Abstract: The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.

Abstract: A method for storing the energy of a nuclear power plant in which the nuclear core is cooled by gases or liquid heat transfer media. The hot heat transfer liquid is stored directly in storage tanks. When needed, it is used for heating a power plant. The heat of a compressed gas heat transfer medium such as helium is stored by passing the compressed gas through tanks filled with heat-resistant solids and recovered by passing the same type of gas in a second circuit in a reverse direction. Through the hot tanks to the power plant and back. This Abstract is not intended to define the invention disclosed in the specification, nor intended to limit the scope of the invention in any way.

Abstract: A method of storing heat includes moving a portion of a heated fluid from at least one reactor core to at least one tank having solid media, storing heat from the portion of the heated fluid in the solid media, and transferring the stored heat from the solid media to a fluid that can be used by a power plant to generate electrical energy. A system for storing heat in a nuclear power plant includes at least one tank comprising solid media structured and arranged to store heat and an arrangement structured and arranged to pass a first fluid through the at least one tank, transfer heat from the first fluid to the solid media, store the heat in the solid media, and transfer the heat from the solid media to a second fluid. This Abstract is not intended to define the invention disclosed in the specification, nor intended to limit the scope of the invention in any way.

Abstract: A jet pump sensing line support clamp may be used for sensing line repair, replacement, and damage prevention or reduction. The clamp may affix to jet pump sensing line supports and confine the individual jet pump sensing lines. The clamp may provide for further access or securing of the lines in the support through the clamp. Methods of installing the clamp may include attaching and tightening the clamp against the sensing lines.

Abstract: The invention relates to an equipment and a system for processing a gaseous mixture by permeation. The equipment of the invention includes m*n separation modules Pij, n and n being natural integers higher than or equal to 2, i being a natural integer from 1 to m, and j is a natural interger from 1 to n. Each of the separation modules P1 includes a permeate inlet Epij, the permeate inlet Ep11 of the separation module P11 corresponding to the F inlet for supplying the gaseous mixture into said equipment, a permeate outlet Spij and a retentate outlet Srij. Furthermore, the permeate outlet Spij is connected to the permeate inlet Epi+1j of the separation module Pj+1j, and the retentate outlet Srij is connected to the permeate inlet Epij+1 of the separation module Pij+1. The equipment does not use any intermediate recycling.

Abstract: Methods and apparatuses are provided for the removal and transportation of thermal energy from a heat source to a distant complex for use in thermochemical cycles or other processes. In one embodiment, an apparatus includes a hybrid heat pipes/thermosyphon intermediate heat exchanger (HPTIHX) system that is divided into three distinct sections, namely: an evaporation chamber, a condensation chamber, and a working fluid transport section of liquid and vapor counter-current flows.

Abstract: Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium, expanding the helium in a turbine; wherein the turbine is in operative communication with an electrical generator; and generating electricity in the electrical generator.

Abstract: Disclosed is an advanced process that relates to the enhanced production of energy using the integration of multiple thermal cycles (Brayton and Rankine) that employ multiple fuels, multiple working fluids, turbines and equipment. The method includes providing a nuclear reactor, reactor working fluid, heat exchangers, compressors, and multiple turbines to drive compressors that pressurize a humidified working fluid that is combusted with fuel fired in at least one gas turbine. The turbine(s) provide for electrical energy, processes or other mechanical loads.

Abstract: A gas turbine plant, wherein a first gas turbine positioned coaxially with a compressor and a second gas turbine positioned coaxially with a generator are rotated by a coolant heated by heat energy provided by the fission of a coated particle fuel. The rotational speed of the first gas turbine is controlled by controlling a flow in the bypass passage of the second gas turbine.

Abstract: An upper plenum structure of a cooled pressure vessel for a prismatic very high temperature reactor which secures a space for coolant to supply to a core and also supports an upper reflector located inside a graphite structure on top of the core. The upper plenum structure includes a cavity structure where the coolant goes down in the upper plenum structure, a plurality of upper reflector supports formed with the cavity and supporting the upper reflector located on top thereof, and a plurality of coolant distributing blocks. Each of the coolant distributing blocks is coupled with a bottom portion of a respective one of the upper reflector supports and is located on top of the core in order to distribute the coolant collected in a cavity, formed by the upper reflector support, to the core. The coolant distributing blocks cooperate with the upper reflector supports to define the cavity structure.

Abstract: A method treats a flow gas that is guided via a catalytic adsorber module to oxidize contaminants carried in the flow gas. The method reliably purifies the flow gas using equipment that is held to a comparatively low level of complexity. To this end, the flow gas is guided in a first purification step via a first catalytic adsorber module to oxidize contaminants carried along therewith, during which molecular or atomic oxygen is added to the flow gas, and the flow gas mixed with the added oxygen is guided in a second purification step via an oxidation catalyst. The flow gas flowing away from the oxidation catalyst is guided in a third purification step via a second catalytic adsorber module to reduce excessive oxygen.

Abstract: Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium; expanding the helium in a turbine; wherein the turbine is in operative communication with an electrical generator; and generating electricity in the electrical generator.

Abstract: Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium; expanding the helium in a turbine; wherein the turbine is in operative communication with an electrical generator; and generating electricity in the electrical generator.

Abstract: In a nuclear power plant making use of a high temperature gas cooled reactor, it is necessary, prior to commencing power generation and connection of a generator to an electrical distribution grid, to condition the power generation circuit of the plant. This involves creating stable conditions within the power generation circuit. To this end, the plant includes a start-up blower system for circulating working fluid, typically helium, around the power generation circuit until the desired conditions are satisfied. The start-up blower system typically includes a normally open in-line valve, at least one blower connected in parallel with the in-line valve and a normally closed isolation valve connected in series with the blower. Conditioning the power generation circuit will typically include stabilizing the pressure in the circuit at between 10 bar and 50 bar.

Abstract: A method of generating a nuclear reaction from a gas stream containing water which involves heating a gas stream at a rapid rate sufficient to dissociate the water into hydrogen and oxygen and to transform hydrogen ions into protons which produce nuclear reactions, including nuclear fusion. Once the reaction state is reached, no additional heat needs to be inputted into the reaction system. Electrons that are freed from chemical species during the resulting nuclear reaction can be collected and used to produce electricity. In addition, hydrogen that is produced during the resulting nuclear reaction can be collected and used as a fuel in internal combustion engines, engine driven machine or piece of equipment.

Abstract: A nuclear power plant which includes a closed loop power generation circuit making use of helium as the working fluid. The plant further includes a helium inventory control system which includes a plurality of helium storage tanks whereby helium can be fed into or removed from the power generation circuit. Each helium storage tank is provided with a heat sink so that the tank has a relatively high thermal inertia which in turn restricts the temperature variation within the storage tank as a result of the introduction of helium into and/or the withdrawal of helium from the storage tank. This permits the optimization of the design of the storage tanks.

Abstract: The present invention includes a nuclear fission reactor apparatus and a method for operation of same, comprising: a core comprising a fissile metal hydride; an atmosphere comprising hydrogen or hydrogen isotopes to which the core is exposed; a non-fissile hydrogen absorbing and desorbing material; a means for controlling the absorption and desorption of the non-fissile hydrogen absorbing and desorbing material, and a means for extracting the energy produced in the core.

Abstract: A method of regulating the power generated in a nuclear power plant which includes the step of regulating the flow of helium through the reactor. To this end, the power plant includes a closed loop power generation circuit having at least one compressor and a recirculation circuit whereby helium can be recirculated around the compressor. By regulating the flow of helium around the recirculation circuit using suitable valves the flow of helium through the reactor and hence the power generated can be regulated. The plant includes a helium inventory control system whereby the inventory of helium in the power generation circuit can be varied thereby varying the power generated in the circuit.

Abstract: The subject of the present invention is to provide a nuclear reactor plant of which is a direct cycle nuclear reactor using a carbon dioxide as a coolant such that a heat evacuation for liquefying coolant is reduced while a compressive work is reduced by using a condensation capability of a carbon dioxide for enhancing a cycle efficiency. The nuclear reactor plant is comprised of a nuclear reactor 1, a turbine 2, and wherein, the coolant of supper critical state is heated by a heat of a nuclear reactor to directly drive a turbine, a gaseous coolant discharged from said turbine is chilled and compressed after said turbine is driven for keeping in a critical state, and then said coolant is circulated again into said nuclear reactor, and wherein, a carbon dioxide is used as said coolant, and a predetermined ratio of gaseous coolant discharged from said turbine is liquefied for being compressed in a liquid state while a rest of gaseous coolant is compressed in a gaseous state.

Abstract: Fuel element and gas-cooled nuclear reactor using this type of fuel elements.

Abstract: High temperature reactor with residual-heat transfer system comprises a cooling gas intake at the bottom and cooling gas outlet at the top so that a cooling gas can flow from the bottom to the top through the reactor core. In order to assure reliable heat transfer a bypass duct is provided with a lower end communicating with the cooling gas intake and the upper end communicating with the cooling gas outlet. The bypass duct is arranged parallel to the reactor core and passing a partial flow of cooling gas from the bottom to the top. This partial flow of cooling gas heats up only trivially. This partial flow of cooling gas is further cooled by the cooler. The upward flow of the comparatively cold cooling gas in the bypass duct stops and by itself reverses because the cooling gas in the bypass duct is drawn toward the reactor core on account of the natural convection.

Abstract: In the method of shutting down a high temperature nuclear reactor having a negative temperature coefficient of reactivity, such as a gas cooled pebble-bed nuclear reactor, while the core is operating in the critical state with the core having a predetermined critical average core temperature and with the heat generated in the critical state being removed by a coolant, effecting the shut down by reducing or discontinuing the removal of heat from the reactor core and increasing the average core temperature by an amount above the critical average core temperature for rendering the core hot sub-critical due to the negative temperature coefficient of reactivity. The core can be maintained in the hot sub-critical state by a controlled removal of after shut-down heat from the core.

Abstract: Isotopically enriched helium-4, that is, helium-4 which is low in helium-3, is useful as a nuclear reactor coolant. It is produced from liquefied natural gas source helium by distilling helium-3 therefrom. The coolant is preferably enriched in hydrogen up to about 6 percent by volume to thereby improve the heat transfer characteristics of the coolant, and to reduce the power requirements for circulation of the coolant.