Effect of ATF Cr-coated-Zircaloy on BWR In-vessel Accident Progression during a Station Blackout

Guo, Zehua; Dailey, Ryan; Zhou, Yukun; Sun, Zhongning; Wang, Jun; Corradini, Michael L.

doi:10.1016/j.nucengdes.2020.110979

Effect of ATF Cr-coated-Zircaloy on BWR In-vessel Accident Progression during a Station Blackout

Journal Article · Thu Dec 24 23:00:00 EST 2020 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2020.110979· OSTI ID:1848095

Guo, Zehua ^[1]; Dailey, Ryan ^[2]; Zhou, Yukun ^[2]; Sun, Zhongning ^[3]; ^[2]; Corradini, Michael L. ^[2]

Univ. of Wisconsin, Madison, WI (United States). Nuclear Engineering; Harbin Engineering Univ., Harbin (China). Heilongjiang Provincial Key Lab. of Nuclear Power System & Equipment; Univ. of Wisconsin, Madison, WI (United States)
Univ. of Wisconsin, Madison, WI (United States). Nuclear Engineering
Harbin Engineering Univ., Harbin (China). Heilongjiang Provincial Key Lab. of Nuclear Power System & Equipment

The deposition of protective coatings on nuclear fuel cladding has been considered as a near-term Accident Tolerant Fuel (ATF) concept that will reduce the high-temperature oxidation rate and enhance accident tolerance of the cladding while providing additional benefits during normal and transient. In this study, the performance of the proposed ATF concept of Cr-coated-Zircaloy is assessed using a generic Boiling Water Reactor MELCOR plant model considering a Short-term Station Blackout (STSBO) scenario. Simulation results indicate that the use of Cr-coated-Zircaloy as cladding and canister material mitigates the core degradation process as compared to the traditional Zircaloy cladding and canister design. The onset of fuel degradation and collapse is delayed by over thirty minutes, and the extent of fuel degradation is reduced. Specifically, the gross in-vessel hydrogen generation decreased by almost a factor of three. Although the eutectic reaction between Cr-coating and Zircaloy could cause an early failure of the coating, the improvement in the delay of fuel degradation is still notable. In addition, a thicker coating is found helpful to obtain additional coping time and to decrease hydrogen generation. In addition to the eutectic formation that may compromise Cr-coated Zr, a different failure mode is identified for the Cr-coated-Zr when compared to Zircaloy; i.e., a complete melt of base material leads to component collapse before the coating is oxidized and consumed. These findings can help the industry focus on productive areas of research and development for accident-tolerant fuel concepts and enhancement of core safety margins.

View Accepted Manuscript (DOE)

Research Organization:: Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: NE0008752

OSTI ID:: 1848095

Alternate ID(s):: OSTI ID: 1776155

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: C Vol. 372; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (30)

Material Selection for Accident Tolerant Fuel Cladding Pint, B. A.; Terrani, K. A.; Yamamoto, Y. Metallurgical and Materials Transactions E, Vol. 2, Issue 3 https://doi.org/10.1007/s40553-015-0056-7	journal	September 2015
Oxidation behavior analysis of cladding during severe accidents with combined codes for Qinshan Phase II Nuclear Power Plant Shi, Xingwei; Cao, Xinrong; Liu, Zhengzhi Annals of Nuclear Energy, Vol. 58 https://doi.org/10.1016/j.anucene.2013.03.031	journal	August 2013
Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors George, Nathan Michael; Terrani, Kurt; Powers, Jeff Annals of Nuclear Energy, Vol. 75 https://doi.org/10.1016/j.anucene.2014.09.005	journal	January 2015
Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions Wu, Xu; Kozlowski, Tomasz; Hales, Jason D. Annals of Nuclear Energy, Vol. 85 https://doi.org/10.1016/j.anucene.2015.06.032	journal	November 2015
Fuel performance of chromium-coated zirconium alloy and silicon carbide accident tolerant fuel claddings Wagih, Malik; Spencer, Benjamin; Hales, Jason Annals of Nuclear Energy, Vol. 120 https://doi.org/10.1016/j.anucene.2018.06.001	journal	October 2018
Evaluation of accident tolerant cladding materials in a severe accident of the BNPP Ebrahimgol, H.; Aghaie, M.; Zolfaghari, A. Annals of Nuclear Energy, Vol. 129 https://doi.org/10.1016/j.anucene.2019.02.008	journal	July 2019
High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process Brachet, Jean-Christophe; Rouesne, Elodie; Ribis, Joël Corrosion Science, Vol. 167 https://doi.org/10.1016/j.corsci.2020.108537	journal	May 2020
A review on hydrogen generation, explosion, and mitigation during severe accidents in light water nuclear reactors Gharari, R.; Kazeminejad, H.; Mataji Kojouri, N. International Journal of Hydrogen Energy, Vol. 43, Issue 4 https://doi.org/10.1016/j.ijhydene.2017.11.174	journal	January 2018
Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions Ott, L. J.; Robb, K. R.; Wang, D. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.052	journal	May 2014
Accident tolerant fuels for LWRs: A perspective Zinkle, S. J.; Terrani, K. A.; Gehin, J. C. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.005	journal	May 2014
Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions Park, Dong Jun; Kim, Hyun Gil; Jung, Yang Il Journal of Nuclear Materials, Vol. 482 https://doi.org/10.1016/j.jnucmat.2016.10.021	journal	December 2016
Accident tolerant fuel cladding development: Promise, status, and challenges Terrani, Kurt A. Journal of Nuclear Materials, Vol. 501 https://doi.org/10.1016/j.jnucmat.2017.12.043	journal	April 2018
HRTEM and chemical study of an ion-irradiated chromium/zircaloy-4 interface Wu, A.; Ribis, J.; Brachet, J. -C. Journal of Nuclear Materials, Vol. 504 https://doi.org/10.1016/j.jnucmat.2018.01.029	journal	June 2018
Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors Brachet, Jean-Christophe; Idarraga-Trujillo, Isabel; Flem, Marion Le Journal of Nuclear Materials, Vol. 517 https://doi.org/10.1016/j.jnucmat.2019.02.018	journal	April 2019
Effect of surface characteristics and environmental aging on wetting of Cr-coated Zircaloy-4 accident tolerant fuel cladding material Umretiya, Rajnikant V.; Vargas, Santiago; Galeano, Diana Journal of Nuclear Materials, Vol. 535 https://doi.org/10.1016/j.jnucmat.2020.152163	journal	July 2020
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
Development and testing of multicomponent fuel cladding with enhanced accidental performance Krejčí, Jakub; Kabátová, Jitka; Manoch, František Nuclear Engineering and Technology, Vol. 52, Issue 3 https://doi.org/10.1016/j.net.2019.08.015	journal	March 2020
Influence of the wet-well nodalization of a BWR3 Mark I on the containment thermal-hydraulic response during an SBO accident Herranz, Luis E.; Fontanet, Joan; Fernández, Elena Nuclear Engineering and Design, Vol. 295 https://doi.org/10.1016/j.nucengdes.2015.09.031	journal	December 2015
Modification of MELCOR for severe accident analysis of candidate accident tolerant cladding materials Merrill, Brad J.; Bragg-Sitton, Shannon M.; Humrickhouse, Paul W. Nuclear Engineering and Design, Vol. 315 https://doi.org/10.1016/j.nucengdes.2017.02.021	journal	April 2017
Current status of materials development of nuclear fuel cladding tubes for light water reactors Duan, Zhengang; Yang, Huilong; Satoh, Yuhki Nuclear Engineering and Design, Vol. 316 https://doi.org/10.1016/j.nucengdes.2017.02.031	journal	May 2017
Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation Sweet, R. T.; George, N. M.; Maldonado, G. I. Nuclear Engineering and Design, Vol. 328 https://doi.org/10.1016/j.nucengdes.2017.11.043	journal	March 2018
System code evaluation of near-term accident tolerant claddings during boiling water reactor short-term and long-term station blackout accidents Wu, Xu; Shirvan, Koroush Nuclear Engineering and Design, Vol. 356 https://doi.org/10.1016/j.nucengdes.2019.110362	journal	January 2020
Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out Feng, Tangtao; Wang, Jun; Zhou, Yimin Nuclear Engineering and Design, Vol. 363 https://doi.org/10.1016/j.nucengdes.2020.110678	journal	July 2020
Pellet-cladding mechanical interaction analysis of Cr-coated Zircaloy cladding Qi, Feipeng; Liu, Zhenhai; Li, Quan Nuclear Engineering and Design, Vol. 367 https://doi.org/10.1016/j.nucengdes.2020.110792	journal	October 2020
Accident tolerant fuels (FeCrAl Cladding & Coating) performance analysis in Boiling Water Reactor (BWR) by the MELCOR 1.8.6 UDGC Wang, Jun; Dailey, Ryan; Guo, Zhehua Nuclear Engineering and Design, Vol. 371 https://doi.org/10.1016/j.nucengdes.2020.110974	journal	January 2021
Neutronic evaluation of coating and cladding materials for accident tolerant fuels Younker, Ian; Fratoni, Massimiliano Progress in Nuclear Energy, Vol. 88 https://doi.org/10.1016/j.pnucene.2015.11.006	journal	April 2016
Effect of pulse current and coating thickness on the microstructure and FCCI resistance of electroplated chromium on HT9 steel cladding Yeo, Sunghwan; Kim, Jun Hwan; Yun, Hee Soo Surface and Coatings Technology, Vol. 389 https://doi.org/10.1016/j.surfcoat.2020.125652	journal	May 2020
Potential Recovery Actions from a Severe Accident in a PWR: MELCOR Analysis of a Station Blackout Scenario Wang, J.; Jo, H. J.; Corradini, M. L. Nuclear Technology, Vol. 204, Issue 1 https://doi.org/10.1080/00295450.2018.1464838	journal	June 2018
Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings Tang, Chongchong; Stueber, Michael; Seifert, Hans Juergen Corrosion Reviews, Vol. 35, Issue 3 https://doi.org/10.1515/corrrev-2017-0010	journal	August 2017
Modifications to MELCOR 1.8.6 for modeling Accident Tolerant Fuel in Boiling Water Reactors Humrickhouse, Paul W.; Merrill, Brad J. https://doi.org/10.2172/1495186	report	August 2018

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