Reactivity-initiated accidents in two pressurized water reactor high burnup core designs

Fox, Mason A.; Lindsay, Isabelle O.; Gorton, Jacob P.; Brown, Nicholas R.

doi:10.1016/j.nucengdes.2023.112745

Reactivity-initiated accidents in two pressurized water reactor high burnup core designs

Journal Article · Fri Nov 10 00:00:00 EST 2023 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2023.112745· OSTI ID:2251585

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Univ. of Tennessee, Knoxville, TN (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Here, this paper presents a safety analysis of two proposed core loadings for 24-month Pressurized Water Reactor (PWR) fuel cycles. This analysis focuses on reactivity-initiated accidents (RIAs) and evaluates core safety performance impacts of rod-averaged burnup limits up to 75 GWD/MTU and less than 7 % enriched UO₂. The capabilities of Polaris, PARCS, and RELAP5-3D are leveraged to evaluate the core neutronic and thermal–hydraulic behavior for normal-operation, uncontrolled control rod withdrawal (CRW) transients, and control rod ejection (CRE) accidents. The two core designs are compared to identify features of realistic high burnup/extended enrichment core design approaches which have significant safety impact, identify experimental data needs for high-fidelity predictive modeling, and provide recommendations for future high burnup core designs. The first core design evaluated in this study was developed by Southern Nuclear Company and used an ZrB₂ Integral Fuel Burnable Absorber (IFBA) and B₄C Wet-Annular Burnable Absorber (WABA)-based burnable poison strategy. The second core design assessed in this work used a Gd₂O₃-doped UO₂ burnable poison, similar to that used in boiling water reactors or French PWRs. Results indicate that fuel thermal limits are maintained for limiting CRW and hot full power (HFP) CRE transients. Cladding failure is predicted for the highest energy deposition rods in each core during limiting hot zero power (HZP) CRE accidents (where maximum radially averaged enthalpy exceeds 120 cal/g), though licensing may be permissible with a limited number of failed rods. While concerns exist regarding high critical boron concentration during steady state for the IFBA core and large plenum pressures for the gadolinia core design, the analysis demonstrates adequate safety performance during limiting RIA accident scenarios for two representative high burnup core designs. Design changes limiting plenum pressures and implementation of accident tolerant fuel (ATF) cladding features which minimize hydriding and susceptibility to pellet-cladding mechanical interaction (PCMI) are recommended for future high burnup fuel concepts. To support the technical basis for burnup limit increases, high-fidelity fuel performance models are needed to address physical effects not considered in this analysis, and high burnup irradiated fuel tests are required to extend applicability of the fuel failure limits and validate existing and future models.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); University of Tennessee, Knoxville, TN (United States)

Sponsoring Organization:: USDOE; USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP); USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF)

Grant/Contract Number:: AC05-00OR22725; AC07-05ID14517; NE0009212

OSTI ID:: 2251585

Alternate ID(s):: OSTI ID: 2499271
OSTI ID: 2205377

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: 15 Vol. 415; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (37)

Effect of hydrogen contents on the mechanical properties of Zircaloy-4 Huang, J. -H.; Huang, S. -P. Journal of Nuclear Materials, Vol. 208, Issue 1-2 https://doi.org/10.1016/0022-3115(94)90208-9	journal	January 1994
Fuel failure and fission gas release in high burnup PWR fuels under RIA conditions Fuketa, Toyoshi; Sasajima, Hideo; Mori, Yukihide Journal of Nuclear Materials, Vol. 248 https://doi.org/10.1016/S0022-3115(97)00173-6	journal	September 1997
Core-to-specimen energy coupling results of the first modern fueled experiments in TREAT Woolstenhulme, Nicolas; Fleming, Austin; Holschuh, Tommy Annals of Nuclear Energy, Vol. 140 https://doi.org/10.1016/j.anucene.2019.107117	journal	June 2020
Reactivity Initiated Accident transient testing on irradiated fuel rods in PWR conditions: The CABRI International Program Biard, Bruno; Chevalier, Vincent; Gaillard, Claude Annals of Nuclear Energy, Vol. 141 https://doi.org/10.1016/j.anucene.2019.107253	journal	June 2020
Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5% Burns, Joseph R.; Hernandez, Richard; Terrani, Kurt A. Annals of Nuclear Energy, Vol. 142 https://doi.org/10.1016/j.anucene.2020.107423	journal	July 2020
Lattice physics calculations using the embedded self-shielding method in polaris, Part II: Benchmark assessment Mertyurek, Ugur; Jessee, Matthew A.; Betzler, Benjamin R. Annals of Nuclear Energy, Vol. 150 https://doi.org/10.1016/j.anucene.2020.107829	journal	January 2021
Sensitivity analysis of in-pile critical heat flux experiments in TREAT for characterization of RIA power-transient effects Seo, Seok Bin; Armstrong, Robert J.; Hernandez, Richard Annals of Nuclear Energy, Vol. 161 https://doi.org/10.1016/j.anucene.2021.108448	journal	October 2021
Multi-field modelling of hydride forming metals. Part I: Model formulation and validation Jernkvist, L. O.; Massih, A. R. Computational Materials Science, Vol. 85 https://doi.org/10.1016/j.commatsci.2013.11.034	journal	April 2014
Elucidating the Impact of Flow on Material-Sensitive Critical Heat Flux and Boiling Heat Transfer Coefficients: An Experimental Study with Various Materials Lee, Soon K.; Lee, Youho; Brown, Nicholas R. International Journal of Heat and Mass Transfer, Vol. 158 https://doi.org/10.1016/j.ijheatmasstransfer.2020.119970	journal	September 2020
Effect of burn-up on the thermal conductivity of uranium dioxide up to 100.000 MWdt−1 Ronchi, C.; Sheindlin, M.; Staicu, D. Journal of Nuclear Materials, Vol. 327, Issue 1 https://doi.org/10.1016/j.jnucmat.2004.01.018	journal	April 2004
The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA) Desquines, J.; Koss, D. A.; Motta, A. T. Journal of Nuclear Materials, Vol. 412, Issue 2 https://doi.org/10.1016/j.jnucmat.2011.03.015	journal	May 2011
Fracture properties of hydrided Zircaloy-4 cladding in recrystallization and stress-relief anneal conditions Hsu, Hsiao-Hung; Tsay, Leu-Wen Journal of Nuclear Materials, Vol. 422, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.12.032	journal	March 2012
Effect of burn-up on the thermal conductivity of uranium–gadolinium dioxide up to 100 GWd/tHM Staicu, D.; Rondinella, V. V.; Walker, C. T. Journal of Nuclear Materials, Vol. 453, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.07.006	journal	October 2014
Multiscale modeling of thermal conductivity of high burnup structures in UO2 fuels Bai, Xian-Ming; Tonks, Michael R.; Zhang, Yongfeng Journal of Nuclear Materials, Vol. 470 https://doi.org/10.1016/j.jnucmat.2015.12.028	journal	March 2016
Hydrogen in zirconium alloys: A review Motta, Arthur T.; Capolungo, Laurent; Chen, Long-Qing Journal of Nuclear Materials, Vol. 518 https://doi.org/10.1016/j.jnucmat.2019.02.042	journal	May 2019
A three-dimensional axial fuel relocation framework with discrete element method to support burnup extension Ma, Zehua; Shirvan, Koroush; Wu, Yingwei Journal of Nuclear Materials, Vol. 541 https://doi.org/10.1016/j.jnucmat.2020.152408	journal	December 2020
A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions Capps, Nathan; Jensen, Colby; Cappia, Fabiola Journal of Nuclear Materials, Vol. 546 https://doi.org/10.1016/j.jnucmat.2020.152750	journal	April 2021
Hydride embrittlement resistance of Zircaloy-4 and Zr-Nb alloy cladding tubes and its implications on spent fuel management Kim, Sangbum; Kang, Joo-Hee; Lee, Youho Journal of Nuclear Materials, Vol. 559 https://doi.org/10.1016/j.jnucmat.2021.153393	journal	February 2022
Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution Barani, Tommaso; Pizzocri, Davide; Cappia, Fabiola Journal of Nuclear Materials, Vol. 563 https://doi.org/10.1016/j.jnucmat.2022.153627	journal	May 2022
Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing Cappia, F.; Wright, K.; Frazer, D. Journal of Nuclear Materials, Vol. 569 https://doi.org/10.1016/j.jnucmat.2022.153881	journal	October 2022
AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding Bischoff, Jeremy; Delafoy, Christine; Vauglin, Christine Nuclear Engineering and Technology, Vol. 50, Issue 2 https://doi.org/10.1016/j.net.2017.12.004	journal	March 2018
Integral LOCA fragmentation test on high-burnup fuel Capps, Nathan; Yan, Yong; Raftery, Alicia Nuclear Engineering and Design, Vol. 367 https://doi.org/10.1016/j.nucengdes.2020.110811	journal	October 2020
Full core LOCA safety analysis for a PWR containing high burnup fuel Capps, Nathan; Wysocki, Aaron; Godfrey, Andrew Nuclear Engineering and Design, Vol. 379 https://doi.org/10.1016/j.nucengdes.2021.111194	journal	August 2021
Experimental study of the transient boiling phenomenon on a vertically placed ribbon Yan, Yikuan; Brown, Emory; Marcum, Wade Nuclear Engineering and Design, Vol. 390 https://doi.org/10.1016/j.nucengdes.2022.111705	journal	April 2022
Design of separate-effects In-Pile transient boiling experiments at the TREAT Facility Folsom, Charles P.; Armstrong, Robert J.; Woolstenhulme, Nicolas E. Nuclear Engineering and Design, Vol. 397 https://doi.org/10.1016/j.nucengdes.2022.111919	journal	October 2022
Model for determining rupture area in Zircaloy cladding under LOCA conditions Capps, Nathan; Sweet, Ryan Nuclear Engineering and Design, Vol. 401 https://doi.org/10.1016/j.nucengdes.2022.112096	journal	January 2023
Sensitivity of UO2 fuel performance to microstructural evolutions driven by dilute additives Cheniour, Amani; Sweet, Ryan T.; Nelson, Andrew T. Nuclear Engineering and Design, Vol. 410 https://doi.org/10.1016/j.nucengdes.2023.112383	journal	August 2023
The maturing of nuclear fuel: Past to Accident Tolerant Fuel Karoutas, Zeses; Brown, Jeffery; Atwood, Andrew Progress in Nuclear Energy, Vol. 102 https://doi.org/10.1016/j.pnucene.2017.07.016	journal	January 2018
Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL Meehan, Nicholas A.; Seo, Seok Bin; Howard, Trevor K. Nuclear Technology, Vol. 209, Issue 8 https://doi.org/10.1080/00295450.2023.2195355	journal	May 2023
Thermal Diffusivities and Thermal Conductivities of UO ₂ -Gd ₂ O ₃ Hirai, Mutsumi; Ishimoto, Shinji Journal of Nuclear Science and Technology, Vol. 28, Issue 11 https://doi.org/10.1080/18811248.1991.9731462	journal	November 1991
Analysis of the Core Power Response during a PWR Rod Ejection Transient Using the PARCS Nodal Code and the DeCART MOC Code Hursin, Mathieu; Downar, Thomas J.; Kochunas, Brendan Nuclear Science and Engineering, Vol. 170, Issue 2 https://doi.org/10.13182/NSE10-75	journal	February 2012
Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON Bratton, Ryan N.; Jessee, Matt A.; Wieselquist, William A. Nuclear Technology, Vol. 197, Issue 1 https://doi.org/10.13182/NT16-75	journal	January 2017
Smoothed Values of the Enthalpy and Heat Capacity of UO₂ Kerrisk, Jerry F.; Clifton, David G. Nuclear Technology, Vol. 16, Issue 3 https://doi.org/10.13182/NT72-6	journal	December 1972
Investigation of Achievable Peak Rod Average Burnup with Full Core Fuel Performance for 4-Loop PWRs Halimi, Assil; Shirvan, Koroush TopFuel 2022 Light Water Reactor Fuel Performance Conference https://doi.org/10.13182/TopFuel22-38787	conference	January 2022
Isotopic and Fuel Lattice Parameter Trends in Extended Enrichment and Higher Burnup LWR Fuel, Volume II: BWR Cumberland, Riley; Sweet, Ryan; Mertyurek, Ugur https://doi.org/10.2172/1782042	report	March 2021
High-burnup Experiments in Reactivity Initiated Accidents (HERA) Kamerman, David; Jensen, Colby; Wachs, Daniel https://doi.org/10.2172/1874819	report	June 2022
Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels using the Polaris/PARCS Two-Step Approach. Vol. I: PWR Fuel Hu, Jianwei; Mertyurek, Ugur; Wieselquist, William https://doi.org/10.2172/1905421	report	June 2022

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