Abstract: The present disclosure is directed to a system including a nuclear thermal rocket or a nuclear reactor, at least one nuclear electric thruster coupled to the nuclear thermal rocket or the nuclear reactor, and a Nuclear Thermionic Avalanche Cell (NTAC) configured to generate electrical power. The NTAC cell may be positioned around a nuclear reactor core of the nuclear thermal rocket or the nuclear reactor, and the nuclear electric thruster may be powered by the NTAC generated electrical power.

Abstract: According to an embodiment, a pressurized water reactor plant has a primary system which includes: a reactor vessel for housing a reactor core which is cooled by a primary coolant, a single steam generator, a hot leg pipe for connecting the reactor vessel and the steam generator, cold leg pipes, at least two primary coolant pumps, and a pressurizer for pressurizing the primary coolant pressure boundary in which the primary coolant flows. The plant also has: a passive cooling and depressurization system which is a primary depressurization means for equalizing the primary system pressure to the secondary system pressure at the time of a tube rupture accident of the steam generator, and a reactor containment vessel containing the primary system and cooling the primary system by air cooling. Thus, a compact pressurized water rector with high economic efficiency, safety, and reliability can be provided.

Abstract: A nuclear reactor includes a reflector and a flow path. The reflector reflects neutrons, contains graphite and a moderator having a smaller moderating power than the graphite, and is sectioned into plural parts along a direction of flow of fuel pebbles. The flow path is surrounded by the reflector, and the fuel pebbles flow through the flow path and undergo nuclear reaction to generate power. Volume ratio of the graphite to the moderator having a smaller moderating power than the graphite in each part of the reflector is determined based on a power distribution in the reactor core in the direction of flow of the fuel pebbles.

Abstract: A high-temperature nuclear reactor, cooled by a liquid fluoride salt, is described. The reactor uses an annular fuel pebble comprised of an inert graphite center kernel, a TRISO fuel particles region, and a graphite outer shell, with an average pebble density lower than the density of the liquid salt so the pebbles float. The pebbles are introduced into a coolant entering the reactor and are carried into the bottom of the reactor core, where they form a pebble bed inside a plurality of vertical channels inside one or more replaceable Pebble Channel Assemblies (PCAs). Pebbles are removed through defueling chutes located at the top of each PCA. Each PCA also includes channels for insertion of neutron control and shutdown elements, and channels for insertion of core flux mapping and other instrumentation.

Abstract: An improved nuclear fission reactor of the continuous fueling type involves determining an asymptotic equilibrium state for the nuclear fission reactor and providing the reactor with a moderator-to-fuel ratio that is optimally moderated for the asymptotic equilibrium state of the nuclear fission reactor; the fuel-to-moderator ratio allowing the nuclear fission reactor to be substantially continuously operated in an optimally moderated state.

Abstract: A guide ring is positioned in the reactor core vessel of a pebble-bed nuclear reactor to segregate fuel pebbles and reflector pebbles fed into the vessel through respective conduits. The reflector pebbles pass through the guide ring and form a central reflector column, while the fuel pebbles pass outside the guide ring and form an annular fuel column surrounding the central reflector column. The guide ring controls the size and shape of the reflector column and controls mixing of the two types of pebbles.

Abstract: A bimodal nuclear power and propulsion system for space is disclosed. Closed cycle heat engines are in operative association with each sector of a sectored reactor core. Heat exchangers employing waste heat, electric power and reactor heat are used to heat propellant to increase Isp. Non-nuclear ground testing of the system is also disclosed.

Abstract: A nuclear propulsion reactor. A reactor vessel is provided with an annular first core and a cylindrical second core that is radially encompassed by the first core. Nuclear fuel elements in the first core provide first stage heating of propellant as they direct the propellant axially through the first core. The second core, which contains fissionable material in a highly refractory form, is in fluid communication with the first core for receiving the heated propellant. Fission reactions in the second core driven by leakage neutrons from the first core provide second stage heating of the propellant as it passes therethrough. The second core directs the coolant to a propellant nozzle for providing propulsive thrust.

Abstract: A multiplicity of pebble-bed cores are housed within separate concrete cavities of a multi-cavity prestressed concrete pressure vessel. Primary cooling systems, one for each pebble-bed core, are supported within another cavity which is coaxial with the longitudinal axis of the prestressed concrete pressure vessel. Tunnel ducts formed within the walls of the concrete vessel communicate between the cavities which house the pebble-bed cores and the cavity which houses the primary cooling systems. Pipes connecting the cores to the primary cooling systems pass through these ducts.

Abstract: A lightweight three sector reactor for use in space. The three sectors provide redundancy for safety and operation assurance. The reactor can be launched empty or fueled and can be fueled, emptied, and refueled while in space. The reactor can be used to power manned space platforms.

Abstract: A nuclear fuel element for a particle bed reactor. Concentric inner and outer porous cylinders attached at either end define an annulus therebetween that contains a fuel particle bed of nuclear fuel material. The outer porous cylinder is provided with fins that extend radially outward along its entire length. A nonporous cylinder is attached to the outer porous cylinder at either end and is positioned around the outer porous cylinder so as to be concentric therewith. Flexible fins extend radially inward form the nonporous cylinder along its entire length and contact the fins on the outer porous cylinder for conduction of heat to heat removal tubes on the outer surface of the nonporous cylinder. The heat removal tubes allow bimodal cooling of the particle bed reactor.

Abstract: A multi-region reactor core pebble bed high temperature gas reactor comprises a pebble bed reactor core housed within a pressure vessel and charged with spherical fuel. The reactor core is surrounded by a reflector wall comprising a partition wall which partitions the reactor core into a plurality of reactor core sub-regions. The reflector wall comprises a plurality of layers of reflector blocks, adjacent blocks of a layer being secured against one another by removable tapered keys wedged therein between.