Measurement of neutron dose on a fusion reactor shield using TLD-300 phosphors

M. Angelone, P. Batistoni, A. Esposito, M. Martone, M. Pelliccioni, M. Pillon, V. Rado

Research output: Contribution to journalArticle

2 Citations (Scopus)

Abstract

A benchmark experiment was carried out at the 14 MeV Frascati Neutron Generator (FNG) to measure the nuclear heating in an experimental assembly simulating a fusion reactor shield and its superconducting coils. TLD-300 detectors were used allowing the neutron and gamma contribution to the total nuclear heating to be separated by using the two-peak method. The experiment aimed at validating the EFF and FENDL neutron transport cross section files presently available for nuclear heating calculations of fusion reactor shields. The calculations were performed using the Monte Carlo code MCNP. The measured and calculated gamma absorbed dose agree well while differences up to 30% were found for the neutron absorbed dose when the EFF file is used. The discrepancy increases up to 50% when the FENDL file is used to calculate the neutron absorbed dose.
Original languageEnglish
Pages (from-to)169 - 173
Number of pages5
JournalRadiation Protection Dosimetry
Volume70
Issue number1-4
DOIs
Publication statusPublished - 1997
Externally publishedYes

    Fingerprint

All Science Journal Classification (ASJC) codes

  • Radiological and Ultrasound Technology
  • Radiation
  • Radiology Nuclear Medicine and imaging
  • Public Health, Environmental and Occupational Health

Cite this

Angelone, M., Batistoni, P., Esposito, A., Martone, M., Pelliccioni, M., Pillon, M., & Rado, V. (1997). Measurement of neutron dose on a fusion reactor shield using TLD-300 phosphors. Radiation Protection Dosimetry, 70(1-4), 169 - 173. https://doi.org/10.1093/oxfordjournals.rpd.a031936