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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

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

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

Result continuities

  • Project

  • 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

  • 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