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R.W. Schleicher

General Atomics

7

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47

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Evaluation of U.S. Demo helium-cooled blanket options

1995 ISFE | International Symposium on Fusion Engineering
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A robust helium-cooled shield/blanket design for ITER

1993 SFE | IEEE/IPSS Symposium on Fusion Engineering
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Limitations of power conversion systems under transient loads and impact on the pulsed tokamak power reactor

1993 SFE | IEEE/IPSS Symposium on Fusion Engineering
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TRIGA power system for power, water and heat in remote communities

1992
- R.W. Schleicher
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An international assessment of the gas tubine MHTGR

1992
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