Long term impact of KOH on Zry-4 fuel cladding

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F12%3A%230000723" target="_blank" >RIV/26722445:_____/12:#0000723 - isvavai.cz</a>

Result on the web

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DOI - Digital Object Identifier

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Result language

angličtina

Original language name

Long term impact of KOH on Zry-4 fuel cladding

Original language description

NPP Temelín is a first VVER reactor type, where the Russian reactor design meets the American fuel design. Since the NPP?s startup in 2002, the hexagonal fuel assemblies VVantage-6 with Zry-4 cladding from Westinghouse fuel vendor have been used. While the VVER primary water chemistry is boric acid-KOH based, Zry-4 and ZIRLOTM alloys are more often used in the western PWR where the LiOH water chemistry is used. Therefore, the fuel vendor was performing post irradiation inspections of the fuel assembliesas an additional proof of PWR material compatibility in VVER water chemistry. Research Centre Řež as a daughter company of Nuclear Institute Rez has been participating on the post irradiation inspection program at NPP Temelín since 2009. This program isperforming mostly like the independent support for the fuel inspections and repair. During these inspections large amount of data was measured and used as a feedback to the fuel vendor and to the fuel operator as well. Oxide measurements

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

JF - Nuclear energy

OECD FORD branch

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Project

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Continuities

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Publication year

2012

Confidentiality

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

Article name in the collection

NPC 2012: Nuclear Plant Chemistry Conference

ISBN

978-2-9516195-2-4

ISSN

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e-ISSN

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Number of pages

8

Pages from-to

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Publisher name

SFEN

Place of publication

Paris

Event location

Paris

Event date

Jan 1, 2012

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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