Three-dimensional neutronic analysis of the ITER in-vessel coils

R. Villari; L. Petrizzi; G. Brolatti; E. Daly; M. Loughlin; A. Martin; F. Moro; E. Polunovskiy

doi:10.1016/j.fusengdes.2010.12.004

Three-dimensional neutronic analysis of the ITER in-vessel coils

R. Villari, L. Petrizzi, G. Brolatti, E. Daly, M. Loughlin, A. Martin, F. Moro, E. Polunovskiy

Research output: Contribution to journal › Article › peer-review

10 Scopus citations

Abstract

A complete neutronic analysis has been performed for the design of the in-vessel coil systems using the MCNP5 Monte Carlo Code in a full 3-D geometry. A detailed geometry of ELM and VS coils based on the latest design specifications has been integrated into the latest version of 40° sector of ITER MCNP model. Nuclear heating and helium production in the coils, absorbed dose in the insulator, dpa and transmutation of copper-alloy and neutron fluxes have been calculated. Neutron spectra have been used as input for an activation analysis performed with FISPACT inventory code for safety analysis and waste classification. The impact of the gaps between blanket modules and of the manifolds on the nuclear parameters has been evaluated as well as the effect on vacuum vessel reweldability. Different options for the conductor and the insulator have been examined.

Original language	English
Pages (from-to)	584-587
Number of pages	4
Journal	Fusion Engineering and Design
Volume	86
Issue number	6-8
DOIs	https://doi.org/10.1016/j.fusengdes.2010.12.004
State	Published - Oct 2011
Externally published	Yes

Keywords

ITER
In-vessel coils
MCNP
Neutronics

UN SDGs

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

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10.1016/j.fusengdes.2010.12.004

Cite this

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title = "Three-dimensional neutronic analysis of the ITER in-vessel coils",

abstract = "A complete neutronic analysis has been performed for the design of the in-vessel coil systems using the MCNP5 Monte Carlo Code in a full 3-D geometry. A detailed geometry of ELM and VS coils based on the latest design specifications has been integrated into the latest version of 40° sector of ITER MCNP model. Nuclear heating and helium production in the coils, absorbed dose in the insulator, dpa and transmutation of copper-alloy and neutron fluxes have been calculated. Neutron spectra have been used as input for an activation analysis performed with FISPACT inventory code for safety analysis and waste classification. The impact of the gaps between blanket modules and of the manifolds on the nuclear parameters has been evaluated as well as the effect on vacuum vessel reweldability. Different options for the conductor and the insulator have been examined.",

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AU - Villari, R.

AU - Petrizzi, L.

AU - Brolatti, G.

AU - Daly, E.

AU - Loughlin, M.

AU - Martin, A.

AU - Moro, F.

AU - Polunovskiy, E.

PY - 2011/10

Y1 - 2011/10

N2 - A complete neutronic analysis has been performed for the design of the in-vessel coil systems using the MCNP5 Monte Carlo Code in a full 3-D geometry. A detailed geometry of ELM and VS coils based on the latest design specifications has been integrated into the latest version of 40° sector of ITER MCNP model. Nuclear heating and helium production in the coils, absorbed dose in the insulator, dpa and transmutation of copper-alloy and neutron fluxes have been calculated. Neutron spectra have been used as input for an activation analysis performed with FISPACT inventory code for safety analysis and waste classification. The impact of the gaps between blanket modules and of the manifolds on the nuclear parameters has been evaluated as well as the effect on vacuum vessel reweldability. Different options for the conductor and the insulator have been examined.

AB - A complete neutronic analysis has been performed for the design of the in-vessel coil systems using the MCNP5 Monte Carlo Code in a full 3-D geometry. A detailed geometry of ELM and VS coils based on the latest design specifications has been integrated into the latest version of 40° sector of ITER MCNP model. Nuclear heating and helium production in the coils, absorbed dose in the insulator, dpa and transmutation of copper-alloy and neutron fluxes have been calculated. Neutron spectra have been used as input for an activation analysis performed with FISPACT inventory code for safety analysis and waste classification. The impact of the gaps between blanket modules and of the manifolds on the nuclear parameters has been evaluated as well as the effect on vacuum vessel reweldability. Different options for the conductor and the insulator have been examined.

KW - ITER

KW - In-vessel coils

KW - MCNP

KW - Neutronics

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EP - 587

JO - Fusion Engineering and Design

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ER -

Three-dimensional neutronic analysis of the ITER in-vessel coils

Abstract

Keywords

UN SDGs

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