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Neutronic Calculations for LH launcher in ITER equatorial port

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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Neutronic Calculations for LH launcher in ITER equatorial port

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  1. 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 Status of the Analysis:February 2010

  2. 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 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

  3. 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 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

  4. 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 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

  5. 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 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

  6. 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

  7. 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

  8. 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 LH Nuclear Heating Total ~ 3 MW

  9. 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 LH Nuclear Heating radial profile ~6 MW/m3 ~ 2x10-5 MW/m3

  10. 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 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

  11. 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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