The Prometheus IFE REACTOR CAVITY*

M. S. Tillack, N. Ghoniem, A. R. Raffray, M. A. Abdou,
and the Prometheus Team

Mechanical, Aerospace and Nuclear Engineering Department
University of California, Los Angeles, CA 90024

The design of a wetted wall reactor cavity was undertaken at UCLA as a part of the Prometheus Inertial Fusion Energy (IFE) reactor study. The preliminary design has been described previously. In this paper, we review the final design concept and summarize the results of detailed analysis on several of the key aspects of the cavity design, including cavity vapor hydrodynamics, cavity clearing and repetition rate limits, film flow characteristics, mechanical response of the first wall system, thermalhydraulics of the low-pressure blanket cooling system, and safety and environmental analyses.

The design philosophy led us to some unique design features. The desire for inherent safety and minimum activation was a top priority. Material choices for the first wall, blanket, and shield were all influenced. The first wall consists of low-activation SiC composite. Both long-term and short- term activation is small, minimizing waste disposal problems and providing negligible decay heat. Li and LiPb were rejected for safety reasons in favor of a Pb wall protectant. Pb has toxicity and radioactivity concerns, but these were carefully estimated and minimized in the design. The blanket also uses SiC structure and reflector, with low-activation Li2O breeder and He coolant. Care was taken to minimize the tritium inventory in the breeder. Use of He at relatively low pressure, together with mul-tiple containment barriers, makes blanket failures unlikely and the consequences benign. The shield material also was chosen to reduce activation. Instead of concrete, Prometheus uses an innovative, highly-effective shield consisting of Al structure, water coolant, and B4C, Pb, and SiC absorbers.

While not all of the design choices use proven technologies, an attempt was made to minimize required R&D and technical risk by adopting near-term technologies that can be extrapolated from existing data. SiC composites are commercially available today, although some development will be required for use in a neutron radiation environment. Pb has been used as a coolant in the past and technologies for using liquid metal as a coolant are well-developed. Similarly, in the blanket, He cooling is an established technology and the data base for Li2O is being rapidly developed for the MFE fusion program. The R&D needs are bounded and predictable, since the extrapolation from existing technologies is minimized.

*Work supported by USDOE contract #DE-AC02-90ER54101


M. S. Tillack
44-139 E4, MANE Dept.
University of California, Los Angeles
Los Angeles, CA 90024-1597
(310) 206-1230
FAX (310) 825-2599
e-mail: tillack@fusion.ucla.edu

Category #11

Please associate this paper with that of M. A. Abdou on the IFE reactor design study.