2006 - NR Papers for Project Prometheus for STAIF Conference

This KAPL letter (SPP-SEC-0039) dated April 10, 2006 provides internal documentation of the papers and presentations prepared by KAPL and Bettis for the 2006 Space Technology and Applications International Forum (STAIF) conference that summarize our work on the Prometheus Project space reactor development. Eighteen presentations and six papers were prepared and approved for public utterance.

The presentations cover:

1) The project overview and the reactor design features

2) The reactor plant and instrumentation development work

3) Hydraulic and reactor plant transient modeling

4) Reactor core and plant materials (two sessions)

The intent of the papers and presentations is to provide future space reactor developers an overview of the Naval Reactors program work on Project Prometheus and direct them to the more complete documentation that will be stored in the Office of Scientific and Technology Information (OSTI) Database. The reference above summarizes the Project Prometheus development work.

Included were the following papers:

1. Summary of NR Program Prometheus Efforts

2. Aspects of Gas Reactor Physics for NRPCT Project Prometheus Applications

3. Reactor Mechanical Design Concept and Performance

4. Key Factors Influencing the Decision on the Number Brayton Units for the Prometheus Space Reactor

5. Pressure Vessel and Reflector Temperature Sensitivity Studies of a Notional Gas-Cooled Space Reactor

6. Prometheus Hot Leg Piping Concept

7. Reactor Instrumentation and Control: Systems and Sensors

8. Fuel for Thought: Considerations for a Space Nuclear Reactors

9. Summary of Structural Material Considerations for Prometheus Space Nuclear Power

10. Mass Transport Modeling and Supporting Experimental Tasks for the Prometheus Space Reactor System

11. Compatibility of Space Nuclear Power Plant Materials in an Inert He/Xe Working Gas Containing Reactive Impurities

12. Use of RELAP5-3D for Dynamic Analysis of a Closed-Loop Brayton Cycle Coupled to a Nuclear Reactor

13. Ex-core CFD Analysis Results for the Prometheus Gas Reactor

14. Review of Helium and Xenon Pure Component and Mixture Transport Properties and Recommendation of Estimating

15. Modeling Compact Counter-Flow Heat Exchangers with RELAP5-3D

16. NRPCT Perspective on Lithium Hydride for Use in a Space Shield

17. Reflector Material Selection for Space Nuclear Applications

18. Assessing the Radiation Damage of Ni-base Superalloys for Prometheus Space Nuclear Power