Overview of materials technologies for space nuclear power and propulsion

Details Overview of materials technologies for space nuclear power and propulsion Overview of materials technologies for space nuclear power and propulsion

Jan 2002

adsabs.harvard.edu/cgi-bin/nph-data_query?bibcode=2002aipc..608.1063z&link_type=abstract

SPACE TECHNOLOGY AND APPLICATIONS INTERNATIONAL FORUM- STAIF 2002. Conference on Thermophyiscs in Microgravity; Conference on In

Statistics

Applications

1

Propulsion Reactors, Power And Production Reactors, Spaceborne And Space Research Instruments, Apparatus, And Components

Scientific paper

A wide range of different space nuclear systems are currently being evaluated as part of the DOE Special Purpose Fission Technology program. The near-term subset of systems scheduled to be evaluated range from 50 kWe gas-, pumped liquid metal-, or liquid metal heat pipe-cooled reactors for space propulsion to 3 kWe heat pipe or pumped liquid metal systems for Mars surface power applications. The current status of the materials technologies required for the successful development of near-term space nuclear power and propulsion systems is reviewed. Materials examined in this overview include fuels (UN, UO2, UZrH), cladding and structural materials (stainless steel, superalloys, refractory alloys), neutron reflector materials (Be, BeO), and neutron shield materials (B4C,LiH). The materials technologies issues are considerably less demanding for the 3 kWe reactor systems due to lower operating temperatures, lower fuel burnup, and lower radiation damage levels. A few reactor subcomponents in the 3 kWe reactors under evaluation are being used near or above their engineering limits, which may adversely affect the 5 to 10 year lifetime design goal. It appears that most of these issues for the 3 kWe reactor systems can be accommodated by incorporating a few engineering design changes. Design limits (temperature, burnup, stress, radiation levels) for the various materials proposed for space nuclear reactors will be summarized. For example, the temperature and stress limits for Type 316 stainless steel in the 3 kWe Na-cooled heat pipe reactor (Stirling engine) concept will be controlled by thermal creep and CO2 corrosion considerations rather than radiation damage issues. Conversely, the lower operating temperature limit for the LiH shield material will likely be defined by ionizing radiation damage (radiolysis)-induced swelling, even for the relatively low radiation doses associated with the 3 kWe reactor. .

Affiliated with

Also associated with

No associations

Rating

Overview of materials technologies for space nuclear power and propulsion does not yet have a rating. At this time, there are no reviews or comments for this scientific paper.

If you have personal experience with Overview of materials technologies for space nuclear power and propulsion, we encourage you to share that experience with our LandOfFree.com community. Your opinion is very important and Overview of materials technologies for space nuclear power and propulsion will most certainly appreciate the feedback.

Rate now

Comments { 0 }

Profile ID: LFWR-SCP-O-1086488