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

Czakoj Tomáš; Košťál Michal; Losa Evžen; Matěj Zdeněk; Šimon Jan; Mravec Filip; Cvachovec František

doi:10.1016/j.net.2022.05.019

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자료유형: 학술저널

저자정보: Czakoj Tomáš (Research Centre Rez Ltd) Košťál Michal (Research Centre Rez Ltd) Losa Evžen (Research Centre Rez Ltd) Matěj Zdeněk (Masaryk University) Šimon Jan (Research Centre Rez Ltd) Mravec Filip (Masaryk University) Cvachovec František (University of Defence)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제54권 제10호

발행연도: 2022.10

수록면: 3,824 - 3,832 (9page)

DOI: 10.1016/j.net.2022.05.019

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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 7e9.2 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

#PGNAA #Reactor #Radiation heating. Prompt gamma #mcnp

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