Abstract: A control rod position indication system is for a nuclear reactor with a reactor core and at least one control rod which is movable along a linear path of movement for controlling reactivity of the core. The system includes a permanent magnet mounted on the control rod or a corresponding drive rod, and a number of reed switches arranged around the path of movement in order to be switched by a magnetic field generated by the permanent magnet when passing by. The permanent magnet has a north-south axis whose orientation is constant during movement, and the respective reed switch has a number of reed contacts which are aligned along a longitudinal axis. The longitudinal axis of at least one reed switch is inclined relative to the north-south axis of the permanent magnet, and the angle of inclination has an absolute value within a range from 15 to 65 degrees.

Abstract: A heat pipe configured to remove heat from a nuclear reactor core is disclosed herein. The heat pipe can include an inner housing defining an inner volume configured to accommodate a heat source and an outer housing configured about the inner housing and the heat source. A wick can be positioned between at least a portion of the inner housing and at least a portion of the outer housing, wherein the wick can include a capillary material, and wherein the wick can define an intermediate volume between the inner housing and the outer housing. A working fluid can be positioned within the intermediate volume, wherein the working fluid can evaporate at a first end of the heat pipe and condense at a second end of the heat pipe adjacent to a heat exchanger, and wherein the wick can return condensed working fluid to the first end of the heat pipe.

Abstract: Systems, devices, and methods for generating an orbital confinement fusion reaction are described. An orbital confinement fusion device can include a cathodic inner electrode defining a longitudinal axis of the device. The inner electrode can include an emitter material. The orbital confinement fusion device can include an anodic outer electrode, concentric with the longitudinal axis and defining a chamber between the inner electrode and the outer electrode. The orbital confinement fusion device can also include a plurality of magnetic field generators disposed in a coaxial arrangement relative to the longitudinal axis. The plurality of magnetic field generators can be configured to form a magnetic field parallel to the longitudinal axis in the chamber.

Abstract: A method for collection of dry samples taken directly from a nuclear reactor core interior. Incremental samples of irradiated metal alloy components of the reactor core may be taken and collected in-situ using a specialized metal-cutting drill bit having a hollow tungsten carbide sampling cutting head, in conjunction with an angled sampling gantry. The drill bit body has an interior airflow passage in hermetic communication with a filter located in a glove box. Air holes are formed through a face of the cutting head. A vacuumed airflow through the airflow passage and at the cutting head causes a sample of any of metal chips, filings, and dust to be obtained directly from the reactor core by being pulled through the air holes and into the airflow passage and ultimately into the filter. A collected sample may be analyzed for radionuclides and radioactivity level.

Abstract: A spacer grid specifically designed for accident tolerant fuel utilizing fuel rods with SiC cladding for implementation in pressurized water reactors. The spacer grid design allows for ease of SiC fuel rod insertion during the fuel assembly fabrication process by providing a smooth contact geometry. The co-planar support allows the fuel rods to be rotated axially more freely at the grid location than a conventional six-point contact geometry used in existing fuel assembly designs. The fuel rod support cells are attached at their corners which are shared between adjacent support cells.

Abstract: More accurate prediction of reactor water quality of a nuclear reactor is implemented. A device for prediction of reactor water quality of a nuclear reactor in a nuclear power plant is disclosed. The device stores a reactor water quality prediction model which is learned using learning data, and with which future reactor water quality is predicted. An explanatory variable of the reactor water quality prediction model includes a value in a predetermined period unit that is generated from data acquired in an operating nuclear power plant. The device generates the value in a predetermined period unit from data acquired in a target operating nuclear power plant, and acquires a predicted value of the reactor water quality in the target nuclear power plant based on the reactor water quality prediction model and the value in a predetermined period unit.

Abstract: A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.

Abstract: Thorium-based fuel bundles according to one or more embodiments of the present invention are used in existing PHWR reactors (e.g., Indian 220 MWe PHWR, Indian 540 MWe PHWR, Indian 700 MWe PHWR, CANDU 300/600/900) in place of conventional uranium-based fuel bundles, with little or no modifications to the reactor. The fuel composition of such bundles is 60+ wt % thorium, with the balance of fuel provided by low-enriched uranium (LEU), which has been enriched to 13-19.95% 235U. According to various embodiments, the use of such thorium-based fuel bundles provides (1) 100% of the nominal power over the entire life cycle of the core, (2) high burnup, and (3) non-proliferative spent fuel bundles having a total isotopic uranium concentration of less than 12 wt %. Reprocessing of spent fuel bundles is also avoided.

Abstract: The power plant system includes a molten salt reactor assembly, a thermocline unit, phase change heat exchangers, and process heat systems. The thermocline unit includes an insulated tank, an initial inlet, a plurality of zone outlets, and a plurality of gradient zones corresponding to each zone outlet and being stacked in the tank. Each gradient zone has a molten salt portion at a portion temperature corresponding to the molten salt supply from the molten salt reactor being stored in the tank and stratified. The molten salt portions at higher portion temperatures generate thermal energy for process heat systems that require higher temperatures, and molten salt portions at lower portion temperatures generate thermal energy for process heat systems that require lower temperatures. The system continuously pumps the molten salt supply in controlled rates to deliver the heat exchange fluid supply to perform work in the corresponding particular process heat system.

Abstract: A divertor for system supporting plasma for fusion employs permanent magnets providing far weaker magnetic field strength than conventionally used in cryogenic magnetic systems through an ability to place the permanent magnets in close proximity to the plasma containment volume.

Abstract: A cooling system in a nuclear power plant is disclosed, including a boundary section disposed inside a containment to enclose a reactor coolant system, and configured to restrict steam containing radioactive materials generated in the reactor coolant system from leaking into paths other than a discharge part. An In-Containment Water Storage Tank (IRWST) is disposed outside the boundary section and is configured to store refueling water therein. An emergency cooling tank is disposed outside the containment and is provided with a condensation heat exchanger. A gas-liquid separator is connected to the emergency cooling tank outside the containment. A return line is configured to connect the gas-liquid separator and the boundary section such that condensate generated by condensing the steam within the boundary section, through the emergency cooling tank and the gas-liquid separator, is discharged toward the boundary section upon an occurrence of a nuclear power plant accident.

Abstract: Systems and methods that facilitate the transmutation of long-lived radioactive transuranic waste into short-live radioactive nuclides or stable nuclides using an electrostatic accelerator particle beam to generate neutrons.

Abstract: Hydrogen infused nuclear reactor core monoliths and processes for their production are disclosed. Such monoliths may function as both a core monolith and a moderator, providing structure and at least some moderation. Hydrogen infused monoliths may be complementary to or be used in lieu of separate moderators for thermalizing neutrons.

Abstract: A method for heating primary coolant in a nuclear reactor system during system start-up. A primary coolant loop fluidly couples together a reactor vessel and a steam generating vessel. The primary coolant loop is filled with primary coolant. A portion of the primary coolant is taken from the primary coolant loop and placed into a start-up sub-system. The portion is heated while in the sub-system to form a heated portion of the primary coolant. The heated portion is returned into the primary coolant loop. The method allows for the primary coolant to be heated to a no-load operating temperature.

Abstract: A housing assembly configured to house a reactor is disclosed. The housing assembly includes a plurality of modular walls configured to surround the reactor and a passive temperature control system. The plurality of modular walls includes a first modular wall. The passive temperature control system is coupled to the first modular wall. The passive temperature control system is configured to transfer heat between the reactor and an area around the housing assembly.

Abstract: A nuclear reactor is designed to couple the load path of control elements with the reactor core, thus reducing opportunity for differential movement between the control elements and the reactor core. A core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The core barrel can be mounted to a reactor vessel head. Movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.

Abstract: An integrated passive reactor system including a pressure vessel, a containment vessel arranged outside the pressure vessel, and a reactor core arranged inside the pressure vessel. A primary loop operates in full natural circulation. The reactor system is provided with a secondary side passive residual heat removal system including a primary loop heat exchanger arranged inside the pressure vessel and a passive residual heat removal heat exchanger arranged outside the containment vessel. The primary loop heat exchanger is arranged above the reactor core. The passive residual heat removal heat exchanger is arranged inside a water tank which is fixed outside the containment vessel. The primary loop heat exchanger and the passive residual heat removal heat exchanger are connected by heat exchanger inlet pipelines and heat exchanger outlet pipelines.

Abstract: The fuel assembly includes at least one fuel rod and an outer channel with four sidewalls surrounding the fuel rod, the outer channel having a configuration based on a position of the fuel assembly within a core of the nuclear reactor, wherein at least a first select sidewall, of the four sidewalls of the outer channel, is a reinforced sidewall, the remaining sidewalls of the outer channel, other than the at least a first select sidewall, are non-reinforced sidewalls, the at least a first select sidewall being in a controlled location that faces and is directly adjacent to a control blade that is to be utilized in the nuclear reactor, wherein an entirety of the reinforced sidewall as a whole is at least one of thicker and made from a material that is more resistant to radiation-induced deformation as compared to an entirety of the non-reinforced sidewalls.

Abstract: Among the various aspects of the present disclosure is the provision of methods for producing radioisotopes and improving the specific activity of radioisotopes (e.g., Cu-64 chloride). As described herein, the method includes matching of the target material and the proton beam strike area, resulting in improved specific activity while reducing the amount of target material used.

Abstract: A breeder blanket for generating tritium using neutrons produced by nuclear fusion of deuterium and/or tritium within a plasma confined within a fusion reactor. The breeder blanket comprises: a plasma-facing first wall; a breeder layer comprising lithium containing material for generating tritium from the neutrons; and neutron moderator material comprising metal hydride and/or deuteride arranged between the first wall and the lithium-containing material.