Neutronic Analysis of the Candidate Multi-Layer Cladding Materials With Enhanced Accident Tolerance for Wwer Reactors

Novák, Ondřej; Ševeček, Martin

doi:10.14311/app.2018.14.0027

Cited by 5 publications

(3 citation statements)

References 12 publications

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“…The calculations also showed that metallic chromium had more stopping power and less total induced displacement damage in comparison with the Zr-based alloy. It is worth mentioning that, the calculated minimum thickness of Cr is not expected to significantly affect the reactor reactivity and would probably results in less than a 1% decrease in fuel cycle length according to calculations made by Novak and Sevecek [21]. On the other hand, applying an inner surface thin film will provide protection for the fuel cladding against the internal corrosion and SCC, supporting the ability to increase fuel burnup during reactor operation as well as contributing to improved spent fuel management and waste minimization.…”

Section: Discussionmentioning

confidence: 84%

On the Use of Chromium Coating for Inner-Side Fuel Cladding Protection: Thickness Identification Based on Fission Fragments Implantation and Damage Profile

2021

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Inner-side coatings have been proposed as a complementary solution within the accident tolerant fuel (ATF) framework, to provide enhanced protection for the nuclear fuel cladding. Unlike external surface, the degradation of irradiated internal cladding surface has not been studied extensively. Fission fragments produced during the fission of nuclear fuel is one of the key players in this degradation. This study aimed to estimate the minimum thickness of the thin chromium film, required to protect the inner side of the nuclear fuel cladding. The approach used is based on a set of calculations, of Ion ranges and damage profiles, for a group fission fragments, using the TRIM code. The calculation results were verified by comparison with the experimental data associated with the phenomena of the inner cladding degradation of thermo-releasing elements. The recommended minimum thickness for such a film was found to be 9 microns. Calculations also showed that chromium metal has a greater stopping power compared to the zirconium-based alloy E110, which indicates an increased ability of chromium to withstand exposure to energetic fission fragments during reactor operation.

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Section: Discussionmentioning

confidence: 84%

On the Use of Chromium Coating for Inner-Side Fuel Cladding Protection: Thickness Identification Based on Fission Fragments Implantation and Damage Profile

2021

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“…However, the thickness of protective coatings on Zr-based claddings should be limited to avoid a significant impact on the neutron transport in LWRs. For example, for Cr coatings, thickness should not exceed 30 µm, so that the reduction of fuel cycle life would be limited to 1% [167].…”

Section: Microstructure and Thickness Of The Coatingsmentioning

confidence: 99%

Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings

et al. 2021

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Zirconium-based alloys have served the nuclear industry for several decades due to their acceptable properties for nuclear cores of light water reactors (LWRs). However, severe accidents in LWRs have directed research and development of accident tolerant fuel (ATF) concepts that aim to improve nuclear fuel safety during normal operation, operational transients and possible accident scenarios. This review introduces the latest results in the development of protective coatings for ATF claddings based on Zr alloys, involving their behavior under normal and accident conditions in LWRs. Great attention has been paid to the protection and oxidation mechanisms of coated claddings, as well as to the mutual interdiffusion between coatings and zirconium alloys. An overview of recent developments in barrier coatings is introduced, and possible barrier layers and structure designs for suppressing mutual diffusion are proposed.

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“…Coating slows down the absorption rate of hydrogen as well as the process of oxidation in normal operation [4][5][6]. Moreover, calculations show that a thin layer of Cr entails only a minor decrease in a fuel cycle length [7]. Regarding the accident conditions, the positive impact of Cr coating has been presented.…”

Section: Introductionmentioning

confidence: 99%

Experimental Study of Damaged Cr-Coated Fuel Cladding in Post-Accident Conditions

Cervenka

Krejčí

Cvrček

et al. 2020

APP

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To enhance the safety of nuclear power, the focus of researchers all around the world has recently mainly objected on the development of Accident Tolerant Fuels. Especially the Chromium coating of current Zirconium based cladding has been widely suggested and discussed for its immense positive effect on overall cladding properties. Nevertheless, it was observed that during the first stage of the Loss of Coolant Accident, cracks appear in the Cr coating due to its inability to tolerate higher plastic strain. Therefore, experimental methodology used in this article focuses on testing fuel cladding with damaged Cr coating after the high-temperature transient. The impact of cracks on degradation of cladding mechanical properties was observed using optical microscopy, ring compression test, microhardness, and evaluating hydrogen content and weight gain.

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Neutronic Analysis of the Candidate Multi-Layer Cladding Materials With Enhanced Accident Tolerance for Wwer Reactors

Cited by 5 publications

References 12 publications

On the Use of Chromium Coating for Inner-Side Fuel Cladding Protection: Thickness Identification Based on Fission Fragments Implantation and Damage Profile

On the Use of Chromium Coating for Inner-Side Fuel Cladding Protection: Thickness Identification Based on Fission Fragments Implantation and Damage Profile

Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings

Experimental Study of Damaged Cr-Coated Fuel Cladding in Post-Accident Conditions

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