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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:
;
Publication Date:
Research Org.:
Knolls Atomic Power Laboratory (KAPL), Niskayuna, NY
Sponsoring Org.:
USDOE
OSTI Identifier:
881290
Report Number(s):
LM-05K188
TRN: US0602908
DOE Contract Number:
DE-AC12-00SN39357
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; DESIGN; ENERGY CONVERSION; FAST REACTORS; FUNCTIONALS; PERFORMANCE; PLANNING; PROPULSION; REACTORS; SHIP PROPULSION REACTORS; SIMULATION; TESTING; NESDPS Office of Nuclear Energy Space and Defense Power Systems

Citation Formats

J Ashcroft, and C Eshelman. Summary of NR Program Prometheus Efforts. United States: N. p., 2006. Web. doi:10.2172/881290.
J Ashcroft, & C Eshelman. Summary of NR Program Prometheus Efforts. United States. doi:10.2172/881290.
J Ashcroft, and C Eshelman. Wed . "Summary of NR Program Prometheus Efforts". United States. doi:10.2172/881290. https://www.osti.gov/servlets/purl/881290.
@article{osti_881290,
title = {Summary of NR Program Prometheus Efforts},
author = {J Ashcroft and C Eshelman},
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 = {10.2172/881290},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Feb 08 00:00:00 EST 2006},
month = {Wed Feb 08 00:00:00 EST 2006}
}

Technical Report:

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  • 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
  • This report summarizes the results of efforts by the DNA Ground Shock Simulation community to develop design techniques and predictive methods for producing crater-related motions using the Direct Induced High Explosive Simulation Techniques (DIHEST). The work was performed by several investigators under the sponsorship of DNA, and was subjected to review and comment in the forum of the Advanced Silo Hardening (ASH) Simulation Working Group. The report briefly presents the evolutionary steps involved in reading improved predictive methods, and the relationships for those methods are re-developed. A summary of the DIHEST data used during the development along with recent experimentalmore » data are provided along with some comments on the applicability of prior experiments.« less
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