Abstract

ITER neutronics model (Tokamak Complex) keeps evolving, and each development requires comprehensive transport analysis for verification and validation. The tokamak complex’s bio-shield plugs are the main shielding barriers between the tokamak and the port cells. Therefore, shielding analysis and optimization for the bio-shield plugs are part of the key factors for ITER licensing. In this work, performance evaluation of two designed bio-shield plugs: IVVS-port cell #3 and TCP-port cell #4 in level B1 has been conducted. Neutron transport calculation analysis on the new designs (generic designs) showed total neutron flux of 1.71 × 106 n/cm2/s and 2.86 × 105 n/cm2/s respectively in a specified tally cell behind the IVVS and TCP bio-shield plug. Spatial neutron distribution behind the bios-shield plug (port cells) showed significant shielding improvement compared to the original IVVS and TCP bio-shield design. Further iterative optimized shielding scheme has been proposed to reduce the total neutron flux from 1.71 × 106 to 8.8 × 104 n/cm2/s and from 2.86 × 105 to 6.4 × 104 n/cm2/s for the respective tally cell behind IVVS and TCP bio-shield plugs.

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.