Studies of (n,xn) cross-sections in Al, Au, Bi, Cu, Fe, I, In, Mg, Ni, Ta, Y, and Zn by the activation method
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F13%3A00205817" target="_blank" >RIV/68407700:21340/13:00205817 - isvavai.cz</a>
Nalezeny alternativní kódy
RIV/61389005:_____/13:00395958
Výsledek na webu
<a href="http://www.sciencedirect.com/science/article/pii/S0168900213007444" target="_blank" >http://www.sciencedirect.com/science/article/pii/S0168900213007444</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.nima.2013.05.133" target="_blank" >10.1016/j.nima.2013.05.133</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Studies of (n,xn) cross-sections in Al, Au, Bi, Cu, Fe, I, In, Mg, Ni, Ta, Y, and Zn by the activation method
Popis výsledku v původním jazyce
The article summarizes series of experiments devoted to studies of (n,xn) cross-sections by the activation method and states numerical values of measured cross-sections. The activation samples are used to measure neutron flux produced during acceleratordriven system studies. The threshold (n,xn) reactions are used but experimental cross-section data of such reactions are mostly not available for neutron energies above 30 MeV. We focused for this reason on activation materials (Al, Au, Bi, In Ta, and Y)commonly used for such purposes and we also measured other materials (Cu, Fe, I, Mg, Ni, and Zn). The cross-sections were studied using quasi mono-energetic neutron sources based on proton reactions in a 7Li target in the energy range from 17 MeV up to94 MeV. We observed a good agreement of the obtained data with the experimental data in the EXFOR database and also with the calculations performed using the code TALYS 1.4. Many of presented measurements represent the first ever measurem
Název v anglickém jazyce
Studies of (n,xn) cross-sections in Al, Au, Bi, Cu, Fe, I, In, Mg, Ni, Ta, Y, and Zn by the activation method
Popis výsledku anglicky
The article summarizes series of experiments devoted to studies of (n,xn) cross-sections by the activation method and states numerical values of measured cross-sections. The activation samples are used to measure neutron flux produced during acceleratordriven system studies. The threshold (n,xn) reactions are used but experimental cross-section data of such reactions are mostly not available for neutron energies above 30 MeV. We focused for this reason on activation materials (Al, Au, Bi, In Ta, and Y)commonly used for such purposes and we also measured other materials (Cu, Fe, I, Mg, Ni, and Zn). The cross-sections were studied using quasi mono-energetic neutron sources based on proton reactions in a 7Li target in the energy range from 17 MeV up to94 MeV. We observed a good agreement of the obtained data with the experimental data in the EXFOR database and also with the calculations performed using the code TALYS 1.4. Many of presented measurements represent the first ever measurem
Klasifikace
Druh
J<sub>x</sub> - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)
CEP obor
JF - Jaderná energetika
OECD FORD obor
—
Návaznosti výsledku
Projekt
—
Návaznosti
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Ostatní
Rok uplatnění
2013
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
Nuclear Instruments and Methods in Physics Research, Section A, Accelerators, Spectrometers, Detectors and Associated Equipment
ISSN
0168-9002
e-ISSN
—
Svazek periodika
726
Číslo periodika v rámci svazku
—
Stát vydavatele periodika
NL - Nizozemsko
Počet stran výsledku
7
Strana od-do
84-90
Kód UT WoS článku
000323557200012
EID výsledku v databázi Scopus
—