Publication Date:
2011-08-24
Description:
An account is given of the significance for U.S. spacecraft development of a nuclear thermal rocket (NTR) reactor concept that has been developed in the (formerly Soviet) Commonwealth of Independent States (CIS). The CIS NTR reactor employs a hydrogen-cooled zirconium hydride moderator and ternary carbide fuels; the comparatively cool operating temperatures associated with this design promise overall robustness.
Keywords:
SPACECRAFT PROPULSION AND POWER
Type:
Aerospace America (ISSN 0740-722X); 31; 7; p. 28-30, 35.
Format:
text
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