Neutronic Design and Optimization of a Porous-fuel, High-temperature, Gas-cooled Reactor for Space Power and Propulsion Applications


Book Description

ABSTRACT: Nuclear reactors are currently being considered for space power and propulsion applications. The system we examined uses a porous fuel matrix as the thermal interchange medium. Its intended use is in thermal propulsion systems, but it can also be applied to electric propulsion systems, and as a source of auxiliary power. The reactor would be used as a power source for interplanetary robotic or manned missions. Our goal was to develop an optimized relation between fuel density and reactor dimensions.




NASA Technical Note


Book Description







Scientific and Technical Aerospace Reports


Book Description

Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.







Space Nuclear-power Reactor Design Based on Combined Neutronic and Thermal-fluid Analyses


Book Description

The design and performance analysis of a space nuclear-power system requires sophisticated analytical capabilities such as those developed during the nuclear rocket propulsion (Rover) program. In particular, optimizing the size of a space nuclear reactor for a given power level requires satisfying the conflicting requirements of nuclear criticality and heat removal. The optimization involves the determination of the coolant void (volume) fraction for which the reactor diameter is a minimum and temperature and structural limits are satisfied. A minimum exists because the critical diameter increases with increasing void fraction, whereas the reactor diameter needed to remove a specified power decreases with void fraction. The purpose of this presentation is to describe and demonstrate our analytical capability for the determination of minimum reactor size. The analysis is based on combining neutronic criticality calculations with OPTION-code thermal-fluid calculations.




Liquid Metal Cooled Reactors


Book Description

Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.