Abstract: A rod position indication system includes a drive rod operably coupled to a control rod that is configured to be both withdrawn from and inserted into a reactor core. A number of sensing devices are arranged along a path of the drive rod, and an end of the drive rod passes by or through one or more of the sensing devices in response to movement of the control rod relative to the reactor core. The sensing devices are arranged into a plurality of groups, and each group includes two or more of the sensing devices electrically coupled together. The rod position indication system further includes a control rod monitoring device electrically coupled to each group of sensing devices by a routing wire.

Abstract: Target assembly for an isotope production system. The target assembly includes a target body having a production chamber and a beam cavity that is adjacent to the production chamber. The production chamber is configured to hold a target liquid. The beam cavity opens to an exterior of the target body and is configured to receive a particle beam that is incident on the production chamber. The target assembly also includes a vibrating device that is secured to the target body. The vibrating device is configured to cause vibrations that are experienced within the production chamber.

Abstract: The present invention relates generally to electric power and process heat generation using a modular, compact, transportable, hardened nuclear generator rapidly deployable and retrievable, comprising power conversion and electric generation equipment fully integrated within a single pressure vessel housing a nuclear core. The resulting transportable nuclear generator does not require costly site-preparation, and can be transported fully operational. The transportable nuclear generator requires an emergency evacuation area substantially reduced with respect to other nuclear generators as it may be configured for operation with a melt-proof conductive ceramic core which allows decay heat removal even under total loss of coolant scenarios.

Abstract: A power module assembly includes a reactor core immersed in a coolant and a reactor vessel housing the coolant and the reactor core. An internal dry containment vessel submerged in liquid substantially surrounds the reactor vessel in a gaseous environment. During an over-pressurization event the reactor vessel is configured to release the coolant into the containment vessel and remove a decay heat of the reactor core through condensation of the coolant on an inner surface of the containment vessel.

Abstract: Fuel bundles for a nuclear reactor are described and illustrated, and in some cases include fuel elements each having a fissile content of 235U between about 0.9 wt % 235U and 5.0 wt % 235U, and wherein at least one of the fuel elements is a poisoned low-enriched uranium fuel element including a neutron poison in a concentration greater than about 5.0 vol %.

Abstract: Nuclear fuel spacers include a deflection-limited elastic rod contact. Spacers may additionally include a rigid contact without elastic functionality. A degree of deflection may be chosen based on plastic deformation threshold, maximum fuel rod movement, anticipated transverse loads related to fuel assembly, inspection, handling, transportation, operation, accidents, and/or any other operating characteristic. Spacers include deflection-limited elastic contacts and/or rigid contacts in several arrangements within the spacer and/or on a single fuel rod. Spacers are compatible with a simple fabrication method that forms rigid, deflection-limiting, and elastic components from a single substrate. Nuclear fuel spacers are useable with several fuel assembly types.

Abstract: A steam generator for a nuclear reactor comprises plenums proximate with a first plane, wherein the first plane intersects a bottom portion of a riser column of a reactor vessel. The steam generator may further comprise plenums proximate with a second plane, approximately parallel with the first plane, wherein the second plane intersects a top portion of the riser column of the reactor vessel. The steam generator may further include a plurality of steam generator tubes that convey coolant from a plenum located proximate with the first plane to one of the plenums proximate with the second plane.

Abstract: Application of axial seed magnetic fields in the range 20-100 T that compress to greater than 10,000 T (100 MG) under typical NIF implosion conditions may significantly relax the conditions required for ignition and propagating burn in NIF ignition targets that are degraded by hydrodynamic instabilities. Such magnetic fields can: (a) permit the recovery of ignition, or at least significant alpha particle heating, in submarginal NIF targets that would otherwise fail because of adverse hydrodynamic instability growth, (b) permit the attainment of ignition in conventional cryogenic layered solid-DT targets redesigned to operate under reduced drive conditions, (c) permit the attainment of volumetric ignition in simpler, room-temperature single-shell DT gas capsules, and (d) ameliorate adverse hohlraum plasma conditions during laser drive and capsule compression. In general, an applied magnetic field should always improve the ignition condition for any NIF ignition target design.

Abstract: Disclosed are a highly selective, highly sensitive method and apparatus for detecting vapors from explosives at low concentrations such as 1 part in 1014. Airborne explosives vapors are selectively adsorbed on a spiral-wound platinum or platinum-coated ribbon of a preconcentrator cartridge while trapping of nitrogen oxides is avoided. The vapors are released and partially decomposed to liberate nitric oxide gas by flash-heating of the ribbon, these products may then be pyrolyzed if necessary to complete the liberation of nitric oxide gas, and then the liberated nitric oxide gas is detected, as by chemiluminescent detection. Also described are various systems incorporating the explosives vapor detector such as a walk-through portal, a vehicle sniffer, and a system incorporated into the air-handling apparatus of a building.

Abstract: A nuclear material within a container is to be detected. Included are: a neutron source for generating neutrons emitted toward the container; a detection section capable of detecting neutrons including primary neutrons emitted from the neutron source and secondary neutrons generated through a nuclear fission reaction of the nuclear material; and a processing section for performing a reactor noise analysis process based on data obtained through detecting of neutrons by the detection section. The neutron source generates neutrons in a pulsatile manner. The processing section performs the reactor noise analysis process based on data obtained by excluding, from time series data obtained through detecting of neutrons by the detection section, data of a time range including a generation time of the neutrons generated by the neutron source in the pulsatile manner.

Abstract: A nuclear material within a container is to be detected. Included are: a neutron source for generating neutrons emitted toward the container; a detection section capable of detecting neutrons including primary neutrons emitted from the neutron source and secondary neutrons generated through a nuclear fission reaction of the nuclear material; and a processing section for performing a reactor noise analysis process based on data obtained through detecting of neutrons by the detection section. The neutron source generates neutrons in a pulsatile manner. The processing section performs the reactor noise analysis process based on data obtained by excluding, from time series data obtained through detecting of neutrons by the detection section, data of a time range including a generation time of the neutrons generated by the neutron source in the pulsatile manner.

Abstract: The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator.

Abstract: Modifications to power plants for moderating climate warming and increasing safety combine a large compressed air energy storage (CAES) system with a thermal power plant such that free power plant waste heat replaces natural gas used at existing and planned CAES facilities. The system allows higher percentages of wind and solar energy on existing grids. The compressed air in a companion CAES can cool a nuclear reactor during an emergency. Also an inexpensive, add-on, external, Emergency Core Cooling System (ECCS) can cool a nuclear reactor after shutdown, even when all internal cooling water circulation has been disabled. All embodiments are installed outside the plant where they will not be damaged in the event of a plant accident. Both systems use environmentally friendly compressed air energy storage in new ways, and can be built and installed quickly around the world at existing plants using only proven infrastructure.

Abstract: A fuel pellet for a nuclear reactor includes a plurality of tristructural-isotropic fuel particles embedded in a structural silicon carbide matrix. A method of manufacturing a fuel pellet includes the steps of coating a plurality of tristructural-isotropic fuel particles with a coating slurry including silicon carbide powder to form a plurality of coated fuel particles; compacting the plurality of fuel particles; and sintering the compacted plurality of fuel particles to form the fuel pellet.

Abstract: A system and method for managing spent nuclear fuel includes a small capacity canister that preferably encloses or encapsulates a single spent nuclear fuel rod assembly but can enclose up to six spent nuclear fuel rod assemblies. The canister is air tight and prevents radioactive material from escaping. The canister is loaded by positioning a single spent nuclear fuel rod assembly in the canister and then closing the canister to make it air tight.

Abstract: A fuel rod for a nuclear fission reactor is disclosed and claimed. The fuel rod includes an elongate hollow cladding configured to retain a nuclear fuel therein. The cladding includes an elongate hollow tube. Fiber layers are positioned around the outside surface of the tube or within the tube forming an integral part thereof. Both the tube and the fibers are formed of a ceramic material. A fuel assembly including a plurality of such fuel rods is also disclosed and claimed.

Abstract: In a plant including a system which is provided with a steam generator 2, a turbine 3, 5, a condenser 6 and a heater 7 and in which non-deaerated water circulates, and a pipe, the steam generator 2, the heater 7 and 8 of the system which comes into contact with the non-deaerated water is deposited with a protective substance.

Abstract: A nuclear reactor is provided that includes a vessel; a core provided in the vessel; at least one plate heat exchanger provided in the vessel, with at least one duct for supplying a secondary fluid to the heat exchanger and a duct for discharging the secondary fluid from the heat exchanger, the discharge duct extending through the vessel. The nuclear reactor comprises a device for attaching the heat exchanger to an area of the vessel through which the discharge duct extends.

Abstract: A power module assembly may include a reactor vessel containing a primary coolant and one or more inlets configured to draw a secondary coolant from the containment cooling pool in response to a loss of power and/or a loss of coolant. One or more outlets may be submerged in the containment cooling pool and may be configured to vent the secondary coolant into the containment cooling pool. A heat exchanger may be configured to remove heat from the primary coolant, wherein the heat may be removed by circulating the secondary coolant from the containment cooling pool through the heat exchanger via natural circulation.

Abstract: A passive safety system for a nuclear power plant (100) cools the plant after shutdown, even when primary water circulation is disabled. The system comprises a source of compressed gas (112, 805) which can be the system's only source of operating energy, a source of external cooling water (106, 500), and interconnection components. If the reactor overheats, the gas is used to force the cooling water into the reactor's core. The gas can be taken from a highly compressed source and decompressed to a lower pressure suitable for forcing the water from the source, in which case the water can first be used to supply heat to the expanding gas to prevent it from freezing its environment. The system can be located underground or can be portable, e.g., carried on railroad cars or other wheeled conveyances. The system can be located above ground, or in a covered trench (705).