Polycrystalline diamond coating protects Zr cladding surface against corrosion in water-cooled nuclear reactors: Nuclear fuel durability enhancement

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

Polycrystalline diamond coating protects Zr cladding surface against corrosion in water-cooled nuclear reactors: Nuclear fuel durability enhancement

Popis výsledku v původním jazyce

In this chapter we demonstrate a new strategy for the protection of zirconium (Zr) nuclear fuel cladding material by composite polycrystalline diamond (PCD) layers against corrosion in water-cooled nuclear reactors. We show that Zr alloy surfaces can be effectively protected against oxygen and hydrogen uptake at both accident and working temperatures in water-cooled nuclear reactor environments by coating the Zr surface with PCD layers grown in a microwave plasma chemical vapour deposition apparatus. This composition enables PCD layers to have suitable thermal expansion over a wide range of temperatures leading to no delamination. A key requirement is effective protection of Zr alloy surfaces against oxidation and hydration under standard operating conditions (360 °C). Oxidation of PCD-coated Zr alloysurfaces after more than 100 days in 360 °C hot water was significantly decreased (35-55%) compared with that of unprotected Zr alloy processed under the same conditions.n

Název v anglickém jazyce

Polycrystalline diamond coating protects Zr cladding surface against corrosion in water-cooled nuclear reactors: Nuclear fuel durability enhancement

Popis výsledku anglicky

In this chapter we demonstrate a new strategy for the protection of zirconium (Zr) nuclear fuel cladding material by composite polycrystalline diamond (PCD) layers against corrosion in water-cooled nuclear reactors. We show that Zr alloy surfaces can be effectively protected against oxygen and hydrogen uptake at both accident and working temperatures in water-cooled nuclear reactor environments by coating the Zr surface with PCD layers grown in a microwave plasma chemical vapour deposition apparatus. This composition enables PCD layers to have suitable thermal expansion over a wide range of temperatures leading to no delamination. A key requirement is effective protection of Zr alloy surfaces against oxidation and hydration under standard operating conditions (360 °C). Oxidation of PCD-coated Zr alloysurfaces after more than 100 days in 360 °C hot water was significantly decreased (35-55%) compared with that of unprotected Zr alloy processed under the same conditions.n

Druh

C - Kapitola v odborné knize

CEP obor

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OECD FORD obor

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

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2018

Kód důvěrnosti údajů

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

Název knihy nebo sborníku

Advanced Coating Materials

ISBN

978-1119407560

Počet stran výsledku

33

Strana od-do

123-156

Počet stran knihy

546

Název nakladatele

Wiley-Scrivener

Místo vydání

Beverly

Kód UT WoS kapitoly

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