A review

AT Motta, L Capolungo, LQ Chen, MN Cinbiz… - Journal of Nuclear …, 2019 - Elsevier
Hydrogen absorbed into zirconium alloy nuclear fuel cladding as a result of the waterside
corrosion reaction can affect the properties of nuclear fuel, principally through the …

A critical review of high burnup fuel fragmentation, relocation, and dispersal under loss-of-coolant accident conditions

N Capps, C Jensen, F Cappia, J Harp, K Terrani… - Journal of Nuclear …, 2021 - Elsevier
High burnup fuel in excess of~ 6268 GWd/MTU has been observed to severely fragment
when subjected to temperature transient conditions as in a loss-of-coolant accident. In the …

BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms

RL Williamson, JD Hales, SR Novascone… - Nuclear …, 2021 - Taylor & Francis
BISON is a nuclear fuel performance application built using the Multiphysics Object-Oriented
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …

Prospects for additive manufacturing of nuclear fuel forms

AT Nelson - Progress in Nuclear Energy, 2023 - Elsevier
Additive manufacturing (AM) is viewed as a critical enabling technology for achieving
superior performance and improved economics across many sectors. Although the past …

Full core LOCA safety analysis for a PWR containing high burnup fuel

N Capps, A Wysocki, A Godfrey, B Collins… - … Engineering and Design, 2021 - Elsevier
For economic reasons, the US nuclear industry is renewing efforts to build a technical basis
to extend peak rod average burnup limits above the current regulatory burnup limit of 62 …

Multi-dimensional simulation of LWR fuel behavior in the BISON fuel performance code

RL Williamson, NA Capps, W Liu, YR Rashid, BD Wirth - Jom, 2016 - Springer
Nuclear fuel operates in an extreme environment that induces complex multiphysics
phenomena occurring over distances ranging from inter-atomic spacing to meters, and times …

Impact of uranium oxide (UO2) fuel with molybdenum (Mo) inserts on pressurized water reactor performance and safety

JP Gorton, D Schappel, AT Nelson… - Journal of Nuclear …, 2020 - Elsevier
This work investigates nuclear reactor performance and safety characteristics of UO 2 with
high thermal conductivity Mo insert structures by using multiphysics modeling techniques …

PCI analysis of a commercial PWR using BISON fuel performance code

N Capps, M Kennard, W Liu, BD Wirth… - Nuclear Engineering and …, 2017 - Elsevier
Through the early 2000's, nuclear fuel cladding failure resulting from pellet-cladding
interaction in commercial pressurized water reactor fuel was managed successfully by …

Modeling of pellet cladding interaction

J Sercombe, B Michel, C Riglet-Martial… - … -Second Edition. Volume …, 2020 - hal.science
In this article, a review of Pellet Cladding Interaction models is proposed. The key elements
behind the modeling stress-strain and iodine concentration at the clad inner wall during a …

Pellet cladding mechanical interaction modeling using the extended finite element method

BW Spencer, W Jiang, JE Dolbow, C Peco - 2016 - osti.gov
As a brittle material, the ceramic UO2 used as light water reactor fuel experiences significant
fracturing throughout its life, beginning with the first rise to power of fresh fuel. This has …