NDLI: A robust helium-cooled shield/blanket design for ITER

Content Provider	IEEE Xplore Digital Library
Author	Wong, C.P.C. Bourque, R.F. Baxi, C.B. Colleraine, A.P. Grunloh, H.J. Lechtenberg, T. Leuer, J.A. Reis, E.E. Redler, K. Will, R. DelBene, V. Inamati, S.B. Kapich, D.D. Kissinger, J.A. Lewis, A.C. Pickering, J.L. Rao, R. Ryder, R.H. Schleicher, R.W.
Copyright Year	1993
Description	Author affiliation: Gen. Atomics, San Diego, CA, USA (Wong, C.P.C.; Bourque, R.F.; Baxi, C.B.; Colleraine, A.P.; Grunloh, H.J.; Lechtenberg, T.; Leuer, J.A.; Reis, E.E.; Redler, K.; Will, R.; DelBene, V.; Inamati, S.B.; Kapich, D.D.; Kissinger, J.A.; Lewis, A.C.; Pickering, J.L.; Rao, R.; Ryder, R.H.; Schleicher, R.W.)
Abstract	General Atomics Fusion and Reactor Groups have completed a helium-cooled conceptual shield/blanket design for ITER. The configuration selected is a pressurized tubes design embedded in radially oriented plates. This plate can be made from ferritic steel or from V-alloy. Helium leakage to the plasma chamber is eliminated by conservative, redundant design and proper quality control and inspection programs. High helium pressure at 18 MPa is used to reduce pressure drop and enhance heat transfer. This high gas pressure is believed practical when confined in small diameter tubes. Ample industrial experience exists for safe high gas pressure operations. Inboard shield design is highlighted in this study since the allowable void fraction is more limited. Lithium is used as the thermal contacting medium and for tritium breeding. Its safety concerns are minimized by a modular, low inventory design that requires no circulation of the liquid metal for the purpose of heat removal. This design is robust, conservative, reliable and meets all design goals and requirement. It can also be built with present-day technology.
Starting Page	13
Ending Page	16
File Size	412755
Page Count	4
File Format	PDF
ISBN	0780314123
DOI	10.1109/FUSION.1993.518271
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	1993-10-11
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Robustness Fusion reactor design Helium Plasma confinement Atomic measurements Inductors Steel Plasma applications Quality control Inspection
Content Type	Text
Resource Type	Article

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