The following research is currently ongoing within MIT AeroAstro, NSE, or both collaboratively:
Surface Fission Power for Future Human Missions
Primary lab affiliation: Engineering Systems Laboratory
Abstract:
Past and current studies have highlighted the use of nuclear surface fission power to support human missions to the surface of Moon and Mars. In December 2024, NASA released a White Paper stating that nuclear fission power has been selected as the “primary surface power generation technology for crewed missions to Mars” . While this decision does not limit the use of other surface power generation technologies (such as solar power and fuel cells etc…), it does underline a necessity for research at the intersection of nuclear technology and human spaceflight, which my research aims to do. Thus, the main research question my work addresses is: “What Lunar and Martian nuclear surface power architectures can fulfill the power demands for human missions?”. Tackling this research question involves modeling and quantifying how much power is needed to support Lunar and Martian human mission architectures (i.e., power demand for life support, thermal control, ISRU, crop growth etc… ), understanding the stakeholder high priority attributes for nuclear power architectures, exploring the launch vehicle/lander trade space for sending space nuclear reactors to the Lunar/Martian surface, and evaluating the space/nuclear policy impacts on potential nuclear power architectures.
See: Charoenboonvivat, Yana, Susan S. Voss, Olivier L. de Weck, and Daniel Hastings. “Comparing Mission Architectures to Support Lunar Surface Fission Power.” In AIAA AVIATION FORUM AND ASCEND 2024, p. 4886. 2024.
Point of contact: Yana Charoenboonvivat <yanac@mit.edu>
Development and Certification of Core Materials for NTP and FSP
Primary lab affiliation: Nuclear Innovation Fission Technologies
Abstract:
One challenging aspect of developing Nuclear Thermal Propulsion (NTP) capabilities is testing potential fuel materials. A series of tests has been developed to utilize the MIT Reactor (MITR) facilities to simulate a hydrogen rich, high temperature environment in the presence of a neutron flux in support of fuel material testing. First, a UN fuel element will be placed in the 3GV6 position of the graphite reflector surrounding MITR. The UN fuel in the presence of a neutron flux will produce sufficient heat to achieve a peak hydrogen temperature of 3000 K. Next, a NTP core will be assembled in-situ in the MITR M3 facility, where the neutron flux from MITR will again be used to provide the requisite neutron flux to achieve the desired operating temperature. In both experiments, closed loop hydrogen handling systems are proposed in order to cool the reactor exhaust to manageable temperatures while also providing the necessary hydrogen flow for material testing. In the case of the 3GV6 experiment, expected heat generation is on the order of kilowatts. Therefore, a heat cycle with a single heat exchanger and exhaust gas cooling flow is adequate to reject waste heat. For the M3 experiments, the required heat generation is on the order of megawatts and requires a heat cycle containing a regenerator, a secondary Helium cooling loop, and high temperature materials. Both experiments are intended to aid in development and certification of core materials for National Aeronautics and Space Administration (NASA) related activities in NTP and Fission Surface Power.
Point of contact: Patrick Riley<pdriley@mit.edu>
Progress toward Transient System Modeling of the Centrifugal Nuclear Thermal Rocket
Primary lab affiliation: Nuclear Innovation Fission Technologies
Abstract:
Traditional solid-core Nuclear Thermal Propulsion (NTP) engines have a specific impulse (Isp) ceiling set by the fuel core melting temperature and thermal stresses. The Centrifugal Nuclear Thermal Rocket (CNTR) engine flows propellant through centrifugally confined liquid uranium to enable high temperature exhaust and thus high Isp operation. Most CNTR research has focused on the engine’s thermal-hydraulic and neutronic performance at steady state. However, to fully assess the CNTR’s technological feasibility and inform system architecture choices, we must better understand the challenges associated with engine startup and shutdown.
Several CNTR startup challenges exist that will affect engine startup architecture selection. One includes whether the moderator, reflector, and rocket nozzle require cooling during startup. Such cooling would elucidate whether the addition of pre-manufactured holes in the Centrifugal Fuel Elements (CFEs) is required and if gas may be used to spin-start the CFEs. Another challenge involves the quantity of spin-start gas or propellant required for the Centrifugal Fuel Elements (CFEs) to reach steady-state speeds. A third challenge concerns the Silicon Carbide (SiC) porous media that confines the liquid uranium. SiC can amorphize when irradiated at low temperatures. Determining the radiation damage rate during startup can inform whether a pre-heating system is needed to prevent amorphization and subsequent loss of the SiC porous media’s mechanical properties.
Point of contact: Taylor Hampson <thampson@mit.edu>
Aircraft Nuclear Propulsion
Primary lab affiliation: MIT Gas Turbines Laboratory (MIT-GTL)
Description:
Jake Hecla <jakehecla@gmail.com> is a Stanton Postdoctoral Fellow in Nuclear Security at the Laboratory for Nuclear Security and Policy at MIT. His work focuses on the technical characteristics, signatures and deterrence impacts of air-breathing nuclear propulsion, an emerging technique for high-persistence flight. The ongoing development of the Burevestnik nuclear-armed, nuclear-powered cruise missile has generated unique detection and countermeasure challenges. To better understand this system and to gain insight into future applications of air-breathing nuclear propulsion, Hecla has developed tools for predicting nuclear engine performance that couple thermodynamic cycle modelling and neutronics. This work has been performed in close cooperation with the MIT Gas Turbines Laboratory (MIT-GTL), and has expanded to include studies of civilian applications of nuclear propulsion.