An Integrated Analysis of a NERVA Based Nuclear Thermal Propulsion System
- Energy Sciences and Technology Department, Brookhaven National Laboratory, Upton, NY 11973 (United States)
This paper presents results and conclusions derived from an integrated analysis of a NERVA based Nuclear Thermal Propulsion (NTP) system. The NTP system is sized to generate a thrust of 70,000 N (15,000 lbf), and have a specific impulse (Isp) of 860 s. This implies a reactor that operates at 350 MWth and has a mixed mean propellant outlet temperature of 2760 K. The integrated analysis will require that self-consistent neutronic/thermal-hydraulic/stress analyses be carried out. The major code packages used in this analysis are MCNP, RELAP, and ANSYS. Results from this analysis indicate that nuclear data will have to be re-generated to cover the wide temperature range, zone loading will be necessary to avoid entering the liquidus region for the fuel, and the effectiveness of the ZrC insulator will have implications for bi-modal applications. These results suggest a path forward in the development of a viable NTP system based on a NERVA reactor should initially concentrate on fuel and structural materials and associated coating development. A series of safety related criticality determinations were carried out addressing water immersion following a launch incident.
- OSTI ID:
- 20798023
- Journal Information:
- AIP Conference Proceedings, Vol. 813, Issue 1; Conference: 10. conference on thermophysics applications in microgravity; 23. symposium on space nuclear power and propulsion; 4. conference on human/robotic technology and the national vision for space exploration; 4. symposium on space colonization; 3. symposium on new frontiers and future concepts, Albuquerque, NM (United States), 12-16 Feb 2006; Other Information: DOI: 10.1063/1.2169269; (c) 2006 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
Similar Records
Assessment of Near-Term Fuel Screening and Qualification Needs for Nuclear Thermal Propulsion Systems
Design and out-of-pile testing of a novel irradiation experiment vehicle to support qualification of nuclear thermal propulsion components
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BUILDING MATERIALS
CRITICALITY
DESIGN
FISSION
NERVA REACTOR
NUCLEAR FUELS
PROPULSION
PROPULSION SYSTEMS
PULSES
REACTOR SAFETY
STRESS ANALYSIS
THERMAL HYDRAULICS
WATER
ZIRCONIUM CARBIDES
NESDPS Office of Nuclear Energy Space and Defense Power Systems