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Neutronic Calculations for LH launcher in ITER equatorial port - PowerPoint PPT Presentation


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A. s. s. o. c. i. a. z. i. o. n. e. E. U. R. A. T. O. M. E. N. E. A. s. u. l. l. a. F. u. s. i. o. n. e. EFDA task HCD-08-03. Neutronic Calculations for LH launcher in ITER equatorial port. R. Villari UT-FUSTEC ENEA CR Frascati.

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EFDA task HCD-08-03

Neutronic Calculations for LH launcher in ITER equatorial port

R. Villari

UT-FUSTEC ENEA CR Frascati

Status of the Analysis:February 2010


Introduction

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Introduction

3-D Neutronic calculations for the ITER LH launcher are in progress to evaluate:

  • Nuclear Heating radial profile along the launcher;

  • Overall Nuclear Heating;

  • Neutron flux attenuation and total fluence on the RF windows

  • Nuclear Heating on the TFC (surrounding sectors);

  • Shutdown dose rate for radiation shielding analysis at cryostat level→ shielding optimisation

Preliminary results on Nuclear Heating and Neutron Flux calculations are presented


Neutronic tools

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Neutronic tools

Calculations are performed using QA validated ITER codes and data:

Codes

  • MCNP5 Monte Carlo code for neutron and gamma transport simulation

  • FISPACT (EASY 2007) inventory code for neutron induced activation

    Nuclear Data

  • FENDL2.1 for neutron and gamma transport

  • EAF 2007 for activation

    In particular the Direct One Step method, based on the use of MCNP and FISPACT, is used for shutdown dose rate calculations


Method

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Method

  • ITER RO provided the irradiation conditions (scenarios) and the last ITER reference MCNP 40° model (Alite 4)

  • The LH launcher model has been developed on the basis of design data provided by ENEA and CEA and integrated into Alite 4.

  • The results of the Neutronic analysis are normalised to 500 MW fusion power

ITER Alite-4 40° model

Available Space for LH system


Design of lhcd system mcnp model

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Design of LHCD system: MCNP model

Secondary Bi-J

Tapers+MC

Frame

PAM

Secondary windows (BeO)

Primary Bi-J

Shield

Passive WG

Phase shifter

Be


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Lh nuclear heating

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LH Nuclear Heating

Total ~ 3 MW


Lh nuclear heating radial profile

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LH Nuclear Heating radial profile

~6 MW/m3

~ 2x10-5 MW/m3


Neutron flux attenuation

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Neutron flux attenuation

PAM 4WG

PAM 2WG

PAM 1WG

MC+tapers

Shield

Attenuation factor >106

Neutron fast flux at RF secondary windows is 3.5x1012 n/m2s→for a lifetime of 107 s the neutron fluence is <1020 m-2→degradation of the ceramic and/or change of heat conductivity are not expected


Conclusions
Conclusions

Neutronic Analyses on the new design of LH launcher are essential to verify if the radiation shielding is sufficient to meet the required design limits and to evaluate the thermal nuclear loads on the system.

The preliminary results of MCNP calculations are :

Neutron flux

The attenuation of 6 order of magnitude at the secondary windows is sufficient to avoid the degradation of the ceramic materials and/or their change in heat conductivity (fluence <1020 n/m2)

Nuclear Heating

Total Nuclear heating is ~3 MW. Nuclear heating varies between 6 MW/m3 at the front part of the PAM to ~2x10-5 MW/m3 at the secondary window (as in the rear zone of the outboard VV).

Work in progress

Shutdown dose rate

Dose rate at 12 days after shutdown at the rear side of the port are in progress. Shielding optimisation of the back shield will be performed in order to guarantee the respect of the ITER design limit (100 microSv/h at 12 days after shutdown).


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