G21D1/02

ENERGY PRODUCTION DEVICES AND ASSOCIATED COMPONENTS, AND RELATED HEAT TRANSFER DEVICES AND METHODS

An energy production device may include a core configured to heat a heat transmission fluid, an energy harnessing device configured to convert heat into electrical energy and a heat transfer device positioned over the core configured to receive the heat transmission fluid and transfer the heat to the energy harnessing device. The energy production device may further include a vibration isolator positioned between the energy harnessing device and the heat transfer device. The vibration isolator may be configured to secure the energy harnessing device to the heat transfer device and substantially prevent the transmission of motion from the energy harnessing device to the heat transfer device.

METHOD OF IMPROVING THE EXPLOSION SAFETY OF NUCLEAR POWER PLANTS

The invention relates to methods of decreasing the effect of blast loads on industrial spaces relating to, inter alia, nuclear power plant and large chemical manufacturing facilities. A method of improving explosion safety in closed spaces by attenuating the effect of a combustion wave or shock wave on a protected surface consists in placing obstructions before the protected surface in the form of elastic membranes filled with a flame-retardant substance. A non-flammable gas is used as the substance filling the membranes; the membranes themselves are made of a material that disintegrates during, and under the action of, displacement of the front of a combustion wave or shock wave along the surface of the membranes. The membranes are filled with a non-flammable gas immediately after flammable gas is detected at a dangerous concentration in the space in front of the protected object. The technical result consists in increasing explosion safety, decreasing the effect that an explosive wave formed in an accidental explosion of fuel-air mixtures has on the walls and floors of protected spaces.

METHOD OF IMPROVING THE EXPLOSION SAFETY OF NUCLEAR POWER PLANTS

The invention relates to methods of decreasing the effect of blast loads on industrial spaces relating to, inter alia, nuclear power plant and large chemical manufacturing facilities. A method of improving explosion safety in closed spaces by attenuating the effect of a combustion wave or shock wave on a protected surface consists in placing obstructions before the protected surface in the form of elastic membranes filled with a flame-retardant substance. A non-flammable gas is used as the substance filling the membranes; the membranes themselves are made of a material that disintegrates during, and under the action of, displacement of the front of a combustion wave or shock wave along the surface of the membranes. The membranes are filled with a non-flammable gas immediately after flammable gas is detected at a dangerous concentration in the space in front of the protected object. The technical result consists in increasing explosion safety, decreasing the effect that an explosive wave formed in an accidental explosion of fuel-air mixtures has on the walls and floors of protected spaces.

Main heat and waste heat integrated thermal exchanger for small nuclear reactor

A main heat and waste heat integrated thermal exchanger for a small nuclear reactor has a first coolant zone for a first main heat loop, a second coolant zone for a second main heat loop and a third coolant zone for a waste heat removal loop. The first coolant for the first main heat loop passes through the first coolant inlet, and then reaches the orifice plate, and finally flows out from the first coolant outlet. The second coolant for the second main heat loop passes through the second coolant inlet, and then reaches the lower tube sheet, and finally flows out from the second coolant outlet. The third coolant for the waste heat removal loop enters the entrance sleeve through the third coolant inlet, and then enters multiple tubes of the tube bundle, and then enters the exit sleeve, and finally flows out from the third coolant outlet.

APPARATUS AND METHOD FOR REAL-TIME PRECISION MEASUREMENT OF THE THERMAL POWER OF A NUCLEAR REACTOR

A method comprising measuring a number of gamma-ray counts in a gamma-ray sensitive detector (60) that is placed outside a biological shield (10) near a primary cooling circuit (30) of a nuclear power plant, and determining the thermal power of the nuclear power plant based on the number of gamma-ray counts measured in the gamma-ray sensitive detector (60).

REACTOR BUILDING AND VESSEL SYSTEMS

Reactor buildings and vessel systems are disclosed. A nuclear power system includes: a building structure that comprises at least two exterior side walls and two end walls, at least one of the exterior walls angled non-orthogonally relative to a floor of the building structure, the at least two exterior walls and two end walls defining an interior volume of the building structure; one or more nuclear reactor systems mounted at least partially in the interior volume of the building structure; and one or more heat exchanger systems mounted at least partially to at least one of the exterior walls. A nuclear reactor vessel system includes: a nuclear fission reactor; an inner vessel that defines an inner volume sized to at least partially enclose the nuclear fission reactor; and an outer vessel sized to wholly or substantially enclose the inner vessel, the inner vessel being removable from the outer vessel.

REACTOR BUILDING AND VESSEL SYSTEMS

Reactor buildings and vessel systems are disclosed. A nuclear power system includes: a building structure that comprises at least two exterior side walls and two end walls, at least one of the exterior walls angled non-orthogonally relative to a floor of the building structure, the at least two exterior walls and two end walls defining an interior volume of the building structure; one or more nuclear reactor systems mounted at least partially in the interior volume of the building structure; and one or more heat exchanger systems mounted at least partially to at least one of the exterior walls. A nuclear reactor vessel system includes: a nuclear fission reactor; an inner vessel that defines an inner volume sized to at least partially enclose the nuclear fission reactor; and an outer vessel sized to wholly or substantially enclose the inner vessel, the inner vessel being removable from the outer vessel.

Integrated system for converting nuclear energy into electrical, mechanical, and thermal energy
11482346 · 2022-10-25 · ·

Provided is an apparatus for generating electricity, mechanical energy, and/or process and district heat using a gas propellant chamber fueled with fissile material and enclosed in a sealed containment vessel which also contains an operating gas. The system allows for the operating gas to be compressed as it enters the nuclear fuel chamber where it is heated. As the operating gas exits the nuclear fuel chamber, the kinetic energy of the gas is converted to rotational energy by a variety of methods. The rotational energy is further converted to electricity, mechanical energy, and/or process and district heat. The operating gas circulates in the containment vessel and is cooled prior to re-entering the gas propellant chamber. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.

Integrated system for converting nuclear energy into electrical, mechanical, and thermal energy
11482346 · 2022-10-25 · ·

Provided is an apparatus for generating electricity, mechanical energy, and/or process and district heat using a gas propellant chamber fueled with fissile material and enclosed in a sealed containment vessel which also contains an operating gas. The system allows for the operating gas to be compressed as it enters the nuclear fuel chamber where it is heated. As the operating gas exits the nuclear fuel chamber, the kinetic energy of the gas is converted to rotational energy by a variety of methods. The rotational energy is further converted to electricity, mechanical energy, and/or process and district heat. The operating gas circulates in the containment vessel and is cooled prior to re-entering the gas propellant chamber. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.

REUSABLE STRUCTURES CONTAINING ISOTOPES FOR SIMULATING RADIOACTIVE CONTAMINATION ENVIRONMENTS, AND METHODS OF FORMATION
20230083647 · 2023-03-16 ·

A structure—for use in simulating radioactive contamination environments—comprises fragments encapsulated within a substrate material. The fragments comprise radioactive isotopes with moderate half-lives. To form such structures, the fragments are encapsulated within the at least one substrate material. In a method of simulating a radioactive contamination environment, multiple removable structures, such as the aforementioned structures, are selectively placed in a facility, and may be subsequently removed, stored, and reused.