Validation of the neutron lead transport for fusion applications

Kód výsledku v 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>

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

Validation of the neutron lead transport for fusion applications

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Validation of the neutron lead transport for fusion applications

Popis výsledku anglicky

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.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

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

Projekt

—

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2022

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

Nuclear Engineering and Technology

ISSN

1738-5733

e-ISSN

—

Svazek periodika

54

Číslo periodika v rámci svazku

3

Stát vydavatele periodika

KR - Korejská republika

Počet stran výsledku

6

Strana od-do

959-964

Kód UT WoS článku

000766667500001

EID výsledku v databázi Scopus

2-s2.0-85114690878