Simultaneous measurements for fast neutron flux and tritium production rate using pulse shape discrimination and single crystal CVD diamond detector
At a Glance
Section titled āAt a Glanceā| Metadata | Details |
|---|---|
| Publication Date | 2024-04-16 |
| Journal | Nuclear Fusion |
| Authors | Makoto Kobayashi, Sachiko Yoshihashi, K. Ogawa, M. Isobe, Tsukasa Aso |
| Institutions | National Institute for Fusion Science, The University of Osaka |
| Citations | 2 |
Abstract
Section titled āAbstractāAbstract This paper presents the development of a simultaneous measurement method for fast neutron energy spectra and tritium production rates within mixed radiation fields using a single crystal chemical vapour deposition diamond detector combined with a lithium fluoride (LiF) foil. The method involves the separation of pulses with rectangular shapes and the determination of the depth position within the single crystal diamond (SCD) struck by fast neutrons or nuclear reaction products including recoil tritons from the LiF foil based on pulse width, extracting pulse events occurred at the specific bulk region and the surface region of the SCD. Subsequently, unfolding techniques were employed to analyse the energy deposition spectrum of pulses at the specific bulk region which are induced only by fast neutrons, allowing the deduction of the fast neutron energy spectrum. To evaluate the tritium production rate, the energy deposition spectrum of pulses from events occurring at the SCD surface facing the LiF foil was analysed. By estimating the energy deposition spectrum solely induced by fast neutrons striking the SCD surface and subtracting it from the energy deposition spectrum of events at the SCD surface, the contribution of energetic ions, such as recoil tritons generated by the 6 Li(n, Ī± ) 3 H reaction in the LiF foil, was determined. The fast neutron flux and tritium production rate obtained through this study were consistent with particle transport calculations, demonstrating the successful development of a method suitable for performance testing of fusion reactor blankets.
Tech Support
Section titled āTech SupportāOriginal Source
Section titled āOriginal SourceāReferences
Section titled āReferencesā- 2024 - Overview of progress on water cooled ceramic breeder blanket in Japan [Crossref]
- 2015 - Design study of blanket structure based on a water-cooled solid breeder for DEMO [Crossref]
- 2022 - Design of the water-cooled ceramic breeder blanket for CFETR [Crossref]
- 2021 - Design and fabrication R&D progress of CN HCCB TBM [Crossref]
- 2020 - Overview of recent ITER TBM program activities [Crossref]
- 2019 - An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort [Crossref]
- 2018 - The FFHR design group, maintainability of the helical reactor FFHR-c1 equipped with the liquid metal divertor and cartridge-type blankets [Crossref]
- 2022 - Overview of Kyoto Fusioneeringās SCYLLAĀ© (āself-cooled yuryo lithium-lead advancedā) blanket for commercial fusion reactors [Crossref]
- 2017 - Automated parametric neutronics analysis of the helium cooled pebble bed breeder blanket with Be12Ti [Crossref]
- 2023 - Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket [Crossref]