In this sbir, ultra safe nuclear corporation (usnc) will investigate and develop a set of novel technologies to minimize the amount of hydrogen needed for reactor decay heat removal after the shutdown…

This federal contract was awarded by the National Aeronautics and Space Administration (NASA) Shared Services Center to Ultra Safe Nuclear Corporation (USNC) under the Small Business Innovation Research (SBIR) program. The $124,589.00 firm-fixed-price contract is for Phase I research and development of technologies to minimize the amount of hydrogen needed for decay heat removal in nuclear thermal propulsion (NTP) systems after reactor shutdown. USNC's proposed solution aims to maximize the temperature of ejected hydrogen and heat radiation from the rocket and nozzle, as well as generate small amounts of electrical power from the removed decay heat. The contract has a total small business set-aside designation.

In this sbir, ultra safe nuclear corporation (usnc) will investigate and develop a set of novel technologies to minimize the amount of hydrogen needed for reactor decay heat removal after the shutdown of nuclear thermal propulsion (NTP) systems. Decay heat is the energy deposited during the decay of radioactive fission products after the reactor shuts down. Its management is a critical issue for NTP systems. Usnc s technology will be an effective, yet simple, solution to address decay heat removal. Central to usnc s optimized strategy for decay heat removal is maximizing the temperature that hydrogen is ejected and maximizing radiative heat transfer from the available surfaces of the rocket and nozzle. Furthermore, usnc s comprehensive solution generates small amounts of electrical power with the removed decay heat, increasing mission flexibility and resilience. Specifically, usnc will primarily investigate four technologies to minimize hydrogen usage: - the inclusion of coolant channels on the outside structure of the tie tube between the insulator and fuel that can heat hydrogen to hotter temperatures than the zirconium hydride moderator can maintain. - circulating hydrogen through the tie tube and the outer structure of the core to maximize heat rejection by radiation. - conversion of some of the heat into useful work through the addition of a power generation unit. - using computationally-intensive optimization to find the best possible strategies and power cycle configurations to minimize the amount of hydrogen ejected from the system.