The Measurement of Helium Leakages through Flange Gaskets for Gas-Cooled Fast Reactors
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F60461373%3A22320%2F20%3A43920252" target="_blank" >RIV/60461373:22320/20:43920252 - isvavai.cz</a>
Result on the web
<a href="https://www.sciencedirect.com/journal/nuclear-engineering-and-design/vol/367/suppl/C" target="_blank" >https://www.sciencedirect.com/journal/nuclear-engineering-and-design/vol/367/suppl/C</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.nucengdes.2020.110783" target="_blank" >10.1016/j.nucengdes.2020.110783</a>
Alternative languages
Result language
angličtina
Original language name
The Measurement of Helium Leakages through Flange Gaskets for Gas-Cooled Fast Reactors
Original language description
The study deals with the development of a method that would reliably determine the tightness of flange joints of the helium circuit of a gas-cooled fast reactor (GFR). The proposed procedure and equipment enable the parallel measurement of the helium leakage from a high-pressure cell and He contamination in the cell by the diffusion of gases from the ambient atmosphere against the pressure gradient. The self-designed apparatus is constructed for the performance of long-term tests of both parameters (i.e. both He leakage and its contamination) at a temperature of 400 °C and a pressure of 20 MPa. Nevertheless, the construction limits of the device at which the measurement can be safely carried out are 450 °C / 35 MPa. The permanent gases diffusing into helium through the gasket were analyzed by a gas chromatograph with a PDHID detector, whereas the He leakage was determined using a high-sensitivity TCD. The article presents continuous results of tests carried out at ambient temperature. The procedures for data measurement and evaluation are demonstrated on one selected type of gasket with the inner diameter of 44 mm, the outer diameter of 79 mm and the thickness of 14.2 mm.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20704 - Energy and fuels
Result continuities
Project
<a href="/en/project/TH02020578" target="_blank" >TH02020578: Joint leakage optimization and determination and helium recovery from coolant leakage in generation four helium cooled reactors</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2020
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Nuclear Engineering and Design
ISSN
0029-5493
e-ISSN
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Volume of the periodical
367
Issue of the periodical within the volume
october
Country of publishing house
US - UNITED STATES
Number of pages
10
Pages from-to
110783
UT code for WoS article
000569400400003
EID of the result in the Scopus database
2-s2.0-85089244475