Shielding analysis for TCP and IVVS bio-shield plugs of ITER

I. K. Baidoo, Y. Wu, J. Song, S. Yu, S. Jakhar, E. Polunovskiy, M. Loughlin

Research output: Contribution to journalArticlepeer-review

3 Scopus citations

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.

Original languageEnglish
Article number111478
JournalFusion Engineering and Design
Volume153
DOIs
StatePublished - Apr 2020
Externally publishedYes

Funding

This work was supported by the ITER IO within the framework of a service contract [IO/17/CT/4300001602/ABN]. This work was also supported by the National Magnetic Confinement Fusion Science Program of China ( 2015GB116000 ); Informatization Project of Chinese Academy of Sciences ( XXH13506-104 ); Young Elite Scientists Sponsorship Program by CAST ( 2017QNRC001 ); the project of HIPS ( KP-2017-19 ). The authors would like to express their appreciation to the other members of the FDS team for providing an insightful discussion on all the aspects of SuperMC code functions. The joint support of World Academy of Science (CAS-TWAS)’s Ph.D. scholarship scheme is also appropriately acknowledged by the first author. This work was supported by the ITER IO within the framework of a service contract [IO/17/CT/4300001602/ABN]. This work was also supported by the National Magnetic Confinement Fusion Science Program of China (2015GB116000); Informatization Project of Chinese Academy of Sciences (XXH13506-104); Young Elite Scientists Sponsorship Program by CAST (2017QNRC001); the project of HIPS (KP-2017-19). The authors would like to express their appreciation to the other members of the FDS team for providing an insightful discussion on all the aspects of SuperMC code functions. The joint support of World Academy of Science (CAS-TWAS)’s Ph.D. scholarship scheme is also appropriately acknowledged by the first author.

FundersFunder number
The World Academy of Sciences
Fondation du Souffle
Chinese Academy of SciencesXXH13506-104
Hefei Institutes of Physical Science, Chinese Academy of SciencesKP-2017-19
China Academy of Space Technology2017QNRC001
National Magnetic Confinement Fusion Program of China2015GB116000

    Keywords

    • Bios-shield plug
    • ITER neutronics
    • MCNP
    • Shielding design
    • SuperMC

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