[en] The Next European Torus (NET) in-vessel components consisting of first wall, divertor, and blanket/shield are subject to severe nuclear and thermal radiation. Their reliability and maintainability are crucial to the success of the NET mission. The requirements, options, preliminary design solution, and materials considerations for these components are described

No abstract available

[en] The development and demonstration of reactor relevant fusion technology and components, including a tritium blanket, is one of NET major objectives. The strategy of introducing breeding blanket segments is defined and discussed in relation to the planning of the operation of NET and the required testing programme of the in-vessel components. (author)

No abstract available

[en] NET will produce fusion reactions, which will result in the structure and internal components of the machine becoming radioactive. Consequently, NET will use remot handling techniques to perform maintenance. The strategy being followed to ensure that NET is fully compatible with the remote handling requirements is described together with a preliminary list of the remote handling equipment being developed. (orig.)

[en] The use of tritium as a fuel affects the design of many systems, as well as requiring several new systems not needed on non DT-burning Tokamaks. A summary is given of the following: major tritium process interconnections, tritium flows and inventories; primary requirements, preferred design alternatives, and related development issues; design philosophy for tritium and primary vacuum systems. (author)

[en] NET, the Next European Torus, will be a fusion technology device attaining a burning Deuterium-Tritium plasma. Tritium environment and the high activation of the machine, the frequency and complexity of maintenance tasks give the maintenance analysis a crucial importance and determine the need to establish a comprehensive maintenance concept which is a basis for definition of a set of remote handling equipment, availability investigation as well as establishment of design standards. The NET maintenance concept is described. (author)

No abstract available

[en] The progress of the First Wall (FW) design studies for the Next European Torus (NET) is summarized with emphasis on concepts with poloidal water cooling double contained in welded steel structures. For the proposed FW concepts manufacturing feasibility studies have been performed by industry, where critical manufacturing steps have been demonstrated by test specimen. (author)

[en] The testing stages in NET for the performance assessment of the various breeding blanket concepts developed at the present time in Europe for DEMO (LiPb and ceramic blankets) and the requirements upon NET to perform these tests are reviewed. Typical locations available in NET for blanket testing are the central outboard segments and the horizontal ports of in-vessel sectors. These test positions will be connectable with external test loops. The number of test loops (helium, water, liquid metal) will be such that each major class of blankets can be tested in NET. The test positions, the boundary conditions and the external test loops are identified and the requirements for test blankets are summarized (author). 6