Arrangements and devices for reducing and/or preventing wear of a thermal sleeve in a nuclear reactor are disclosed. Arrangements include a first structure provided on or in one the thermal sleeve and a second structure provided on or in the head penetration adapter. At least a portion of the first structure and at least another portion of the second structure interact to resist, reduce, and/or prevent rotation of the thermal sleeve about its central axis relative to the head penetration adapter. Devices include a base for coupling to a guide tube of the reactor and a plurality of protruding members extending upward from the base. Each member having a portion for engaging a corresponding portion of a guide funnel of the thermal sleeve.

A nuclear reactor includes guide tubes (12); and vessel head penetrations (22) each comprising a tubular adapter (24) fixed in one of the openings (2a) and defining an inner passage (34). Each vessel head penetration (22) also includes a tubular sleeve (36) engaged in the inner passage (34) and axially extending in line with one of the guide tubes (12). Each sleeve (36) is suspended by an upper axial sleeve end (38) lying on an upper range (40) on the corresponding adapter (24). A lower axial end (48) of the sleeve (36) projects axially into the vessel (1) beyond the adapter (24) and is separated from an upper axial end (54) of the corresponding guide tube (12) by an axial gap having an axial height of less than 50 millimeters.

A nuclear reactor includes guide tubes (12); and vessel head penetrations (22) each comprising a tubular adapter (24) fixed in one of the openings (2a) and defining an inner passage (34). Each vessel head penetration (22) also includes a tubular sleeve (36) engaged in the inner passage (34) and axially extending in line with one of the guide tubes (12). Each sleeve (36) is suspended by an upper axial sleeve end (38) lying on an upper range (40) on the corresponding adapter (24). A lower axial end (48) of the sleeve (36) projects axially into the vessel (1) beyond the adapter (24) and is separated from an upper axial end (54) of the corresponding guide tube (12) by an axial gap having an axial height of less than 50 millimeters.

Arrangements and devices for reducing and/or preventing wear of a thermal sleeve in a nuclear reactor are disclosed. Arrangements include a first structure provided on or in one the thermal sleeve and a second structure provided on or in the head penetration adapter. At least a portion of the first structure and at least another portion of the second structure interact to resist, reduce, and/or prevent rotation of the thermal sleeve about its central axis relative to the head penetration adapter. Devices include a base for coupling to a guide tube of the reactor and a plurality of protruding members extending upward from the base. Each member having a portion for engaging a corresponding portion of a guide funnel of the thermal sleeve.

A simple nuclear reactor in which most of the reflector material is outside of the reactor vessel is described. The reactor vessel is a cylinder that contains all of the fuel salt and a displacement component, which may be a reflector, in the upper section of the reactor vessel. Other than the displacement component, the reflector elements including a radial reflector and a bottom reflector are located outside the vessel. The salt flows around the outside surface of the displacement component through a downcomer heat exchange duct defined by the exterior of the displacement component and the interior surface of the reactor vessel. This design reduces the overall size of the reactor vessel for a given volume of salt relative to designs with internal radial or bottom reflectors.

A method for dynamic pressure control during a multiphase injection is described wherein the pressures of fluids in the various reservoirs of a fluid delivery system are controlled to provide desired fluid delivery parameters. The methods include advancing the first drive member to expel the first fluid from the first reservoir into a conduit, wherein the fluid is pressurized to a first fluid pressure; measuring the first fluid pressure to provide a target value; while the second reservoir is in fluid isolation from the conduit, advancing or retracting the second drive member to increase or decrease the fluid pressure of the second fluid in the second reservoir to the target value; placing the second reservoir in fluid communication with the conduit; and advancing the second drive member to expel the second fluid from the second reservoir into the conduit.

A method for dynamic pressure control during a multiphase injection is described wherein the pressures of fluids in the various reservoirs of a fluid delivery system are controlled to provide desired fluid delivery parameters. The methods include advancing the first drive member to expel the first fluid from the first reservoir into a conduit, wherein the fluid is pressurized to a first fluid pressure; measuring the first fluid pressure to provide a target value; while the second reservoir is in fluid isolation from the conduit, advancing or retracting the second drive member to increase or decrease the fluid pressure of the second fluid in the second reservoir to the target value; placing the second reservoir in fluid communication with the conduit; and advancing the second drive member to expel the second fluid from the second reservoir into the conduit.

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.

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.

A Control Neutron Absorber (CNA) assembly for a microreactor that produces nuclear energy is disclosed. The CNA assembly includes a housing, a CNA rod, and a burnable absorber. The housing includes an inner housing and an outer housing. The inner housing is configured to receive a CNA rod. The outer housing extends coaxially with the inner housing and is positioned radially outward and offset from the inner housing defining a cavity therebetween. The CNA rod includes a neutron absorbing rod including a first neutron absorbing material. The neutron absorbing rod is positioned within the inner housing and is configured to move axially relative to the inner housing. The burnable absorber includes a second neutron absorbing material, exhibits a neutron absorbing strength that is less than that of the neutron absorbing rod, is positioned within the inner housing, and is configured to receive the neutron absorbing rod therein.