Title: The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts

Abstract

Accident tolerant fuel claddings seek to improve safety margins during loss-of-coolant accident (LOCA) scenarios by reducing cladding steam oxidation rates, hydrogen production, delaying or mitigating cladding burst, and reducing cladding deformation. After rapid and extensive progress in recent years, Cr coated Zr-based alloys, ferritic FeCrAl, and SiC/SiC ceramic matrix composites (CMCs) have emerged as the most promising cladding concepts, but there are few studies comparing the accident tolerance of all three concepts simultaneously. Here, in this study, LOCA burst testing has been conducted on Cr high impulse power magnetron sputtered Zry-4 (Cr/Zry-4), C26M (FeCrAl), and SiC/SiC SiGA (CMC). Experimental observations indicate Cr/Zry-4 burst at higher temperatures than Zry-4 however the effectiveness of the coating on mitigating ZrO₂ formation via Cr₂O₃ formation depended on physical proximity to the burst opening. No dramatic improvement in diametrical strain nor opening geometry was observed. C26M burst at higher temperatures than Zry-4 at lower pressures, exhibiting small amounts of strain and smaller openings, and formed slow-growing Al₂O₃ regardless of location. The CMCs did not burst or show any macroscopic signs of deformation, all the way up to an internal cladding pressure of 15.2 MPa. High temperature expanding Nb plug testing indicated that CMC room temperaturemore » strength may persist up to 1650°C, with an approximately 40% loss of strength at 1900°C. CMC steam oxidation was also compared to reference chemically vapor deposited SiC up to 1700°C, and CMCs were found to oxidize at slightly accelerated rates that were still orders of magnitude lower than bare Zry-4. Projected H₂ generation during LOCA burst testing showed that when accounting for cladding burst exposing inner diameters to steam, Cr coated Zry-4 reduced H₂ generation by a factor of two compared with bare Zry-4, while both C26M and SiC/SiC reduced H₂ generation by orders of magnitude relative to bare Zry-4.« less

Authors:

Kane, K.  ^[1];

• Search DOE PAGES for author "Kane, K."
• Search DOE PAGES for ORCID "0000-0003-3647-3419"

Bell, Sam ^[2]; Capps, Nathan ^[3]; Garrison, Ben ^[3]; Shapovalov, K. ^[4]; Jacobsen, G. ^[4]; Deck, C.  ^[4];

• Search DOE PAGES for author "Deck, C."
• Search DOE PAGES for ORCID "0000-0002-8365-3167"

Graening, Tim Seibert ^[3]; Koyanagi, Takaaki  ^[3];

• Search DOE PAGES for author "Koyanagi, Takaaki"
• Search DOE PAGES for ORCID "0000-0001-7272-4049"

Massey, Caleb ^[3]

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+ Show Author Affiliations

1. Johns Hopkins Univ., Baltimore, MD (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
2. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
3. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
4. General Atomics, San Diego, CA (United States)

Publication Date:

Tue Nov 15 00:00:00 EST 2022

Research Org.:

Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:

USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign

OSTI Identifier:

1997815

Grant/Contract Number:  

AC05-00OR22725

Resource Type:

Accepted Manuscript

Journal Name:

Journal of Nuclear Materials

Additional Journal Information:

Journal Volume: 574; Journal Issue: 1; Journal ID: ISSN 0022-3115

Publisher:

Elsevier

Country of Publication:

United States

Language:

English

Subject:

36 MATERIALS SCIENCE; LOCA; Steam oxidation; Burst testing; Accident tolerant fuel cladding; Ceramic matrix; Composite