Performance of a virtual frisch-grid CdZnTe detector for prompt γ-ray induced by 14 MeV neutrons: Monte Carlo simulation study

Taewoong Lee, Younghak Kim, Ajin Jo, Jongguk Kim, W. Lee

Research output: Contribution to journalArticlepeer-review

3 Citations (Scopus)

Abstract

The performance of a virtual (6 × 6 × 15 mm3) Frisch-grid cadmium zinc telluride detector for the detection of contraband with 14 MeV neutron-activation prompt γ-rays was studied using Monte Carlo simulations. A sensitive nonlinear iterative peak clipping algorithm was applied to the spectra to rapidly and easily identify the prompt γ-ray peaks. This algorithm showed better performance than directly using the original spectra. The CZT detector showed good energy resolution for the high energy prompt γ-rays and its carbon-to-oxygen peak ratios were almost equal to the theoretical value of the target contraband materials. The minimum detectable concentration of carbon and oxygen elements using the CZT detector was calculated. The simulation results for the CZT detector were compared to those of a HPGe detector and demonstrated the feasibility of using a CZT detector in neutron activation analysis.

Original languageEnglish
Article number108818
JournalApplied Radiation and Isotopes
Volume153
DOIs
Publication statusPublished - 2019 Nov

Bibliographical note

Funding Information:
This study was supported by the grant of the Korea Institute of Radiological and Medical Science (KIRAMS) , funded by the Ministry of Science and ICT (MSIT) (No. 1711045543 ; 1711045540 / 50462-2019 ), and the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS) granted the financial resource from the Nuclear Safety and Security Commission (NSSC) (No. 1903006 ), Republic of Korea.

Publisher Copyright:
© 2019

Keywords

  • Detection of contraband materials
  • Minimum detectable concentration (MDC)
  • Prompt γ-ray neutron activation analysis (PGNAA)
  • Sensitive nonlinear iterative peak clipping algorithm (SNIP)
  • Virtual frisch-grid cadmium zinc telluride (CZT)

ASJC Scopus subject areas

  • Radiation

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