New experimental device for VHTR structural material testing and helium coolant chemistry investigation - High Temperature Helium Loop in NRI Řež
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F60461373%3A22320%2F12%3A43894746" target="_blank" >RIV/60461373:22320/12:43894746 - isvavai.cz</a>
Alternative codes found
RIV/26722445:_____/12:#0000691 RIV/46356088:_____/12:#0001678
Result on the web
<a href="http://dx.doi.org/10.1016/j.nucengdes.2011.10.045" target="_blank" >http://dx.doi.org/10.1016/j.nucengdes.2011.10.045</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.nucengdes.2011.10.045" target="_blank" >10.1016/j.nucengdes.2011.10.045</a>
Alternative languages
Result language
angličtina
Original language name
New experimental device for VHTR structural material testing and helium coolant chemistry investigation - High Temperature Helium Loop in NRI Řež
Original language description
The High Temperature Helium Loop (HTHL) is an experimental device for simulation of VHTR helium coolant conditions. The purpose of the HTHL is structural materials testing and helium coolant chemistry investigation. In the HTHL pure helium will be used as working medium and its main physical parameters are 7 MPa, max. temperature in the test section 900 °C and flow rate 37.8 kg/h. The HTHL consists of an active channel, the helium purification system, the system of impurities dosage (e.g. CO, CO2, H2, H2O, O2, N2, and CH4) and the helium chemistry monitoring system (sampling and on-line analysis and determination of impurities in the helium flow). The active channel is planned to be placed into the core of the experimental reactor LVR-15 which will serve as a neutron flux source (max. 2.5 x 1018 n/m2 s for fast neutrons). The HTHL is now under construction. Some of its main parts are finished, some are still being produced (active channel internals, etc.), some should be improved to wo
Czech name
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Czech description
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Classification
Type
J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP classification
JF - Nuclear energy
OECD FORD branch
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Result continuities
Project
<a href="/en/project/2A-1TP1%2F100" target="_blank" >2A-1TP1/100: High Temperature Gas Systems.</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>Z - Vyzkumny zamer (s odkazem do CEZ)
Others
Publication year
2012
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
251
Issue of the periodical within the volume
10
Country of publishing house
US - UNITED STATES
Number of pages
5
Pages from-to
203-207
UT code for WoS article
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EID of the result in the Scopus database
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