Measurement of various monitors reaction rate in a special core at LR-0 reactor
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000009" target="_blank" >RIV/26722445:_____/18:N0000009 - isvavai.cz</a>
Výsledek na webu
<a href="http://dx.doi.org/10.1016/j.anucene.2017.10.036" target="_blank" >http://dx.doi.org/10.1016/j.anucene.2017.10.036</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.anucene.2017.10.036" target="_blank" >10.1016/j.anucene.2017.10.036</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Measurement of various monitors reaction rate in a special core at LR-0 reactor
Popis výsledku v původním jazyce
Validation of the selected materials cross sections is an important task for their use as flux monitors within experimental measurements. As the reaction rate is a function of neutron spectrum and material cross section, the neutron spectrum must be well defined for the correct cross section validation. This criterion is met in the special core of the LR-0 reactor, where the reaction rates of Ta-181(n,gamma), Fe-54(n,p), Fe-54 (n,alpha) and Y-89(n,2n) reactions were measured. The Au-197(n,gamma) and Ni-58(n,p) reactions were used as flux monitors during measurements. Results of calculation show that in case of Ta-181(n,gamma) reaction, the values reported in JEFF-3.2 provide a good agreement, while ENDF/B-VII.1 is underpredicting the experiment. In case of Fe-54(n,p) reaction, JEFF-3.2 is in satisfactory agreement, while ENDF/E-VII.1 overpredicts the result by about 10%. The Fe-54(n,alpha) shows significant discrepancies, JEFF-3.2 under predicts by about 20%, while ENDF/B-VII.1 overpredicts result by 40%. The high threshold Y-89(n,2n) reaction is interesting from the point of view of spectral averaged cross section. It is worth noting that the resulted spectral averaged cross section, being 0.169 with 16 uncertainty of 0.007 mb, is in very good agreement with previous result, being 0.172 +/- 0.006 mb.
Název v anglickém jazyce
Measurement of various monitors reaction rate in a special core at LR-0 reactor
Popis výsledku anglicky
Validation of the selected materials cross sections is an important task for their use as flux monitors within experimental measurements. As the reaction rate is a function of neutron spectrum and material cross section, the neutron spectrum must be well defined for the correct cross section validation. This criterion is met in the special core of the LR-0 reactor, where the reaction rates of Ta-181(n,gamma), Fe-54(n,p), Fe-54 (n,alpha) and Y-89(n,2n) reactions were measured. The Au-197(n,gamma) and Ni-58(n,p) reactions were used as flux monitors during measurements. Results of calculation show that in case of Ta-181(n,gamma) reaction, the values reported in JEFF-3.2 provide a good agreement, while ENDF/B-VII.1 is underpredicting the experiment. In case of Fe-54(n,p) reaction, JEFF-3.2 is in satisfactory agreement, while ENDF/E-VII.1 overpredicts the result by about 10%. The Fe-54(n,alpha) shows significant discrepancies, JEFF-3.2 under predicts by about 20%, while ENDF/B-VII.1 overpredicts result by 40%. The high threshold Y-89(n,2n) reaction is interesting from the point of view of spectral averaged cross section. It is worth noting that the resulted spectral averaged cross section, being 0.169 with 16 uncertainty of 0.007 mb, is in very good agreement with previous result, being 0.172 +/- 0.006 mb.
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
2018
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
Annals of Nuclear Energy
ISSN
0306-4549
e-ISSN
—
Svazek periodika
112
Číslo periodika v rámci svazku
February
Stát vydavatele periodika
GB - Spojené království Velké Británie a Severního Irska
Počet stran výsledku
10
Strana od-do
759-768
Kód UT WoS článku
000419409100064
EID výsledku v databázi Scopus
2-s2.0-85034045194