Design Options for a Versatile Nuclear Thermal Propulsion (NTP) Stage
No abstract available
Houts, Mike↗
Engineering topics
Eades, Michael
Publications and source records attributed to Eades, Michael.
Comparing Low Enriched Fuel to Highly Enriched Fuel for use in Nuclear Thermal Propulsion Systems
Low enriched uranium (LEU) is an economically and politically friendly alternative to highly enriched uranium (HEU) that can enable the use of nuclear thermal propulsion (NTP) systems. Historically, only HEU reactors were considered for NTP due to need of minimum mass systems and the common perception that HEU nuclear cores will always make smaller reactors than LEU cores. However, recent studies have shown LEU NTP systems can be created to enable human Mars missions. These studies do not show the performance losses or gains when using an LEU system rather than an HEU system. The goal of this paper is to present four optimized NTP systems designed for the same 16,000 lbs-f thrust, with a combination of minimum mass and high specific impulse. The four designs differ in the nuclear fuel type; two contain a carbide composite fuel that is derived from historical experiments and two contain tungsten cermet fuel which has become a good fuel choice given advances in manufacturing techniques. Within each fuel type, LEU or HEU will be used. The final paper will contain core design details such as fuel dimensions, enrichment profiles, fuel layout and thermal design details including core pressure drops and hydrogen outlet conditions. Similar performances are found between HEU and LEU designs.
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
SPOC Benchmark Case: SNRE Model
The Small Nuclear Rocket Engine (SNRE) was modeled in the Center for Space Nuclear Research’s (CSNR) Space Propulsion Optimization Code (SPOC). SPOC aims to create nuclear thermal propulsion (NTP) geometries quickly to perform parametric studies on design spaces of historic and new NTP designs. The SNRE geometry was modeled in SPOC and a critical core with a reasonable amount of criticality margin was found. The fuel, tie-tubes, reflector, and control drum masses were predicted rather well. These are all very important for neutronics calculations so the active reactor geometries created with SPOC can continue to be trusted. Thermal calculations of the average and hot fuel channels agreed very well. The specific impulse calculations used historically and in SPOC disagree so mass flow rates and impulses differed. Modeling peripheral and power balance components that do not affect nuclear characteristics of the core is not a feature of SPOC and as such, these components should continue to be designed using other tools. A full paper detailing the available SNRE data and comparisons with SPOC outputs will be submitted as a follow-up to this abstract.
MCNP↗
SCCTE: An LEU NTP Concept with Tungsten Cermet Fuel
Presented in this paper is the Space Capable Cryogenic Thermal Engine (SCCTE), a Low Enriched Uranium (LEU) W-UO2 cermet fuel, ZrH1.8 moderated Nuclear Thermal Propulsion (NTP) Concept. The SCCTE project was undertaken by a collaboration with NASA Marshall Space Flight Center (MSFC) and Center for Space Nuclear Research (CSNR) to investigate the applicability of LEU cermet NTP technology for a human Mars mission in the 2030's time frame. This paper focuses on the nuclear design aspects of SCCTE.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Center for Space Nuclear Research (CSNR) NTP Design Team Report
The CSNR NTR Design Team has developed a history of collaboration with NASA Marshall Spaceflight Center (MSFC). First assembled in the summer of 2013 to explore the concept of the Low-Enriched Uranium Nuclear Thermal Rocket (LEU-NTR), the team continued research to find solutions with guiding Nuclear Thermal Propulsion (NTP) technological development and provide design and analysis support for the Space Capable Cryogenic Thermal Engine (SCCTE) Project. The work presented in this report provides a background on the cermet LEU-NTR, summarizes work complete to explore a new design space for NTRs, and describes the SCCTE core that was developed.
33 ADVANCED PROPULSION SYSTEMS↗
A Potential NASA Research Reactor to Support NTR Development
In support of efforts for research into the design and development of a man rated Nuclear Thermal Rocket (NTR) engine, the National Aeronautics and Space Administration (NASA), Marshall Space Flight Center (MSFC), is evaluating the potential for building a Nuclear Regulatory Commission (NRC) licensed research reactor. The proposed reactor would be licensed by NASA and operated jointly by NASA and university partners. The purpose of this reactor would be to perform further research into the technologies and systems needed for a successful NTR project and promote nuclear training and education.
Eades, Michael↗