Measurement of the selected spectral averaged cross sections in a radial channel of the VR-1 reactor
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000043" target="_blank" >RIV/26722445:_____/19:N0000043 - isvavai.cz</a>
Nalezeny alternativní kódy
RIV/68407700:21340/19:00332404
Výsledek na webu
<a href="https://www.sciencedirect.com/science/article/abs/pii/S0969804319306396" target="_blank" >https://www.sciencedirect.com/science/article/abs/pii/S0969804319306396</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.apradiso.2019.108855" target="_blank" >10.1016/j.apradiso.2019.108855</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Measurement of the selected spectral averaged cross sections in a radial channel of the VR-1 reactor
Popis výsledku v původním jazyce
The spectral averaged cross section is an important quantity used in a validation of nuclear cross section. When the cross sections are averaged over the neutron standard field (Cf-252(s,f) or U-235(n,f) neutron spectrum), they can be used for tuning of evaluations. This kind of quantities is very useful because the data in integral measurements can be determined with a significantly smaller uncertainties than the standard differential data. The experiment was aimed at the spectral average cross sections measurement and was performed in a radial channel of VR-1 reactor (with fuel enrichment 19.75 wt %). The results are in a good agreement within the uncertainties with a previous measurements in LR-0 reactor (with fuel enrichment 3.3 wt %), thus it supports the hypothesis that even significant amount of U-238(n,f) neutrons in the LR-0 reactor spectrum does not have a significant influence. The derived spectral averaged cross sections are as follows: 0.1709 +/- 0.0115 mb for Y-89(n,2n), 10.738 +/- 0.719 mb for Ti-46(n,p), 17.896 +/- 1.181 mb for Ti-47(n,p), 0.294 +/- 0.02 mb for Ti-48(n,p), 72.994 +/- 4.964 mb for Fe-54(n,p), 0.528 +/- 0.036 mb for Cu-63(n,a), 0.444 +/- 0.029 mb for Nb-93(n,2n)Nb-92* and 0.239 +/- 0.016 mb for Ni-58(n,x)Co-57.
Název v anglickém jazyce
Measurement of the selected spectral averaged cross sections in a radial channel of the VR-1 reactor
Popis výsledku anglicky
The spectral averaged cross section is an important quantity used in a validation of nuclear cross section. When the cross sections are averaged over the neutron standard field (Cf-252(s,f) or U-235(n,f) neutron spectrum), they can be used for tuning of evaluations. This kind of quantities is very useful because the data in integral measurements can be determined with a significantly smaller uncertainties than the standard differential data. The experiment was aimed at the spectral average cross sections measurement and was performed in a radial channel of VR-1 reactor (with fuel enrichment 19.75 wt %). The results are in a good agreement within the uncertainties with a previous measurements in LR-0 reactor (with fuel enrichment 3.3 wt %), thus it supports the hypothesis that even significant amount of U-238(n,f) neutrons in the LR-0 reactor spectrum does not have a significant influence. The derived spectral averaged cross sections are as follows: 0.1709 +/- 0.0115 mb for Y-89(n,2n), 10.738 +/- 0.719 mb for Ti-46(n,p), 17.896 +/- 1.181 mb for Ti-47(n,p), 0.294 +/- 0.02 mb for Ti-48(n,p), 72.994 +/- 4.964 mb for Fe-54(n,p), 0.528 +/- 0.036 mb for Cu-63(n,a), 0.444 +/- 0.029 mb for Nb-93(n,2n)Nb-92* and 0.239 +/- 0.016 mb for Ni-58(n,x)Co-57.
Klasifikace
Druh
J<sub>imp</sub> - Článek v periodiku v databázi Web of Science
CEP obor
—
OECD FORD obor
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Návaznosti výsledku
Projekt
Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Ostatní
Rok uplatnění
2019
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
Applied Radiation and Isotopes
ISSN
0969-8043
e-ISSN
—
Svazek periodika
154
Číslo periodika v rámci svazku
December
Stát vydavatele periodika
GB - Spojené království Velké Británie a Severního Irska
Počet stran výsledku
7
Strana od-do
1-7
Kód UT WoS článku
000498291900009
EID výsledku v databázi Scopus
2-s2.0-85070815748