Integral approach for neutronics analyses of the European test blanket modules in ITER

Fischer, U.; Große, Daniel; Moro, F.; Pereslavtsev, P.; Petrizzi, L.; Villari, R.; Weber, Virginia

doi:10.1016/j.fusengdes.2011.01.067

Cited by 12 publications

(6 citation statements)

References 4 publications

(3 reference statements)

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“…To go further in the direction of global fusion blanket design approach, this work needs also to be completed by a methodology using the CAD-based integral approach for neutronics analyses, as started at KIT [21].…”

Section: Resultsmentioning

confidence: 99%

Numerical benchmarks TRIPOLI−MCNP with use of MCAM on FNG ITER bulk shield and FNG HCLL TBM mock-up experiments

Fausser

Lee

Villari

et al. 2011

Fusion Engineering and Design

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Section: Resultsmentioning

confidence: 99%

Numerical benchmarks TRIPOLI−MCNP with use of MCAM on FNG ITER bulk shield and FNG HCLL TBM mock-up experiments

Fausser

Lee

Villari

et al. 2011

Fusion Engineering and Design

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“…e. Respect of ITER nuclear zoning, limit of release of effluents or dust, ORE principles, etc. A nuclear analysis on TBM shield performances and irradiation in the interspace is presented in [15].…”

Section: Port Cell Integrationmentioning

confidence: 99%

Present status of the conceptual design of the EU test blanket systems

Boccaccini¹,

Aiello

Bede

et al. 2011

Fusion Engineering and Design

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“…The situation in the ITER EPs is particularly challenging, due to their proximity to the plasma, the port plug weight restrictions, the limited space for shielding and the relative orientation with respect to the plasma. A collection of works showing current status is [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports

et al. 2018

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The planned in situ maintenance tasks in the ITER port interspace are fundamental to ensure the operation of equipment to control, evaluate and optimize the plasma performance during the entire facility lifetime. They are subject to a limit of shutdown dose rates (SDDR) of 100 µSv h−1 after 106 s of cooling time, which is nowadays a design driver for the port plugs as well as the application of ALARA. Three conceptual shielding proposals outside the ITER ports are studied in this work to support the achievement of this objective. Considered one by one, they offer reductions ranging from 25% to 50%, which are rather significant. This paper shows that, by combining these shields, the SDDR as low as 57Δ µSv h−1 can be achieved with a local approach considering only radiation from one port (no cross-talk form neighboring ports). The locally evaluated SDDR are well below the limit which is an essential pre-requisite for achieving 100µSv h−1 in a global analysis including all contributions. Further studies will have to deal with a realistic port plug design and the cross-talks from neighbour ports.

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Integral approach for neutronics analyses of the European test blanket modules in ITER

Cited by 12 publications

References 4 publications

Numerical benchmarks TRIPOLI−MCNP with use of MCAM on FNG ITER bulk shield and FNG HCLL TBM mock-up experiments

Numerical benchmarks TRIPOLI−MCNP with use of MCAM on FNG ITER bulk shield and FNG HCLL TBM mock-up experiments

Present status of the conceptual design of the EU test blanket systems

Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports

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