Design study of a 10-MWt reactor for space applications
Declassified 31 Aug 1973. The 10.0-MW(t) reactor-shield concept is described. The reactor is lithium-cooled and will have a fast neutron energy spectrum. It is designed to produce 10-MW(t) power for 10,000 hours with a coolant outlet temperature of 2000F using a high density UN fuel system limited by design to 1.5 a/o uranium burnup, columbium alloys for pressure vessel, core support structure and fuel element cladding, and titanium alloys for that portion of the support structure which operates below 1000F. The reactor proportions were selected from the results of the 2 to 40MW(t) radiatively-cooled reactor parametric studies and are based on the design fuel burnup limit, a maximum fuel temperature of 2300F, and the use of a radially power flattened core. The reactor concept is identical to that of the PWAR-20 reactor except that a safety rod is incorporated in the center of the core to increase the nuclear safety of the reactor during assembly and ground handling. The safety rod is ejected in orbit prior to nuclear startup. 13 references. (auth)
- Research Organization:
- Pratt and Whitney Aircraft, Middletown, Conn. (USA). Connecticut Advanced Nuclear Engineering Lab.
- DOE Contract Number:
- AT(30-1)-2789
- NSA Number:
- NSA-29-028725
- OSTI ID:
- 4330993
- Report Number(s):
- TIM-876
- Resource Relation:
- Other Information: Declassified 31 Aug 1973. Orig. Receipt Date: 30-JUN-74
- Country of Publication:
- United States
- Language:
- English
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