Neutron Flux Distributions for ITER B1 Port Cell 16 Shielding Design

Kara Godsey; Bor Kos; Matthew Swinney

doi:10.13182/PHYSOR22-37424

Neutron Flux Distributions for ITER B1 Port Cell 16 Shielding Design

Kara Godsey, Bor Kos, Matthew Swinney

Radiation Transport

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

The ITER fusion device being built in the south of France represents an interesting and complex neutronics problem. Equipment housed within the port cells bordering the plasma will be exposed to intense radiation environments with high-energy neutrons impacting the performance and degradation of electronics and equipment. Therefore, it is important to design shielding to reduce the impact of the neutron flux to equipment and to also reduce the resulting shut-down dose rate from the activation of materials within the port cells. In this analysis, the flux resulting from plasma neutrons was evaluated for port cell 16 of the B1 level, which houses equipment for the pellet-injection system, with a shielding design integrated to reduce the impact to equipment. The reduction in total plasma neutron flux was shown to be ~10³ from the inboard to outboard side of the shielding, and about 10⁴ from the inboard side of the bioshield to the inside of the pellet-injection cask.

Original language	English
Title of host publication	Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022
Publisher	American Nuclear Society
Pages	2943-2951
Number of pages	9
ISBN (Electronic)	9780894487873
DOIs	https://doi.org/10.13182/PHYSOR22-37424
State	Published - 2022
Event	2022 International Conference on Physics of Reactors, PHYSOR 2022 - Pittsburgh, United States Duration: May 15 2022 → May 20 2022

Publication series

Name	Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022

Conference

Conference	2022 International Conference on Physics of Reactors, PHYSOR 2022
Country/Territory	United States
City	Pittsburgh
Period	05/15/22 → 05/20/22

Funding

This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). The authors would like to acknowledge the contribution of Joel Risner at ORNL for serving as a technical reviewer and a source of guidance on many tools and processes involved in this work and also to Dave Rasmussen at U.S. ITER for providing an additional technical review and for general ITER guidance. This work was sponsored by US ITER. This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).

Funders	Funder number
DOE Public Access Plan
US ITER
U.S. Department of Energy
Oak Ridge National Laboratory

Keywords

ADVANTG
MCNP
dose rate
flux
fusion neutronics
shielding

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

Access to Document

10.13182/PHYSOR22-37424

Cite this

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title = "Neutron Flux Distributions for ITER B1 Port Cell 16 Shielding Design",

abstract = "The ITER fusion device being built in the south of France represents an interesting and complex neutronics problem. Equipment housed within the port cells bordering the plasma will be exposed to intense radiation environments with high-energy neutrons impacting the performance and degradation of electronics and equipment. Therefore, it is important to design shielding to reduce the impact of the neutron flux to equipment and to also reduce the resulting shut-down dose rate from the activation of materials within the port cells. In this analysis, the flux resulting from plasma neutrons was evaluated for port cell 16 of the B1 level, which houses equipment for the pellet-injection system, with a shielding design integrated to reduce the impact to equipment. The reduction in total plasma neutron flux was shown to be ~103 from the inboard to outboard side of the shielding, and about 104 from the inboard side of the bioshield to the inside of the pellet-injection cask.",

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author = "Kara Godsey and Bor Kos and Matthew Swinney",

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year = "2022",

doi = "10.13182/PHYSOR22-37424",

language = "English",

series = "Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022",

publisher = "American Nuclear Society",

pages = "2943--2951",

booktitle = "Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022",

}

Godsey, K, Kos, B & Swinney, M 2022, Neutron Flux Distributions for ITER B1 Port Cell 16 Shielding Design. in Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022, American Nuclear Society, pp. 2943-2951, 2022 International Conference on Physics of Reactors, PHYSOR 2022, Pittsburgh, United States, 05/15/22. https://doi.org/10.13182/PHYSOR22-37424

Neutron Flux Distributions for ITER B1 Port Cell 16 Shielding Design. / Godsey, Kara; Kos, Bor; Swinney, Matthew.
Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. American Nuclear Society, 2022. p. 2943-2951 (Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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AB - The ITER fusion device being built in the south of France represents an interesting and complex neutronics problem. Equipment housed within the port cells bordering the plasma will be exposed to intense radiation environments with high-energy neutrons impacting the performance and degradation of electronics and equipment. Therefore, it is important to design shielding to reduce the impact of the neutron flux to equipment and to also reduce the resulting shut-down dose rate from the activation of materials within the port cells. In this analysis, the flux resulting from plasma neutrons was evaluated for port cell 16 of the B1 level, which houses equipment for the pellet-injection system, with a shielding design integrated to reduce the impact to equipment. The reduction in total plasma neutron flux was shown to be ~103 from the inboard to outboard side of the shielding, and about 104 from the inboard side of the bioshield to the inside of the pellet-injection cask.

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Neutron Flux Distributions for ITER B1 Port Cell 16 Shielding Design

Abstract

Publication series

Conference

Funding

Keywords

UN SDGs

Access to Document

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