Review of available literature on the formation and analysis of corrosion layers on fuel coating

Kód výsledku v IS VaVaI

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Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Review of available literature on the formation and analysis of corrosion layers on fuel coating

Popis výsledku v původním jazyce

The investigation into the topic of fuel cladding oxidation within the thermalchemical milieu of nuclear reactors is a fundamental pursuit, underpinning the core tenets of reactor operational efficacy and safety. Particularly, the oxidation dynamics exhibited by crucial fuel cladding materials, notably ZrO2 and ????-Zr(O), bear immense significance in comprehending the intricate interplay between these materials and the rigorous environmental conditions within nuclear reactors. The high temperatures and chemically aggressive surroundings inherent to nuclear reactors impose unique challenges on the materials constituting the fuel cladding. As the primary line of defense encapsulating the nuclear fuel, ZrO2 and ????-Zr(O) undergo a nuanced transformation under these conditions. Unraveling the behavior of these materials is imperative not only from an academic standpoint but more critically for ensuring the robustness and safety of nuclear reactors. A paramount aspect of this task lies in the exploration of the tetragonal phase’s proportion at the interface of fuel cladding materials. The tetragonal phase plays a pivotal role in influencing the mechanical and thermodynamic properties of the materials. A comprehensive understanding of the distribution and prevalence of this phase at the interface is instrumental in discerning the material’s structural integrity, deformation mechanisms, and potential failure modes. To navigate this intricacy, the assimilation of both experimental and calculated data becomes an indispensable methodology. The synergy between empirical observations and theoretical predictions facilitates a nuanced analysis, enabling the determination of the authentic value of the tetragonal fraction at the interface. This analytical precision is crucial for extrapolating meaningful insights into the material behavior within the demanding operational confines of nuclear reactors. Furthermore, the corrosion process is profoundly impacted by factors such as oxide thickness and hydrogen concentration within the oxide layer. The quantification of these parameters is essential for delineating the corrosion kinetics and understanding the underlying mechanisms governing the oxidation of fuel cladding materials. This nuanced understanding not only contributes to the broader scientific discourse but also holds pragmatic implications for the development of predictive models and strategies for corrosion mitigation in nuclear reactor systems. Report CVR-5079.

Název v anglickém jazyce

Review of available literature on the formation and analysis of corrosion layers on fuel coating

Popis výsledku anglicky

The investigation into the topic of fuel cladding oxidation within the thermalchemical milieu of nuclear reactors is a fundamental pursuit, underpinning the core tenets of reactor operational efficacy and safety. Particularly, the oxidation dynamics exhibited by crucial fuel cladding materials, notably ZrO2 and ????-Zr(O), bear immense significance in comprehending the intricate interplay between these materials and the rigorous environmental conditions within nuclear reactors. The high temperatures and chemically aggressive surroundings inherent to nuclear reactors impose unique challenges on the materials constituting the fuel cladding. As the primary line of defense encapsulating the nuclear fuel, ZrO2 and ????-Zr(O) undergo a nuanced transformation under these conditions. Unraveling the behavior of these materials is imperative not only from an academic standpoint but more critically for ensuring the robustness and safety of nuclear reactors. A paramount aspect of this task lies in the exploration of the tetragonal phase’s proportion at the interface of fuel cladding materials. The tetragonal phase plays a pivotal role in influencing the mechanical and thermodynamic properties of the materials. A comprehensive understanding of the distribution and prevalence of this phase at the interface is instrumental in discerning the material’s structural integrity, deformation mechanisms, and potential failure modes. To navigate this intricacy, the assimilation of both experimental and calculated data becomes an indispensable methodology. The synergy between empirical observations and theoretical predictions facilitates a nuanced analysis, enabling the determination of the authentic value of the tetragonal fraction at the interface. This analytical precision is crucial for extrapolating meaningful insights into the material behavior within the demanding operational confines of nuclear reactors. Furthermore, the corrosion process is profoundly impacted by factors such as oxide thickness and hydrogen concentration within the oxide layer. The quantification of these parameters is essential for delineating the corrosion kinetics and understanding the underlying mechanisms governing the oxidation of fuel cladding materials. This nuanced understanding not only contributes to the broader scientific discourse but also holds pragmatic implications for the development of predictive models and strategies for corrosion mitigation in nuclear reactor systems. Report CVR-5079.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

20501 - Materials engineering

Projekt

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Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2023

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů