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Title: Summary of NR Program Prometheus Efforts

Abstract

The Naval Reactors Program led work on the development of a reactor plant system for the Prometheus space reactor program. The work centered on a 200 kWe electric reactor plant with a 15-20 year mission applicable to nuclear electric propulsion (NEP). After a review of all reactor and energy conversion alternatives, a direct gas Brayton reactor plant was selected for further development. The work performed subsequent to this selection included preliminary nuclear reactor and reactor plant design, development of instrumentation and control techniques, modeling reactor plant operational features, development and testing of core and plant material options, and development of an overall project plan. Prior to restructuring of the program, substantial progress had been made on defining reference plant operating conditions, defining reactor mechanical, thermal and nuclear performance, understanding the capabilities and uncertainties provided by material alternatives, and planning non-nuclear and nuclear system testing. The mission requirements for the envisioned NEP missions cannot be accommodated with existing reactor technologies. Therefore concurrent design, development and testing would be needed to deliver a functional reactor system. Fuel and material performance beyond the current state of the art is needed. There is very little national infrastructure available for fast reactor nuclear testing andmore » associated materials development and testing. Surface mission requirements may be different enough to warrant different reactor design approaches and development of a generic multi-purpose reactor requires substantial sacrifice in performance capability for each mission.« less

Authors:
 [1];  [2]
  1. Space Energy Conversion, Lockheed Martin KAPL Inc. (United States)
  2. Space Reactor Engineering, Bechtel Bettis Inc. (United States)
Publication Date:
OSTI Identifier:
21054554
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 880; Journal Issue: 1; Conference: International forum-STAIF 2007: 11. conference on thermophysics applications in microgravity; 24. symposium on space nuclear power and propulsion; 5. conference on human/robotic technology and the vision for space exploration; 5. symposium on space colonization; 4. symposium on new frontiers and future concepts, Albuquerque, NM (United States), 11-15 Feb 2007; Other Information: DOI: 10.1063/1.2437490; (c) 2007 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; COMPUTERIZED SIMULATION; CONTROL; DESIGN; ELECTRICAL PROPERTIES; ENERGY CONVERSION; EVALUATION; FAST REACTORS; FISSION; NUCLEAR FUELS; PERFORMANCE; PLANNING; PROPULSION; REACTOR OPERATION; REACTOR TECHNOLOGY; REVIEWS; SHIP PROPULSION REACTORS; TESTING; NESDPS Office of Nuclear Energy Space and Defense Power Systems

Citation Formats

Ashcroft, John, and Eshelman, Curtis. Summary of NR Program Prometheus Efforts. United States: N. p., 2007. Web. doi:10.1063/1.2437490.
Ashcroft, John, & Eshelman, Curtis. Summary of NR Program Prometheus Efforts. United States. doi:10.1063/1.2437490.
Ashcroft, John, and Eshelman, Curtis. Tue . "Summary of NR Program Prometheus Efforts". United States. doi:10.1063/1.2437490.
@article{osti_21054554,
title = {Summary of NR Program Prometheus Efforts},
author = {Ashcroft, John and Eshelman, Curtis},
abstractNote = {The Naval Reactors Program led work on the development of a reactor plant system for the Prometheus space reactor program. The work centered on a 200 kWe electric reactor plant with a 15-20 year mission applicable to nuclear electric propulsion (NEP). After a review of all reactor and energy conversion alternatives, a direct gas Brayton reactor plant was selected for further development. The work performed subsequent to this selection included preliminary nuclear reactor and reactor plant design, development of instrumentation and control techniques, modeling reactor plant operational features, development and testing of core and plant material options, and development of an overall project plan. Prior to restructuring of the program, substantial progress had been made on defining reference plant operating conditions, defining reactor mechanical, thermal and nuclear performance, understanding the capabilities and uncertainties provided by material alternatives, and planning non-nuclear and nuclear system testing. The mission requirements for the envisioned NEP missions cannot be accommodated with existing reactor technologies. Therefore concurrent design, development and testing would be needed to deliver a functional reactor system. Fuel and material performance beyond the current state of the art is needed. There is very little national infrastructure available for fast reactor nuclear testing and associated materials development and testing. Surface mission requirements may be different enough to warrant different reactor design approaches and development of a generic multi-purpose reactor requires substantial sacrifice in performance capability for each mission.},
doi = {10.1063/1.2437490},
journal = {AIP Conference Proceedings},
number = 1,
volume = 880,
place = {United States},
year = {Tue Jan 30 00:00:00 EST 2007},
month = {Tue Jan 30 00:00:00 EST 2007}
}
  • The Naval Reactors Program led work on the development of a reactor plant system for the Prometheus space reactor program. The work centered on a 200 kWe electric reactor plant with a 15-20 year mission applicable to nuclear electric propulsion (NEP). After a review of all reactor and energy conversion alternatives, a direct gas Brayton reactor plant was selected for further development. The work performed subsequent to this selection included preliminary nuclear reactor and reactor plant design, development of instrumentation and control techniques, modeling reactor plant operational features, development and testing of core and plant material options, and development ofmore » an overall project plan. Prior to restructuring of the program, substantial progress had been made on defining reference plant operating conditions, defining reactor mechanical, thermal and nuclear performance, understanding the capabilities and uncertainties provided by material alternatives, and planning non-nuclear and nuclear system testing. The mission requirements for the envisioned NEP missions cannot be accommodated with existing reactor technologies. Therefore concurrent design, development and testing would be needed to deliver a functional reactor system. Fuel and material performance beyond the current state of the art is needed. There is very little national infrastructure available for fast reactor nuclear testing and associated materials development and testing. Surface mission requirements may be different enough to warrant different reactor design approaches and development of a generic multi-purpose reactor requires substantial sacrifice in performance capability for each mission.« less
  • Several types of diamido/donor ligands have been synthesized in the last several years and attached to group 4 metal complexes, often with the intent of preparing new group 4 olefin polymerization catalysts. The authors have been interested in zirconium complexes that contain diamido/ether ligands ([(t-BuN-o-C{sub 6}H{sub 4}){sub 2}O]{sup 2{minus}} or [(ArylNCH{sub 2}CH{sub 2}){sub 2}O]{sup 2{minus}}) as catalysts for the polymerization of {alpha} olefins, especially since in the first case the polymerization of up to 500 equiv of 1-hexene has been found to take place in a living manner at 0 C via, 1,2-insertion of the olefin into the cationic alkylmore » complex. The authors became interested in diamido/donor ligands in which the central donor cannot readily attain a planar geometry. This report describes zirconium complexes that contain the [(2,4,6-Me{sub 3}C{sub 6}H{sub 2}NCH{sub 2}CH{sub 2}){sub 2}NR]{sup 1{minus}} and [Mes{sub 2}N{sub 2}NH]-HfMe{sub 2} complexes, and the activation of zirconium dimethyl complexes for the polymerization of 1-hexene at temperatures up to 30 C.« less
  • The Outstanding Achievement Award in Water Pollution Control' is intended to recognize the water pollution control program that best demonstrates achieving significant, lasting, and measurable excellence in water-quality improvement in preventing water-quality degradation in a region, basin, or water body. This article is about the 1991 Award. This year, WPCF honored Los Angeles Hyperion Treatment Plant with a citation of outstanding achievement. To qualify for this honor, Hyperion has remarkably improved the quality of wastewater discharged to Santa Monica Bay since 1985. Capital programs developed by Los Angeles to achieve this rapid improvement, coined the Hyperion Improvement Program (HIP), reflectmore » the city's commitment to protect the valuable resource of Santa Monica Bay. The HIP was conceived in 1986 to cease sludge ocean disposal by the end of 1987 and expedite effluent quality improvement before 1991, when the full secondary expansion is scheduled for completion. The program included implementing chemical addition to enhance primary treatment performance; installing fine bubble diffusers to double the level of secondary treatment from 3.38 to 8.76 m{sup 3}/s (100 to 200 mgd); increasing waste activated sludge thickening capacity to handle the doubled secondary flow; improving digester performance, increasing sludge dewatering capacity; ceasing ocean disposal of sludge; and completing a truck loading facility to support the EPA-award-winning off-site beneficial sludge reuse program. The successful HIP effort resulted in the plant's meeting more stringent 1991 discharge standards in 1986 and meeting 1998 full secondary treatment standards (except for biochemical oxygen demand) in 1989.« less
  • Three Nafion membranes of similar composition but different thicknesses were operated in a 3-cell 1kW class all vanadium mixed acid redox flow battery. The influence of current density on the charge/discharge characteristics, coulombic and energy efficiency, capacity fade, operating temperature and pressure drop in the flow circuit will be discussed and correlated to the Nafion membrane thickness. Material costs associated with the Nafion membranes, ease of handling the membranes, and performance impacts will also be discussed.