Polycrystalline Diamond and Cr Double Coatings Protect Zr Nuclear Fuel Tubes Against Accidental Temperature Corrosion in Water-Cooled Nuclear Reactors

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F24%3A00381168" target="_blank" >RIV/68407700:21340/24:00381168 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21730/24:00381168

Výsledek na webu

<a href="https://doi.org/10.1007/978-3-031-45534-6_4" target="_blank" >https://doi.org/10.1007/978-3-031-45534-6_4</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1007/978-3-031-45534-6_4" target="_blank" >10.1007/978-3-031-45534-6_4</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Polycrystalline Diamond and Cr Double Coatings Protect Zr Nuclear Fuel Tubes Against Accidental Temperature Corrosion in Water-Cooled Nuclear Reactors

Popis výsledku v původním jazyce

The chapter proposes a new strategy for protecting Zr alloy nuclear fuel tubes from accidental temperature corrosion in water-cooled nuclear reactors. Protection of the zirconium alloy fuel tubes against accidental temperature corrosion in water-cooled nuclear reactors is important for the safety and efficiency of nuclear power plants, as corrosion in fuel tubes can lead to accidents and reduce the lifespan of the fuel. The new strategy of zirconium alloy fuel tubes from accidental temperature corrosion presented here involves a combination of polycrystalline diamond (PCD) and chromium (Cr) layers. The PCD layer prevents direct interaction between the Zr alloy surface and the hot water environment of the reactor and releases carbon into the underlying Zr material to alter conditions for the penetration of oxygen and hydrogen. The Cr layer helps to reduce corrosion by forming carbides and improving adhesion of the coatings to the Zr alloy substrate. The chapter also discusses the importance of the order of the Cr and PCD layers and the parameters affecting the corrosion of coated ZIRLO tubes. Overall, this new strategy has the potential to significantly improve nuclear safety.

Název v anglickém jazyce

Polycrystalline Diamond and Cr Double Coatings Protect Zr Nuclear Fuel Tubes Against Accidental Temperature Corrosion in Water-Cooled Nuclear Reactors

Popis výsledku anglicky

The chapter proposes a new strategy for protecting Zr alloy nuclear fuel tubes from accidental temperature corrosion in water-cooled nuclear reactors. Protection of the zirconium alloy fuel tubes against accidental temperature corrosion in water-cooled nuclear reactors is important for the safety and efficiency of nuclear power plants, as corrosion in fuel tubes can lead to accidents and reduce the lifespan of the fuel. The new strategy of zirconium alloy fuel tubes from accidental temperature corrosion presented here involves a combination of polycrystalline diamond (PCD) and chromium (Cr) layers. The PCD layer prevents direct interaction between the Zr alloy surface and the hot water environment of the reactor and releases carbon into the underlying Zr material to alter conditions for the penetration of oxygen and hydrogen. The Cr layer helps to reduce corrosion by forming carbides and improving adhesion of the coatings to the Zr alloy substrate. The chapter also discusses the importance of the order of the Cr and PCD layers and the parameters affecting the corrosion of coated ZIRLO tubes. Overall, this new strategy has the potential to significantly improve nuclear safety.

Druh

O - Ostatní výsledky

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

—

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2024

Kód důvěrnosti údajů

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