C. P. C. Wong

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An attractive blanket concept for the fusion reactor is the dual coolant Pb–17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb–17Li is circulated for power conversion and for tritium breeding. A SiCf/SiC(More)
Testing blanket concepts in the integrated fusion environment is one of the principal objectives of ITER. Blanket test modules will be inserted in ITER from Day 1 of its operation and will provide the first experimental data on the feasibility of the D-T cycle for fusion. With the US rejoining ITER, the US community has decided to have strong participation(More)
General Atomics, P.O. Box 85608, San Diego, California 92186-5608, Clement.Wong@gat.com 1Fusion Nuclear Technology Consulting, Linkenheim, Germany 2University of Wisconsin, Madison, Wisconsin 3University of California, Los Angeles, California 4Argonne National Laboratory, Argonne, Illinois 5INEEL, Idaho Falls, Idaho 6University of California, San Diego,(More)
The advanced limiter-divertor plasma-facing systems (ALPS) program was initiated in order to evaluate the potential for improved performance and lifetime for plasma-facing systems. The main goal of the program is to demonstrate the advantages of advanced limiter/divertor systems over conventional systems in terms of power density capability, component(More)
Under the APEX program the He-cooled system design task is to evaluate and recommend high power density refractory alloy first wall and blanket designs and to recommend and initiate tests to address critical issues. We completed the preliminary design of a helium-cooled, W–5Re alloy, lithium breeder design and the results are reported in this paper. Many(More)
First wall and blanket (FW/blanket) design is a crucial element in the performance and acceptance of a fusion power plant. High temperature structural and breeding materials are needed for high thermal performance. A suitable combination of structural design with the selected materials is necessary for D /T fuel sufficiency. Whenever possible, low(More)
This paper summarizes the most recent design activities concerning the use of SiCf/SiC composite as structural material for fusion power reactor breeding blanket. Several studies have been performed in the past. The most recent proposals are the TAURO blanket concept in the European Union, the ARIES-AT concept in the US, and DREAM concept in Japan. The(More)
The objective of the Fusion Development Facility (FDF) under consideration is to fill the gaps between ITER and current experiments and a fusion demonstration power plant (DEMO). FDF should carry forward advanced tokamak (AT) physics and enable development of fusion's energy applications. Near-term AT physics and nonsuperconducting magnet technology will be(More)
This study, called APEX, is exploring novel concepts for fusion chamber technology that can substantially improve the attractiveness of fusion energy systems. The emphasis of the study is on fundamental understanding and advancing the underlying engineering sciences, integration of the physics and engineering requirements, and enhancing innovation for the(More)