[en] The central cell field of the tandem mirror reactor (TMR) will be achieved with discrete solenoids spaced at regular intervals to provide space for feeding and diagnostic devices. The solenoids are superconducting and operate in a steady dc mode. To provide long term operation, the solenoid will be designed for cryostatically stable operation

[en] The mineral resource implications of an economy of tokamak-type fusion reactors are assessed based upon the recent conceptual reactor design study, NUWMAK, developed at the University of Wisconsin. For comparative purposes, various structural alloys of vanadium and steel are assumed to be usable in the NUWMAK design in place of the titanium alloy originally selected. In addition, the inner blanket core and magnet system of the conceptual reactor, HFCTR, developed at the Massachusetts Institute of Technology, are assumed to be interchangeable with the comparable components in NUWMAK. These variations permit a range of likely requirements to be assessed

[en] The mineral resource implications of an economy of tokamak-type fusion reactors are assessed based upon the recent conceptual reactor design study, NUWMAK, developed at the University of Wisconsin. For comparative purposes, various structural alloys of vanadium and steel are assumed to be usable in the NUWMAK design in place of the titanium alloy originally selected. In addition, the inner blanket core and magnet system of the conceptual reactor, HFCTR, developed at the Massachusetts Institute of Technology, are assumed to be interchangeable with the comparable components in NUWMAK. These variations permit a range of likely requirements to be assessed

[en] ARIES-ST is a 1000 MW fusion power plant conceptual design based on a low aspect ratio 'spherical torus' (ST) plasma. The plasma-facing components include the inboard and outboard first wall, divertor plates, and plasma stability plates. Several unique aspects of ST plasma influence the engineering design. The limited inboard space precludes a full inboard divertor slot, such that substantial power and particle flows are expected to impact the inboard first wall. Strong requirements on plasma vertical stability require close-in conductors. The use of He-cooled tungsten for the stability plates allows them to act as plasma-interactive components operating at high temperature and moderately high (1-2 MW/m²) heat flux. High plasma core radiation fraction and a natural tendency for low inboard transport losses help to alleviate these inboard problems, such that the peak power loads are not expected to exceed the capability of He-cooled tungsten and steel structures. The main features of the plasma-facing components are summarized here together with the analysis of their thermal hydraulic and thermomechanical performance

[en] ARIES-III is a conceptual, 1000-MWe, D³He, commercial tokamak-reactor design, based on extrapolation from present-day physics. The low neutron environment of the D³He-fueled ARIES-III reactor requires almost no technological development to ensure full 30-yr-lifetime performance of in-vessel components. This paper describes the fusion-power-core (FPC) component layout and the required maintenance procedures. Components were arranged to facilitate direct access to in-vessel components. This was done by subdividing in-vessel components and by minimizing outer-vessel component movement. Special consideration was also given to divertor module access so that both the supper and lower modules can be replaced without removing any other in-vessel component

[en] This paper reports on ARIES III, a conceptual design study of a 1000 MWe D-³He tokamak fusion power reactor in which most of the energy comes from charged particle transport, bremsstrahlung and synchrotron radiation, and only a small fraction (∼ 4%) comes form neutrons. This form of energy is deposited as surface heating on the chamber first wall (FW) and divertor elements, while the neutron energy is deposited as bulk nuclear heating within the shield. Since this reactor does not use tritium, there is no breeding blanket. Instead a shield is provided to protect the magnets from neutrons. The Fw is very unique in a D-³He reactor, it must be capable of absorbing the high surface heat in a mode suitable for efficient power cycle conversion, it must be able to reflect synchrotron radiation, and it must be able to withstand high current plasma disruptions. The FW is made of a low activation ferritic steel (MHT-9) and is cooled with an organic coolant (HB-40) at a pressure of 2 MPa. The FW has a coating of 0.01 cm tungsten on the MHT-9, followed by 0.15 cm of Be on the plasma side. This is needed for synchrotron radiation reflection and as a melt layer to guard against the thermal effects of a plasma disruption

[en] ARIES-ST is a 1000 MWe fusion power plant based on a low aspect ratio 'spherical torus' (ST) plasma. The ARIES-ST power core was designed to accommodate the unique features of an ST power plant, to meet the top-level requirements of an attractive fusion energy source, and to minimize extrapolation from the fusion technology database under development throughout the world. The result is an advanced helium-cooled ferritic steel blanket with flowing PbLi breeder and tungsten plasma-interactive components. Design improvements, such as the use of SiC inserts in the blanket to extend the outlet coolant temperature range were explored and the results are reported here. In the final design point, the power and particle loads found in ARIES-ST are relatively similar to other advanced tokamak power plants (e.g. ARIES-RS [Fusion Eng. Des. 38 (1997) 3; Fusion Eng. Des. 38 (1997) 87]) such that exotic technologies were not required in order to satisfy all of the design criteria. Najmabadi and the ARIES Team [Fusion Eng. Des. (this issue)] provide an overview of ARIES-ST design. In this article, the details of the power core design are presented together with analysis of the thermal-hydraulic, thermomechanical and materials behavior of in-vessel components. Detailed engineering analysis of ARIES-ST TF and PF systems, nuclear analysis, and safety are given in the companion papers

[en] The current status of fusion power research and the perception of a fusion power economy is reviewed as of early 1980. It is concluded that considerable progress has been made in the past 20 years and that by the late 1980s the achievement of energy ''break even'' could propel scientists into the commercialization stage of fusion research. Several fusion reactor designs have been reviewed and the common features used to develop an environmental and safety assessment of fusion versus other forms of energy available in the 21st century. With the existing knowledge as of 1980, it was concluded that fusion power plants will represent a much smaller environmental and safety hazard than coal or fission reactor plants even though fusion plants might be somewhat more expensive. Since this paper was written, events in the scientific community have reinforced the foregoing conclusions, and efforts are now under way to reduce even more the hazards discussed herein

[en] The ARIES-AT blanket has been developed with the overall objective of achieving high performance while maintaining attractive safety features, simple design geometry, credible maintenance and fabrication processes, and reasonable design margins as an indication of reliability. The design is based on Pb-17Li as breeder and coolant and SiC_f/SiC composite as structural material. This paper summarizes the results of the design study of this blanket

[en] As an element in the US Advanced Power Extraction (APEX) program, we evaluated the design option of using advanced nanocomposite ferritic steel (AFS) as the structural material and Flibe as the tritium breeder and coolant. We selected the recirculating flow configuration as our reference design. Based on the material properties of AFS, we found that the reference design can handle a maximum surface heat flux of 1 MW/m², and a maximum neutron wall loading of 5.4 MW/m², with a gross thermal efficiency of 47%, while meeting all the tritium breeding and structural design requirements. This paper covers the results of the following areas of evaluation: materials selection, first wall and blanket design configuration, materials compatibility, components fabrication, neutronics analysis, thermal hydraulics analysis including MHD effects, structural analysis, molten salt and helium closed cycle power conversion system, and safety and waste disposal of the recirculating coolant design