TY - GEN
T1 - Core Physics Characteristics of Extended Enrichment and Higher Burnup Boiling Water Reactor Fuel
AU - Mertyurek, Ugur
AU - Cumberland, Riley
AU - Wieselquist, William A.
N1 - Publisher Copyright:
© 2024 AMERICAN NUCLEAR SOCIETY. All rights reserved.
PY - 2024
Y1 - 2024
N2 - This paper presents the highlights of boiling water reactor (BWR) core physics studies performed at Oak Ridge National Laboratory as part of a series of studies conducted to compare low-enriched uranium (LEU) with LEU+ fuel. The studies analyzed isotopic fuel content, lattice parameters (Phase 1), and core physics (Phase 2) to identify challenges in operation, storage, and transportation for BWRs and pressurized water reactors (PWRs). Because of a lack of publicly available lattice and core designs for modern BWR fuel assemblies and reactor cores, several optimized lattice designs were generated, and different core loading strategies were investigated. Twelve optimized lattice designs with 235U enrichments ranging from 1.6% to 9% and gadolinia loadings ranging from 3 to 8 wt% were used to model axial enrichment and geometry variations in fuel assemblies for core designs. Each core shares a common set of approximations in design and analysis to allow for consistent comparisons between LEU and LEU+ fuel. The objective is to highlight anticipated changes in core behavior with respect to the reference LEU core. Results of this study show that the differences in LEU and LEU+ core reactor physics characteristics are less significant than the differences in lattice physics characteristics reported in the Phase 1 studies.
AB - This paper presents the highlights of boiling water reactor (BWR) core physics studies performed at Oak Ridge National Laboratory as part of a series of studies conducted to compare low-enriched uranium (LEU) with LEU+ fuel. The studies analyzed isotopic fuel content, lattice parameters (Phase 1), and core physics (Phase 2) to identify challenges in operation, storage, and transportation for BWRs and pressurized water reactors (PWRs). Because of a lack of publicly available lattice and core designs for modern BWR fuel assemblies and reactor cores, several optimized lattice designs were generated, and different core loading strategies were investigated. Twelve optimized lattice designs with 235U enrichments ranging from 1.6% to 9% and gadolinia loadings ranging from 3 to 8 wt% were used to model axial enrichment and geometry variations in fuel assemblies for core designs. Each core shares a common set of approximations in design and analysis to allow for consistent comparisons between LEU and LEU+ fuel. The objective is to highlight anticipated changes in core behavior with respect to the reference LEU core. Results of this study show that the differences in LEU and LEU+ core reactor physics characteristics are less significant than the differences in lattice physics characteristics reported in the Phase 1 studies.
KW - BWR
KW - HALEU
KW - LEU+
KW - PARCS
KW - SCALE
UR - http://www.scopus.com/inward/record.url?scp=85202816521&partnerID=8YFLogxK
U2 - 10.13182/PHYSOR24-43661
DO - 10.13182/PHYSOR24-43661
M3 - Conference contribution
AN - SCOPUS:85202816521
T3 - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024
SP - 2194
EP - 2203
BT - Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024
PB - American Nuclear Society
T2 - 2024 International Conference on Physics of Reactors, PHYSOR 2024
Y2 - 21 April 2024 through 24 April 2024
ER -