Polycrystalline Diamond Coating Protects Zr Cladding Surface Against Corrosion in Water-cooled Nuclear Reactors: Nuclear Fuel Durability Enhancement

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21730%2F18%3A00329816" target="_blank" >RIV/68407700:21730/18:00329816 - isvavai.cz</a>

Výsledek na webu

<a href="https://onlinelibrary.wiley.com/doi/abs/10.1002/9781119407652.ch5" target="_blank" >https://onlinelibrary.wiley.com/doi/abs/10.1002/9781119407652.ch5</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1002/9781119407652.ch5" target="_blank" >10.1002/9781119407652.ch5</a>

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. The composition of PCD is not homogeneous – it contains diamond sp3-hybridized phase (96%) and soft sp2-hybridized C phase. 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. Also at high temperatures (1100 °C), i.e. accident conditions, PCD layers may serve as passive elements for nuclear safety. PCD-protected Zr alloys also exhibited lower hydrogen concentrations than unprotected samples under all investigated conditions; in particular at accident conditions. After ion beam irradiation (10 dpa, 3 MeV Fe2+) PCD layers show satisfactory structural integrity with both sp3 and sp2 carbon phases present.

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. The composition of PCD is not homogeneous – it contains diamond sp3-hybridized phase (96%) and soft sp2-hybridized C phase. 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. Also at high temperatures (1100 °C), i.e. accident conditions, PCD layers may serve as passive elements for nuclear safety. PCD-protected Zr alloys also exhibited lower hydrogen concentrations than unprotected samples under all investigated conditions; in particular at accident conditions. After ion beam irradiation (10 dpa, 3 MeV Fe2+) PCD layers show satisfactory structural integrity with both sp3 and sp2 carbon phases present.

Druh

C - Kapitola v odborné knize

CEP obor

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OECD FORD obor

10304 - Nuclear physics

Projekt

<a href="/cs/project/TE01020455" target="_blank" >TE01020455: Centrum pokročilých jaderných technologií (CANUT)</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

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

978-1-119-40763-8

Počet stran výsledku

34

Strana od-do

123-156

Počet stran knihy

546

Název nakladatele

J. Wiley

Místo vydání

New York

Kód UT WoS kapitoly

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