Analysis of high heat flux testing of mock-ups

ITER EU Home Team is performing a large R&D effort in support of the development of high heat flux components for ITER. In this framework, this paper describes the thermal analyses, the fatigue lifetime evaluation and the transient VDE with materia

Assessment of the shielding efficiency of the HCLL blanket for a DEMO-type fusion reactor

International audienceThis work summarizes the results of a neutronic study on the HCLL blanket for a DEMO-type fusion reactor. The analysis is based on three-dimensional Monte Carlo calculations using the MCNP-4C code. It comprises the assessment of the shielding efficiency in terms of the radiation loads to the superconducting TF-coils and the neutron induced production of He and H gas in the steel structure of the blanket and at locations where the welding of pipe connections is assumed. The analysis is performed utilizing three-dimensional 9$^0$-sector model representing the modular HCLL breeder blanket developed by CEA. The shielding performance of the blanket/shield/vacuum vessel system is assessed at the torus mid-plane considering three variants of a two-component shield, arranged in between the central inboard modules and the Vacuum Vessel. Estimates of radial distributions of the He and H gas production in the steel structure of the blanket are obtained and the radial depth where the re-weldability criterion for the He production <1 appm is fulfilled is identified

Studies on additional electrical heating of the HCLL TBM breeder zone

International audienceAmong the test blanket modules (TBMs) to be tested in the successive ITER phases, European design activities have focused on the electromagnetic (EM) TBM to be tested in ITER first phase (H-H), and on the integral (IN) TBM to be tested in the full duty D-T phase. The scope of the present contribution is to report activities performed on the helium cooled lithium lead (HCLL) TBM, in its EM version for the H-H phase. This phase is characterized for the TBM by relevant D-T phase magnetic field, surface heat flux and disruption induced loads, and the lack of nuclear volumetric heating. On one hand, H-H phase gives the opportunity of experiments and use of instrumentation which will not be possible in the irradiated environment of D-T phase. On the other hand, H-H phase specificity is a temperature level in the breeder zone much lower than that in the D-T phase. Main EU objectives assigned to TBM testing in H-H phase for design validation and for the build-up of a reliability database can be fulfilled at this temperature level, which is not the case for the scientific experimental program (MHD, corrosion and tritium permeation). Hence, partial heating of the TBM is foreseen. A technical solution for an electrically heated configuration of the breeder zone has been investigated. Finite element (FE) analyses were performed to assess the thermal behaviour of the TBM for the non-heated and heated cases

The design of a new JET divertor for high triangularity and high current scenarios

A new divertor (MKII-HP) has been designed to be implemented in JET as part of a possible enhancement programme of the JET facility (JET EP). The aim is to handle up to 40 MW of injected power for 10 s with plasma triangularities up to 0.5 while keeping enough flexibility for other scenarios. The divertor is shaped to optimise the wetting fraction without exposing sharp edges or metallic parts and the general design allows for high halo currents. (C) 2003 Elsevier Science B.V. All rights reserved

The design of a new JET divertor for high triangularity and high current scenarios

A new divertor (MKII-HP) has been designed to be implemented in JET as part of a possible enhancement programme of the JET facility (JET EP). The aim is to handle up to 40 MW of injected power for 10 s with plasma triangularities up to 0.5 while keeping enough flexibility for other scenarios. The divertor is shaped to optimise the wetting fraction without exposing sharp edges or metallic parts and the general design allows for high halo currents. (C) 2003 Elsevier Science B.V. All rights reserved