5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P3.203 ITER Generic Diagnostics Ports nuclear analysis

7 Sep 2016, 11:00
1h 20m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 203
Poster J. Power Plants Safety and Environment, Socio-Economics and Technology Transfer P3 Poster session

Speaker

Rafael Juarez (Departamento de Ingeniería Energética)

Description

ITER is a prominent facility in the development of the nuclear fusion. It presents 44 ports providing access to the Vacuum Vessel at three different heights: Lower, Equatorial and Upper ports. Out of them, 22 ports, correspond to Diagnostics ports. They host a diversity of diagnostics systems, designed by the different ITER Domestics Agencies (DAs). They are later integrated into the different Diagnostics ports again by the DAs, not necessarily coincident with those who designed the systems. ITER Diagnostics ports represent a challenge from the neutronics standpoint. In addition to the general ITER port neutronics loads, Diagnostics ports present the difficulty of port plug penetrations with direct view to the plasma. Thus, Diagnostics ports design demands stringent nuclear analysis tasks, requiring large computational resources, long times and cumbersome methodologies and computational tools. Provided that many tenant will be implied in the nuclear analysis of each Diagnostics port, at different organization levels, the workload distribution procedure could easily lead to coordination problems: i) lack of standardization, ii) results spreading and iii) work replication. In order to avoid such problems, Diagnostics Division in IO-CT has developed MCNP models of the generic Diagnostics ports which are inserted into the latest ITER MCNP model C-lite version available. They will be used by all of the diagnostics tenants implied in the design of systems of port integrators. In this work, the MCNP models and their nuclear response during plasma operation are presented. This approach will serve to get three important objectives: Establishing reference values to serve a basis for studies convergence and checking Models standardization, mandatory to avoid inconsistencies between works Time, human and computational resources saving to all the implied tenants Thus, reference nuclear analysis of ITER Diagnostics ports, 22 of 44 ITER ports, are presented in this work.

Co-authors

Angel Ibarra (Laboratorio Nacional de Fusión por Confinamiento Magnético , CIEMAT, Madrid, Spain) Arkady Serikov (Institute for Neutron Physics and Reactor Technology, Karlsruhe Institute of Technology, Karlsruhe, Germany) Fernando Mota (Laboratorio Nacional de Fusión por Confinamiento Magnético , CIEMAT, Madrid, Spain) Javier Sanz (Departamento de Ingeniería Energética, Universidad de Educación a Distancia, Madrid, Spain) Juan Pablo Catalan (Departamento de Ingeniería Energética, Universidad de Educación a Distancia, Madrid, Spain) Julio Guirao (ITER Organization, Route de Vinon sur Verdon, 13067 Saint Paul lez Durance Cedex, France) Luciano Bertalot (ITER Organization, Route de Vinon sur Verdon, 13067 Saint Paul lez Durance Cedex, France) Michael Walsh (ITER Organization, Route de Vinon sur Verdon, 13067 Saint Paul lez Durance Cedex, France) Natalia Casal (ITER Organization, Route de Vinon sur Verdon, 13067 Saint Paul lez Durance Cedex, France) Rafael Juarez (Departamento de Ingeniería Energética, Universidad de Educación a Distancia, Madrid, Spain) Thibaud Giacomin (ITER Organization, Route de Vinon sur Verdon, 13067 Saint Paul lez Durance Cedex, France) Victor Udintsev (ITER Organization, Route de Vinon sur Verdon, 13067 Saint Paul lez Durance Cedex, France)

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