Assessment of material properties by lateral compression testing in nuclear grade fuel claddings

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000139" target="_blank" >RIV/26722445:_____/18:N0000139 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Assessment of material properties by lateral compression testing in nuclear grade fuel claddings

Popis výsledku v původním jazyce

Claddings act as barriers against fission products release throughout the NPP operation and spent-fuel storage. During the reactor operation and in particular for fast reactors, claddings are subjected to aggressive conditions caused by mechanical stresses at elevated temperatures, corrosion and neutron radiation that will reduce their mechanical strength. There is only very limited data on the evolution of mechanical properties after irradiation due to cost, difficulty of tests on irradiated cladding tubes and lack of standards for testing. There is therefore a need to develop simple, reproducible way to test mechanically irradiated tube sections. Fuel cladding mechanical properties can be estimated by a number of testing techniques and evaluating methodologies. To date there is no standard for testing of fuel claddings due to their geometrical constrains, i.e. tubular product form (approx. 7mm – OD) with thin walls (approx. 0.6 mm). In this work, 24% and 46% cold-worked materials were compressed at room temperature, 300oC, 500oC and 700oC, respectively. Further mathematical analysis and data processing were developed to properly interpret the load-deflection curves. The results show that there were two types of behavior of load-deflection curves, load of the 46% cold-worked materials tested at 300oC and 500oC declined after reaching certain displacement which were in contrast to all the others test conditions. On the other hand, 46% cold-worked materials generally demonstrated higher collapse load among all the test temperatures except those were tested at 700oC. These results might relate to the microstructure differences caused by the different amounts of cold-worked in the materials.

Název v anglickém jazyce

Assessment of material properties by lateral compression testing in nuclear grade fuel claddings

Popis výsledku anglicky

Claddings act as barriers against fission products release throughout the NPP operation and spent-fuel storage. During the reactor operation and in particular for fast reactors, claddings are subjected to aggressive conditions caused by mechanical stresses at elevated temperatures, corrosion and neutron radiation that will reduce their mechanical strength. There is only very limited data on the evolution of mechanical properties after irradiation due to cost, difficulty of tests on irradiated cladding tubes and lack of standards for testing. There is therefore a need to develop simple, reproducible way to test mechanically irradiated tube sections. Fuel cladding mechanical properties can be estimated by a number of testing techniques and evaluating methodologies. To date there is no standard for testing of fuel claddings due to their geometrical constrains, i.e. tubular product form (approx. 7mm – OD) with thin walls (approx. 0.6 mm). In this work, 24% and 46% cold-worked materials were compressed at room temperature, 300oC, 500oC and 700oC, respectively. Further mathematical analysis and data processing were developed to properly interpret the load-deflection curves. The results show that there were two types of behavior of load-deflection curves, load of the 46% cold-worked materials tested at 300oC and 500oC declined after reaching certain displacement which were in contrast to all the others test conditions. On the other hand, 46% cold-worked materials generally demonstrated higher collapse load among all the test temperatures except those were tested at 700oC. These results might relate to the microstructure differences caused by the different amounts of cold-worked in the materials.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

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

Projekt

<a href="/cs/project/LQ1603" target="_blank" >LQ1603: Výzkum pro SUSEN</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 statě ve sborníku

The 8th International Conference & Workshop REMOO–2018 May 29-31, 2018

ISBN

978-3-9818275-6-9

ISSN

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e-ISSN

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Počet stran výsledku

5

Strana od-do

1-5

Název nakladatele

Get It Published

Místo vydání

Erlangen, Germany

Místo konání akce

Venice, Italy

Datum konání akce

29. 5. 2018

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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