Cermet-fueled reactors for advanced space applications

Conference · Tue Dec 01 04:00:00 EST 1987

OSTI ID:5529665

Cowan, C L; Palmer, R S; Taylor, I N; Vaidyanathan, S; Bhattacharyya, S K; Barner, J O

Cermet-fueled nuclear reactors are attractive candidates for high-performance advanced space power systems. The cermet consists of a hexagonal matrix of a refractory metal and a ceramic fuel, with multiple tubular flow channels. The high performance characteristics of the fuel matrix come from its high strength at elevated temperatures and its high thermal conductivity. The cermet fuel concept evolved in the 1960s with the objective of developing a reactor design that could be used for a wide range of mobile power generating sytems, including both Brayton and Rankine power conversion cycles. High temperature thermal cycling tests for the cermet fuel were carried out by General Electric as part of the 710 Project (General Electric 1966), and by Argonne National Laboratory in the Direct Nuclear Rocket Program (1965). Development programs for cermet fuel are currently under way at Argonne National Laboratory and Pacific Northwest Laboratory. The high temperature qualification tests from the 1960s have provided a base for the incorporation of cermet fuel in advanced space applications. The status of the cermet fuel development activities and descriptions of the key features of the cermet-fueled reactor design are summarized in this paper.

• Research Organization: General Electric Co., San Jose, CA (USA). Astro Space Div.; Argonne National Lab., IL (USA); Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5529665
• Report Number(s): PNL-SA-15224; CONF-880122-8; ON: DE88005528
• Country of Publication: United States
• Language: English

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