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Nuclear Design of a Vapor Core Reactor for Space Nuclear Propulsion

Conference · · AIP Conference Proceedings
DOI:https://doi.org/10.1063/1.43212· OSTI ID:5460740
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  1. Univ. of Florida, Gainesville, FL (United States). Innovative Nuclear Space Power and Propulsion Inst.
Neutronic analysis methodology and results are presented for the nuclear design of a vapor core reactor for space nuclear propulsion. The Nuclear Vapor Thermal Reactor (NVTR) Rocket Engine uses modified NERVA geometry and systems which the solid fuel replaced by uranium tetrafluoride vapor. The NVTR is an intermediate term gas core thermal rocket engine with specific impulse in the range of 1000--1200 seconds; a thrust of 75,000 lbs. for a hydrogen flow rate of 30 kg/s; average core exit temperatures of 3100 K to 3400 K; and reactor thermal powers of 1400 to 1800 MW. Initial calculations were performed on epithermal NVTRs using Zirconium Carbide (ZrC) fuel elements. Studies are now directed at thermal NVTRs that use fuel elements made of Carbon-Carbon (C-C) composite. The large ZrC-moderated reactors resulted in thrust-to-weight ratios of only 1 to 2; the compact C-C composite systems yield thrust-to-weight ratios of 3 to 5.
Research Organization:
Univ. of Florida, Gainesville, FL (United States). Innovative Nuclear Space Power and Propulsion Inst.
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
OSTI ID:
5460740
Report Number(s):
CONF-930103--
Conference Information:
Journal Name: AIP Conference Proceedings Journal Issue: 2 Journal Volume: 271
Country of Publication:
United States
Language:
English