G21C7/00

Operating a nuclear reactor using a deposit model of a nuclear reactor heat transfer surface

A method of operating a nuclear reactor is provided. The method includes defining a layer increment of a deposit layer modeling a deposit on a heat transfer surface of the nuclear reactor; periodically updating a thickness of the deposit layer by adding the layer increment to the deposit layer; recalculating properties of the deposit layer after each layer increment is added to the deposit layer; determining a temperature related variable of the heat transfer surface as a function of the recalculated properties of the deposit layer; and altering operation of the nuclear reactor when the temperature related variable of the heat transfer surface reaches a predetermined value. A method of modeling a deposit on a heat transfer surface of a nuclear reactor is also provided.

SHIELDED TRANSPORTABLE NUCLEAR REACTOR
20210398704 · 2021-12-23 ·

A transportable nuclear power generator assembly includes a first modular nuclear power generator unit and a second nuclear power generator unit. The first modular nuclear power generator unit includes a first transport container, a first nuclear power module positioned inside the first transport container, and a first supporting mechanism movably supports the first nuclear power module inside the first transport container. The second modular nuclear power generator unit includes a second transport container, a second nuclear power module positioned inside the second transport container, and a second supporting mechanism configured to support the second nuclear power module inside the second transport container. At least one of the first supporting mechanism and the second supporting mechanism is configured to move at least one of the first nuclear power module and the second nuclear power module relative to one another to result in an at least critical state or a subcritical state.

SHIELDED TRANSPORTABLE NUCLEAR REACTOR
20210398704 · 2021-12-23 ·

A transportable nuclear power generator assembly includes a first modular nuclear power generator unit and a second nuclear power generator unit. The first modular nuclear power generator unit includes a first transport container, a first nuclear power module positioned inside the first transport container, and a first supporting mechanism movably supports the first nuclear power module inside the first transport container. The second modular nuclear power generator unit includes a second transport container, a second nuclear power module positioned inside the second transport container, and a second supporting mechanism configured to support the second nuclear power module inside the second transport container. At least one of the first supporting mechanism and the second supporting mechanism is configured to move at least one of the first nuclear power module and the second nuclear power module relative to one another to result in an at least critical state or a subcritical state.

Method for calculating a PCI margin associated with a loading pattern of a nuclear reactor, associated system, computer program and medium
11342088 · 2022-05-24 · ·

A method for calculating a PCI margin associated with a loading pattern of a nuclear reactor including a core into which fuel assemblies are loaded according to the loading pattern is implemented by an electronic system. The fuel assemblies include fuel rods each including fuel pellets of nuclear fuel and a cladding surrounding the pellets. This method includes calculating a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating a reference secondary PCI margin for the reference pattern; calculating a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating a modified principal PCI margin for the modified pattern, depending on a comparison of the modified secondary PCI margin with the reference secondary PCI margin.

Method for calculating a PCI margin associated with a loading pattern of a nuclear reactor, associated system, computer program and medium
11342088 · 2022-05-24 · ·

A method for calculating a PCI margin associated with a loading pattern of a nuclear reactor including a core into which fuel assemblies are loaded according to the loading pattern is implemented by an electronic system. The fuel assemblies include fuel rods each including fuel pellets of nuclear fuel and a cladding surrounding the pellets. This method includes calculating a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating a reference secondary PCI margin for the reference pattern; calculating a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating a modified principal PCI margin for the modified pattern, depending on a comparison of the modified secondary PCI margin with the reference secondary PCI margin.

DETACHABLE CONNECTION
20220130560 · 2022-04-28 ·

Detachable connection of a linear motor tubular armature and a vertical cylindrical rod of a nuclear reactor actuator, the rod, located in a guide pipe, is installed in the armature with an annular gap, in which a tubular fork with pins is placed. L-shaped slots are made at the end of the armature, vertical slots are made above them and the lower part of the armature is closed with a longitudinally fixed plug. On the side surface of the plug, custom-character-shaped grooves are made for the insertion or removal of the fork pins. Also, radial protrusions are made on the rod, and in the guide pipe, below the vertical slots of the armature, a bushing with custom-character-shaped grooves is fixed coaxially to the armature with the possibility of inserting the protrusions of the rod into, or removing the protrusions of the rod from, the grooves.

DETACHABLE CONNECTION
20220130560 · 2022-04-28 ·

Detachable connection of a linear motor tubular armature and a vertical cylindrical rod of a nuclear reactor actuator, the rod, located in a guide pipe, is installed in the armature with an annular gap, in which a tubular fork with pins is placed. L-shaped slots are made at the end of the armature, vertical slots are made above them and the lower part of the armature is closed with a longitudinally fixed plug. On the side surface of the plug, custom-character-shaped grooves are made for the insertion or removal of the fork pins. Also, radial protrusions are made on the rod, and in the guide pipe, below the vertical slots of the armature, a bushing with custom-character-shaped grooves is fixed coaxially to the armature with the possibility of inserting the protrusions of the rod into, or removing the protrusions of the rod from, the grooves.

Transition metal-based materials for use in high temperature and corrosive environments
11174536 · 2021-11-16 · ·

A material (e.g., an alloy) comprises molybdenum, rhenium, and at least one element selected from the group consisting of tellurium, iodine, selenium, chromium, nickel, copper, titanium, zirconium, tungsten, vanadium, and niobium. Methods of forming the material (e.g., the alloy) comprise mixing molybdenum powder, rhenium powder, and a powder comprising at least one element selected from the group consisting of tellurium, iodine, selenium, chromium, nickel, copper, titanium, zirconium, tungsten, vanadium, and niobium. The mixed powders may be coalesced to form the material (e.g., the alloy).

Detachable connection in nuclear reactor control system

This disclosure enables a creation of a detachable connection between a linear motor tubular armature and a vertical cylindrical rod of an actuator of a control and protection system of a nuclear reactor. Such configuration reduces a dose load on a member of personnel, as well as provides an increase in reliability of a coupling of the linear motor tubular armature and the vertical cylindrical rod in conditions of high temperature and radiation.

Detachable connection in nuclear reactor control system

This disclosure enables a creation of a detachable connection between a linear motor tubular armature and a vertical cylindrical rod of an actuator of a control and protection system of a nuclear reactor. Such configuration reduces a dose load on a member of personnel, as well as provides an increase in reliability of a coupling of the linear motor tubular armature and the vertical cylindrical rod in conditions of high temperature and radiation.