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; Saux, Matthieu Le; Vandenberghe, V.; Urvoy, Stéphane; Rouesne, Elodie; Guilbert, Thomas; Toffolon-Masclet, Caroline; Tupin, Marc; Phalippou, Christian; Lomello, Fernando; Schuster, Frédéric; Billard, Alain; Velişa, Gihan; Ducros, C.; Sanchette, Frédéric

doi:10.1016/j.jnucmat.2019.02.018

Cited by 259 publications

(131 citation statements)

References 65 publications

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“…However, according to the findings from Terrani et al [46], recent results of LOCA tests on CrN-coated Zr alloy cladding showed that although the CrN coating was well-attached to the matrix without any apparent delamination, the ceramic coating could not maintain the circumferential extension on the ballooning area of the cladding. This yielded the formation of many surface cracks due to inherent brittleness of the ceramic, limiting the ability of the coating to protect the cladding from high-temperature steam oxidation [14], which resulted in a comparable oxidation or bursting behavior of the coated and the uncoated claddings (Figure 4 [46]).…”

Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

“…The mechanical strength of pure Cr does not extensively differ from that of industrial Zr alloys (from room temperature to the cladding's service temperature of approximately 350 • C), and a thin outer Cr coating has a limited effect on the overall mechanical properties of the cladding under normal operating conditions [14,17,69]. Due to the good hardness and strong adhesion of the Cr coating, Cr-coated Zr alloy claddings have shown substantially improved wear resistance compared to uncoated claddings [14,18]. This would greatly reduce the probability of cladding failure due to grid-to-rod vibration and debris friction during reactor operation.…”

Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

“…Since the inception of the ATF concept and its development, many countries have accumulated extensive experience and achievements in the research and development of zirconium alloys with Cr-based coatings [14][15][16][17][18][19][20][21][22][23][24][25]. However, existing literature and reports have not been able to establish a systematic framework.…”

Section: Introductionmentioning

confidence: 99%

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Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

2020

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To cope with the shortcomings of nuclear fuel design exposed during the Fukushima Nuclear Accident, researchers around the world have been directing their studies towards accident-tolerant fuel (ATF), which can improve the safety of fuel elements. Among the several ATF cladding concepts, surface coatings comprise the most promising strategy to be specifically applied in engineering applications in a short period. This review presents a comprehensive introduction to the latest progress in the development of Cr-based surface coatings based on zirconium alloys. Part I of the review is a retrospective look at the application status of zirconium alloy cladding, as well as the development of ATF cladding. Following this, the review focuses on the selection process of ATF coating materials, along with the advantages and disadvantages of the current mainstream preparation methods of Cr-based coatings worldwide. Finally, the characteristics of the coatings obtained through each method are summarized according to some conventional performance evaluations or investigations of the claddings. Overall, this review can help assist readers in getting a thorough understanding of the selection principle of ATF coating materials and their preparation processes.

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Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

Section: Development Of Atf Coating Materialsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

2020

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“…the multilayered chromium-coated clad to achieve an overall higher corrosion resistance at high temperatures compared to an uncoated Zry-4 clad. 30 For our studies, we derived base physical properties for chromium from Ref. 31.…”

Section: Iib Chromium-coated Cladmentioning

confidence: 99%

“…Parameters for the Arrhenius equation of the chromium oxidation by high-temperature steam are 30,32 K T ð Þ ¼ 21:5e…”

Section: Iib Chromium-coated Cladmentioning

confidence: 99%

Risk-Informed Safety Analysis for Accident Tolerant Fuels

Parisi

Mandelli

et al. 2020

Nuclear Science and Engineering

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Accident tolerant fuels (ATFs) are being tested by different nuclear vendors and research organizations, and their introduction into the U.S light water reactor fleet is planned for the second half of the 2020s. Under the framework of the U.S. Department of Energy Light Water Reactor Sustainability (LWRS) Program, as part of the LWRS Risk-Informed Systems Analysis Pathway, research is being conducted at the Idaho National Laboratory (INL) to develop tools and methods that can help the industry to quantify the benefits from adopting ATF technology. In this paper we describe the developed risk-informed methodology including the safety analysis code improvements, and we present some results for selected accident scenarios. The developed methodology combines the INL state-of-the-art deterministic Best Estimate code RELAP5-3D and the probabilistic risk analysis tools RAVEN and SAPHIRE. The analyses are performed on a three-loop pressurized water reactor, simulating station blackout and large-break loss-of-coolant accidents and considering near-term ATFs or iron-chromium-aluminum and chromium-coated clads. Finally, we show how, applying our methodology, the new core damage frequency (CDF) can be assessed. The results indicate that the main benefit in introducing near-term ATFs is a significant reduction in hydrogen production during accident conditions. No significant CDF reduction was found.

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Long‐term high‐temperature steam oxidation behavior of Cr‐coated Zircaloy‐4 alloy for accident tolerant fuel

Xiang

Yang

Chen

et al. 2022

Materials & Corrosion

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The Cr-coated Zircaloy-4 samples were prepared by arc ion plating to enhance the high-temperature oxidation resistance of Zircaloy-4 alloys for accident tolerant fuel claddings. The oxidation tests of the Cr coating were performed under 1473 K steam for 60, 120, and 240 min. The steam oxidation tests indicated that the Cr-coated Zircaloy-4 substrate had excellent hightemperature steam oxidation resistance to protect the fuel cladding from damage for at least 240 min. The weight gains and the thickness of the oxidation scale of the samples were measured to evaluate the oxidation kinetics of the Cr coating in 1473 K steam. In addition, the diffusion and interfacial evolution were analyzed during the oxidation process, and the steam oxidation behaviors of the Cr coatings were also discussed in detail.

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Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors

Cited by 259 publications

References 65 publications

Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

Risk-Informed Safety Analysis for Accident Tolerant Fuels

Long‐term high‐temperature steam oxidation behavior of Cr‐coated Zircaloy‐4 alloy for accident tolerant fuel

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