Calculation and measurement of Al prompt capture gammas above water in a pool-type reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F22%3AN0000030" target="_blank" >RIV/26722445:_____/22:N0000030 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/00216224:14330/22:00128971 RIV/68407700:21340/22:00351454

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S1738573322002686" target="_blank" >https://www.sciencedirect.com/science/article/pii/S1738573322002686</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.net.2022.05.019" target="_blank" >10.1016/j.net.2022.05.019</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Calculation and measurement of Al prompt capture gammas above water in a pool-type reactor

Popis výsledku v původním jazyce

Prompt capture gammas are an important part of the fission reactor gamma field. Because some of the structural materials after neutron capture can emit photons with high energies forming the dominant component of the gamma spectrum in the high energy region, the following study of the high energy capture gamma was carried out. High energy gamma radiation may play a major role in areas of the radiation sciences as reactor dosimetry. The HPGe measurements and calculations of the high-energy aluminum capture gamma were performed at two moderator levels in the VR-1 pool-type reactor. The result comparison for nominal levels was within two sigma uncertainties for the major 7.724 MeV peak. A larger discrepancy of 60% was found for the 7.693 MeV peak. The spectra were also measured using a stilbene detector, and a good agreement between HPGe and stilbene was observed. This confirms the validity of stilbene measurements of gamma flux. Additionally, agreement of the wide peak measurement in 7–9.2 MeV by stilbene detector shows the possibility of using the organic scintillators as an independent power monitor. This fact is valid in these reactor types because power is proportional to the thermal neutron flux, which is also proportional to the production of capture gammas forming the wide peak.

Název v anglickém jazyce

Calculation and measurement of Al prompt capture gammas above water in a pool-type reactor

Popis výsledku anglicky

Prompt capture gammas are an important part of the fission reactor gamma field. Because some of the structural materials after neutron capture can emit photons with high energies forming the dominant component of the gamma spectrum in the high energy region, the following study of the high energy capture gamma was carried out. High energy gamma radiation may play a major role in areas of the radiation sciences as reactor dosimetry. The HPGe measurements and calculations of the high-energy aluminum capture gamma were performed at two moderator levels in the VR-1 pool-type reactor. The result comparison for nominal levels was within two sigma uncertainties for the major 7.724 MeV peak. A larger discrepancy of 60% was found for the 7.693 MeV peak. The spectra were also measured using a stilbene detector, and a good agreement between HPGe and stilbene was observed. This confirms the validity of stilbene measurements of gamma flux. Additionally, agreement of the wide peak measurement in 7–9.2 MeV by stilbene detector shows the possibility of using the organic scintillators as an independent power monitor. This fact is valid in these reactor types because power is proportional to the thermal neutron flux, which is also proportional to the production of capture gammas forming the wide peak.

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

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)

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

10

Stát vydavatele periodika

KR - Korejská republika

Počet stran výsledku

9

Strana od-do

3824-3832

Kód UT WoS článku

000869040500009

EID výsledku v databázi Scopus

2-s2.0-85131438730