Abstract

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.

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call

Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.