Abstract: Exemplary pellets can be used for magnetic fusion devices for mitigating plasma disruption. In some embodiments, the pellets may be cryogenically cooled that may cause a rise in the electrical conductivity of the pellets. A high conductivity of the pellet can screen out the plasma's magnetic field from the interior of the pellet. The screening out of the plasma's magnetic field can slow the ablation rate of the pellet which may allow for deeper pellet penetration and a better suited spatial profile of deposited material for proper mitigation of the plasma disruption. In some other embodiments, the pellets may not be cryogenically cooled.

Abstract: A modular and transportable nuclear reactor system comprising a transportation module including a housing. A cask and a radiation shielding section are located in the housing with the shielding surrounding the cask. A high temperature sodium cooled reactor is located in the cask and the reactor is cooled by the natural circulation of in-vessel sodium. The reactor powers at least one thermal-to-electric conversion unit.

Abstract: Methods, apparatus, devices, and systems for creating, controlling, conducting, and optimizing fusion activities of nuclei. In particular, the present inventions relate to, 5 among other things, fusion activities that are conducted individually or collectively on a very small scale, preferably on the nano-scale or smaller such as pico to femto scales, for the utilization of energy produced from these activities in smaller devices and for aggregation into larger devices.

Abstract: An HTS assembly for use in a toroidal field coil having a central column is described. The HTS assembly comprises a plurality of parallel arrays of HTS tapes arranged to pass through the central column, each array comprising a plurality of HTS tapes arranged such that c-axes of all tapes in an array are parallel to each other, and such that planes of the HTS layers of the HTS tapes are perpendicular to a first radius of the central column. Each HTS tape has a c-angle which is an angle between a perpendicular to a plane of an HTS layer of the HTS tape and the c-axis of the tape. The plurality of arrays comprises first and second sets of arrays. Each array within the first set of arrays comprises HTS tapes of a first type having a first c-angle, and each array within the second set of arrays comprises HTS tapes of a second type having a second c-angle which is greater than the first c-angle. The first set of arrays are arranged closer to the first radius than the second set of arrays.

Abstract: An automated system for on-line monitoring and coil diagnostics of rod position indicator (RPI) coils coil diagnostic, or RPI coil diagnostic system. The RPI coil diagnostic system performs coil diagnostics for a RPI system in a nuclear power plant. The RPI coil diagnostic system is in electrical communication with and monitors the outputs of the detector coils. The RPI coil diagnostic system measures characteristics of the detector coils that are indicative of the health of the detector coils and/or the connections between the detector coils and the RPI electronics.

Abstract: A damping area or “dash pot” on the upper ends of control rods absorb energy from dropped control rod assemblies without narrowing the diameter of guide tubes. As a result, coolant can freely flow through the guide tubes reducing boiling water issues. The dampening area reduces a separation distance between an outside surface of the control rod and an inside surface of the guide tubes decelerating the control rods when entering a top end of the guide tubes. In another example, the dampening area may be located on a drive shaft. The dampening area may have a larger diameter than an opening in a drive shaft support member that decelerates the drive shaft when dropped by a drive mechanism.

Abstract: A system that measures the temperature distribution of the reactor coolant flowing through the hot leg or cold leg pipes by measuring the speed of sound time delay. This concept uses radiation hardened and temperature tolerant ultrasonic signal drivers based on vacuum micro-electronic technology. The system employs ultrasonic signals propagated through water, and relies on the characteristic that the speed of sound changes as the density and temperature of the water changes. Thus, a measured difference in the speed of sound in water may be directly correlated to a temperature change of the water.

Abstract: The present invention provides an alternative circulation cooling method for an emergency core cooling system that, even if the emergency core cooling system does not operate normally, can prevent the implementation of containment vessel venting by suppressing a rise in pressure and temperature in the containment vessel, and can suppress the implementation of dry-well venting even if containment vessel venting needs to be performed, as well as a nuclear power plant that is capable of the same. An alternative circulation cooling method for an emergency reactor core cooling system is performed at a nuclear power plant that includes an RHR system and a MUWC system. The method includes: connecting the downstream side of an RHR heat exchanger to the upstream side of a MUWC pump, and cooling water from a suppression chamber using the RHR heat exchanger and performing nuclear reactor injecting or containment vessel spraying using the MUWC pump.

Abstract: Embodiments of systems and methods for compressing plasma are described in which plasma pressures above the breaking point of solid material can be achieved by injecting a plasma into a funnel of liquid metal in which the plasma is compressed and/or heated.

Abstract: A channel baffle structure comprises a pipe, a swing check plate and a driving apparatus, wherein the main part of the swing check plate is located inside the pipe, and the driving apparatus is disposed outside the pipe. A connection structure is used for connecting the driving apparatus and the swing check plate. The check plate can be opened and closed passively by gravity and fluid pressure, but can also be actively opened and closed by the driving apparatus, such that requirements for multiple operating conditions of the channel can be satisfied.

Abstract: Damper systems selectively reduce coolant fluid flow in nuclear reactor passive cooling systems, including related RVACS. Systems include a damper that blocks the flow in a coolant conduit and is moveable to open, closed, and intermediate positions. The damper blocks the coolant flow when closed to prevent heat loss, vibration, and development of large temperature gradients, and the damper passively opens, to allow full coolant flow, at failure and in transient scenarios. The damper may be moveable by an attachment extending into the coolant channel that holds the damper in a closed position. When a transient occurs, the resulting loss of power and/or overheat causes the attachment to stop holding the damper, which may be driven by gravity, pressure, a spring, or other passive structure into the open position for full coolant flow. A power source and temperature-dependent switch may detect and stop holding the damper closed in such scenarios.

Abstract: A device and method that enables a specimen that is to be converted into a radioisotope to be inserted into an extended, retractable thimble of a nuclear reactor moveable in-core detector system and be harvested after irradiation either during reactor operation or a refueling outage without damaging the retractable thimble. The specimen is enclosed within the interior of a forward portion of a tubular member having a closed lead end and structured to travel within the retractable thimble. The tubular member is sized to extend from a position above and proximate the desired core elevation the specimen is to be irradiated at to a location above a seal table that the retractable thimble extends through. The specimen is inserted and withdrawn from the core by inserting or withdrawing the tubular member from above the seal table. Desirably, the forward end of the tubular member is divided into several specimen compartments.

Abstract: The present invention is related to an apparatus and a method for producing fibrous debris of test for a nuclear plant. More particularly, producing fibrous debris of test having the uniform length distribution equal to the fibrous debris collected by a plurality of strainer bags while passing through a strainer in length distribution degree, and conducting a test for evaluating the influence of debris in the core due to a loss of coolant accident based on the produced fibrous debris for testing, thereby ensuring reproducibility of a test by the fibrous debris of test having a uniform length distribution and, thereby producing conservative experimental data.

Abstract: A shipping container comprises a tubular or cylindrical shell having a closed end and an open end, a top end-cap removably secured to the open end of the tubular or cylindrical shell, and at least one fuel assembly compartment defined inside the shell. Each fuel assembly compartment includes elastomeric sidewalls and is sized and shaped to receive an unirradiated nuclear fuel assembly through the open end of the shell. The shipping container may further include a divider component, for example having a cross-shaped cross-section with ends of the cross secured to inner walls of the shell, and the divider component and the inner walls of the shell define the fuel assembly compartments. To load, the shipping container is arranged vertically and an unirradiated nuclear fuel assembly is loaded through the open end of the shell into each compartment, after which the open end is closed off by securing the top end-cap.

Abstract: A treatment system for evaluating boron sources for boron neutron cancer therapy (BNCT) has a substantially square secondary moderator having a central treatment chamber for a subject; and four substantially identical neutron generators positioned around the substantially square secondary moderator with the axis of each acceleration chamber passing through the center of the treatment chamber.

Abstract: The invention relates to a multi-component cladding for a nuclear fuel rod that includes a combination of ceramic and metal components. More particularly, the invention is directed to a cladding that includes a ceramic composite having a zirconium composition deposited thereon to form a zirconium coated ceramic composite. The ceramic composite includes a ceramic matrix and a plurality of ceramic fibers. The cladding is effective to protect the contents of the cladding structure from exposure to high temperature environments during various load conditions of a nuclear reactor.

Abstract: A passive cooling system for cooling the in-containment refueling water storage tank and the spent fuel pool of nuclear power plants that can extend the number of days the plants can safely be maintained without operator intervention. The cooling system employs a thermosiphon in a closed loop cycle that circulates a refrigerant around the cooling loop between heat exchangers within the spent fuel and in-containment refueling water and the ambient atmosphere outside the containment, by natural circulation.

Abstract: A Boron neutron cancer treatment system has a secondary moderator having a central treatment chamber for a subject, and eight substantially identical neutron generators, each comprising a pre-moderator block. The eight neutron generators are positioned around the secondary moderator with the axis of each acceleration chamber passing through the center of the treatment chamber, and with the angled sides of the neutron generators fully adjacent.

Abstract: A high reliable water injection device is provided that injects water into a reactor containment vessel and can reliably shut off cooling water at normal times and quickly and reliably inject water into the reactor containment vessel without the need for external power, in a case of emergency. The water injection device injects water into a reactor containment vessel includes a flow path through which cooling water is supplied; a disk that closes the flow path; a swing arm that is connected to the disk and performs closing and opening of the flow path by the disk; and a weight that is connected to the swing arm via a swing lever, in which the weight is supported by a support member made of a low melting point alloy.

Abstract: A Boron neutron cancer treatment system has a moderator chamber filled with liquid or granular moderator material except for a central treatment chamber, the moderator chamber having parallel upper and lower surfaces, and a plurality of modular neutron generators fully immersed in the liquid or granular moderator material of the moderator chamber.