Measurement of neutron spectra in spent fuel storage
Status PubMed-not-MEDLINE Language English Country England, Great Britain Media print-electronic
Document type Journal Article
PubMed
39427477
DOI
10.1016/j.apradiso.2024.111552
PII: S0969-8043(24)00380-4
Knihovny.cz E-resources
- Keywords
- Ambient dose equivalent, Digitizer, Gamma detector, Gamma spectra, Neutron detector, Neutron sources, Neutron spectra, Pulse shape discrimination, Unfolding,
- Publication type
- Journal Article MeSH
The neutron spectrum was measured at two locations in the spent fuel storage facility of the Temelín nuclear power plant. The measurement had two primary objectives: to map the neutron -γ field by quantifying the ambient dose equivalent H∗(10) and to identify methods that could improve the quality of the adjusted neutron spectrum using a Bonner Sphere Spectrometer (BSS). Three spectrometers were used: a BSS and two proton recoil spectrometers. Hydrogen-filled proportional counters and an EJ309 scintillator were used to construct the a priori spectrum for BSS adjustment. The details of this process and its results are discussed. The a posteriori spectrum was used to calculate the ambient dose equivalent H∗(10). The resulting spectrum is highly thermalised, but the predominant contribution to H∗(10) was in the 100 keV-1.3 MeV range. The use of hydrogen-proportional counters in combination with the BSS is recommended.
Department of Laboratory Operation Research Centre Řež Hlavní 130 250 68 Řež Czech Republic
Department of Neutron Physics Research Centre Řež Hlavní 130 250 68 Řež Czech Republic
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