Introduction of the temelin irradiated cladding project - TIRCLAD 1

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F20%3A00340301" target="_blank" >RIV/68407700:21340/20:00340301 - isvavai.cz</a>

Alternative codes found

RIV/26722445:_____/19:N0000130

Result on the web

<a href="http://globaltopfuel.ans.org/" target="_blank" >http://globaltopfuel.ans.org/</a>

DOI - Digital Object Identifier

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Result language

angličtina

Original language name

Introduction of the temelin irradiated cladding project - TIRCLAD 1

Original language description

The paper presents an overview of an ongoing long-term project focused on in-pile testing of Zr-based materials that has been initiated in 2012 in the Czech Republic. In cooperation with several Czech and Russian organizations, the materials are being irradiated at the Temelin NPP in VVER-1000 core and two irradiated batches have already been transported to UJV Rez and Research Center Rez for extensive post-irradiation evaluation. The project is implemented on the background of a large material research program sponsored by JSC Tvel and CEZ utility, but it is fully independently implemented in the Czech Republic by Alvel and its partners (ČEZ, Škoda Nuclear Machinery, UJP Praha, UJV, CVŘ). The samples that are under irradiation are made of E110 (Zr1%Nb) alloy that has been used for decades as a nuclear fuel cladding material in VVER reactors. First, reference non-irradiated materials have been studied to develop methodologies, determine initial states, mechanical behavior and as-received microstructure. Later, six batches of samples will be studied over time with increasing neutron dose of every batch. The final irradiation damage of the last sixth batch corresponds to the damage of nuclear pins irradiated up to 85 GWd/tHM. The material assemblies are fully compatible with the VVER-1000 fuel design and can be easily transported by a fuel handling machine between fuel assemblies in the core and in the spent fuel pool. There are several material properties that have been studied including creep, mechanical behavior, chemical analysis, microstructural analysis, nanoindentation, morphology etc. The main objectives of the project include evaluation of materials’ microstructural and bulk properties and the derivation of dose- and temperature-dependent correlations that can be implemented into FEM and fuel performance codes to support licensing of advanced fuel designs.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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OECD FORD branch

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

Project

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Continuities

V - Vyzkumna aktivita podporovana z jinych verejnych zdroju

Publication year

2020

Confidentiality

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

Article name in the collection

Global/Top Fuel 2019: International Nuclear Fuel Cycle Conference/Light Water Reactor Fuel Performance Conference

ISBN

978-0-89448-771-2

ISSN

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e-ISSN

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Number of pages

6

Pages from-to

1119-1124

Publisher name

American Nuclear Society

Place of publication

La Grande Park, Illinois

Event location

Seattle, WA

Event date

Sep 22, 2019

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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