Validation of the neutron lead transport for fusion applications
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F22%3AN0000069" target="_blank" >RIV/26722445:_____/22:N0000069 - isvavai.cz</a>
Result on the web
<a href="https://www.sciencedirect.com/science/article/pii/S1738573321005428" target="_blank" >https://www.sciencedirect.com/science/article/pii/S1738573321005428</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.net.2021.09.002" target="_blank" >10.1016/j.net.2021.09.002</a>
Alternative languages
Result language
angličtina
Original language name
Validation of the neutron lead transport for fusion applications
Original language description
Lead is an important material, both for fusion or fission reactors. The cross sections of natural lead should be validated because lead is a main component of lithium-lead modules suggested for fusion power plants and it directly affects the crucial variable, tritium breeding ratio. The presented study discusses a validation of the lead transport libraries by dint of the activation of carefully selected activation samples. The high emission standard Cf-252 neutron source was used as a neutron source for the presented validation experiment. In the irradiation setup, the samples were placed behind 5 and 10 cm of the lead material. Samples were measured using a gamma spectrometry to infer the reaction rate and compared with MCNP6 calculations using ENDF/B-VIII.0 lead cross sections. The experiment used validated IRDFF-II dosimetric reactions to validate lead cross sections, namely (19)7Au(n, 2n)Au-196, Ni-58(n,p)Co-58, Nb-93(n, 2n)Nb-92m, In-115(n,n')(115)mIn, In-115(n,gamma)(116)mIn, Au-197(n,gamma)Au-198 and Cu-63(n,gamma)Cu-64 reactions. The threshold reactions agree reasonably with calculations; however, the experimental data suggests a higher thermal neutron flux behind lead bricks. The paper also suggests Cf-252 isotropic source as a valuable tool for validation of some cross-sections important for fusion applications, i.e. reactions on structural materials, e.g. Cu, Pb, etc.
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
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
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Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2022
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 Technology
ISSN
1738-5733
e-ISSN
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Volume of the periodical
54
Issue of the periodical within the volume
3
Country of publishing house
KR - KOREA, REPUBLIC OF
Number of pages
6
Pages from-to
959-964
UT code for WoS article
000766667500001
EID of the result in the Scopus database
2-s2.0-85114690878