Irradiation Setup Quantifying the Fast and Thermal Neutron and Gamma Shares of a Polyethylene Shielded Americium-Beryllium Neutron Source

Research output: Contribution to book/Conference proceedings/Anthology/ReportConference contributionContributed

Contributors

Abstract

The construction of an irradiation workbench for quantitative neutron irradiation at a polyethylene shielded americium-beryllium source is currently in progress. Quantitatively measured and simulated physical quantities like spectral fluence rate, fluence rate, dose rate and ambient dose rate are meant to be catalogued for different distances from the shielding opening and for the individual fast and thermal neutron and photon components of the source radiation field. Only the quantification of the fast neutron field is being presented. Methods include a stilbene detector characterization using a pulse-shape-discrimination-aided Time-of-Flight setup and unfolding pulse-charge spectra via a simple unfolding technique. The determined spectral fluence rates are in good agreement with the performed simulations. Position dependencies are confirmed in the data.

Details

Original languageEnglish
Title of host publication2022 IEEE NSS/MIC RTSD - IEEE Nuclear Science Symposium, Medical Imaging Conference and Room Temperature Semiconductor Detector Conference
PublisherInstitute of Electrical and Electronics Engineers Inc.
ISBN (electronic)9781665488723
Publication statusPublished - 2022
Peer-reviewedNo

Publication series

SeriesIEEE Symposium on Nuclear Science (NSS/MIC)
ISSN1082-3654

Conference

Title2022 IEEE Nuclear Science Symposium, Medical Imaging Conference, and Room Temperature Semiconductor Detector Conference, IEEE NSS MIC RTSD 2022
Duration5 - 12 November 2022
CityMilano
CountryItaly

External IDs

ORCID /0000-0001-9023-3606/work/173988483