Patent classifications
G21C15/25
INTERMIXING FEEDWATER SPARGER NOZZLES AND METHODS FOR USING THE SAME IN NUCLEAR REACTORS
Nozzles mix coolant from different sources together in an outlet to prevent differences in coolant output. Different flow path configurations are useable in the nozzle, including a multiple-path configuration with flows from different sources jacketed or concentrically arranged around flows from other sources. Swirl vanes may be installed in the nozzle to impart mixing or filtering the fluid flow. Diffusers may be used to passively suction or accelerate flow and mixing the same like a jet pump. Nozzles can be combined with filtration systems like trap filters that capture debris based on a momentum difference between the denser debris and fluid. Filters can use magnetic, adhesive, or porous materials to capture debris without blocking a flow path. Filters can be disengaged, such as when clogged, such that coolant flows around the system. Nozzles can be installed on feedwater sparger assemblies in varying manner to distribute coolant from multiple nozzles.
Molten fuel nuclear reactor with neutron reflecting coolant
- Ryan Abbott ,
- Brian C. Kelleher ,
- William M. Kerlin ,
- Kevin Kramer ,
- Jeffery F. Latkowski ,
- Jon D. McWhirter ,
- Robert C. Petroski ,
- Joshua C. Walter ,
- Jesse R. Cheatham, III ,
- Anselmo T. Cisneros, Jr. ,
- Ken Czerwinski ,
- Bassem S. El-Dasher ,
- Daniel Flowers ,
- Charles Gregory Freeman ,
- Mark A. Havstad ,
- Christopher J. Johns
Configurations of molten fuel salt reactors are described that utilize neutron-reflecting coolants or a combination of primary salt coolants and secondary neutron-reflecting coolants. Further configurations are described that circulate liquid neutron-reflecting material around an reactor core to control the neutronics of the reactor. Furthermore, configurations which use the circulating neutron-reflecting material to actively cool the containment vessel are also described.
Molten fuel nuclear reactor with neutron reflecting coolant
- Ryan Abbott ,
- Brian C. Kelleher ,
- William M. Kerlin ,
- Kevin Kramer ,
- Jeffery F. Latkowski ,
- Jon D. McWhirter ,
- Robert C. Petroski ,
- Joshua C. Walter ,
- Jesse R. Cheatham, III ,
- Anselmo T. Cisneros, Jr. ,
- Ken Czerwinski ,
- Bassem S. El-Dasher ,
- Daniel Flowers ,
- Charles Gregory Freeman ,
- Mark A. Havstad ,
- Christopher J. Johns
Configurations of molten fuel salt reactors are described that utilize neutron-reflecting coolants or a combination of primary salt coolants and secondary neutron-reflecting coolants. Further configurations are described that circulate liquid neutron-reflecting material around an reactor core to control the neutronics of the reactor. Furthermore, configurations which use the circulating neutron-reflecting material to actively cool the containment vessel are also described.
FLOW RESTRICTING SLIP JOINT CLAMPS AND METHODS FOR USE IN A NUCLEAR REACTOR JET PUMP
Clamps can be secured to a slip joint and limit flow through the same by seating on a diffuser axially regardless of wear and damage in the slip joint. An extension from the clamp seats to the inlet mixer. These extensions can be adjusted from outside the clamp to achieve an individual preload or flow limitation through the slip joint. The extension may be an O-ring or other shape. A biasing drive may connect to and move the extension from an outside surface of the clamp. The biasing drive may include a threaded cap in an outer groove that is linked to a plunger via a spring. Clamps are fabricated of materials that maintain their physical properties when exposed to an operating nuclear reactor environment and may be relatively rigid and resilient metals.
FLOW RESTRICTING SLIP JOINT CLAMPS AND METHODS FOR USE IN A NUCLEAR REACTOR JET PUMP
Clamps can be secured to a slip joint and limit flow through the same by seating on a diffuser axially regardless of wear and damage in the slip joint. An extension from the clamp seats to the inlet mixer. These extensions can be adjusted from outside the clamp to achieve an individual preload or flow limitation through the slip joint. The extension may be an O-ring or other shape. A biasing drive may connect to and move the extension from an outside surface of the clamp. The biasing drive may include a threaded cap in an outer groove that is linked to a plunger via a spring. Clamps are fabricated of materials that maintain their physical properties when exposed to an operating nuclear reactor environment and may be relatively rigid and resilient metals.
REACTOR COOLING AND ELECTRIC POWER GENERATION SYSTEM
A reactor cooling and power generation system according to the present invention includes a reactor vessel, a heat exchange section to receive heat generated from a core inside the reactor vessel through a fluid, and a power production section having a thermoelectric element configured to produce electric energy using energy of the fluid whose temperature has increased while receiving the heat of the reactor, wherein the system is configured to allow the fluid that has received the heat from the core to circulate through the power production section, and to operate even during an accident as well as during a normal operation of a nuclear power plant to produce electric power.
Also, the reactor cooling and power generation system according to the present invention may continuously operate during an accident as well as a normal operation so as to cool the reactor and produce emergency power, thereby improving system reliability. In addition, the reactor cooling and power generation system according to the present invention may facilitate application of safety class or seismic design with a small scale facility, thereby improving the reliability owing to the application of the safety class or seismic design.
REACTOR COOLING AND ELECTRIC POWER GENERATION SYSTEM
A reactor cooling and power generation system according to the present invention includes a reactor vessel, a heat exchange section to receive heat generated from a core inside the reactor vessel through a fluid, and a power production section having a thermoelectric element configured to produce electric energy using energy of the fluid whose temperature has increased while receiving the heat of the reactor, wherein the system is configured to allow the fluid that has received the heat from the core to circulate through the power production section, and to operate even during an accident as well as during a normal operation of a nuclear power plant to produce electric power.
Also, the reactor cooling and power generation system according to the present invention may continuously operate during an accident as well as a normal operation so as to cool the reactor and produce emergency power, thereby improving system reliability. In addition, the reactor cooling and power generation system according to the present invention may facilitate application of safety class or seismic design with a small scale facility, thereby improving the reliability owing to the application of the safety class or seismic design.
Apparatus and method to remotely inspect piping and piping attachment welds
An apparatus and method to remotely perform automated piping and piping attachment weld inspections. The apparatus has two spaced positioning arms that rotate out from one side of a frame structure and a kicker arm that rotates out from an opposite side of the frame structure at a location between the two positioning arms. The positioning arms and the kicker arm wedge the frame structure between an object to be scanned and an opposing structure. A scanning subassembly supported on the frame structure is configured to pivot and move in an appropriate direction and to pilot a transducer around the surface of the object to be scanned.
Intermixing feedwater sparger nozzles and methods for using the same in nuclear reactors
Nozzles mix coolant from different sources together in an outlet to prevent differences in coolant output. Different flow path configurations are useable in the nozzle, including a multiple-path configuration with flows from different sources jacketed or concentrically arranged around flows from other sources. Swirl vanes may be installed in the nozzle to impart mixing or filtering the fluid flow. Diffusers may be used to passively suction or accelerate flow and mixing the same like a jet pump. Nozzles can be combined with filtration systems like trap filters that capture debris based on a momentum difference between the denser debris and fluid. Filters can use magnetic, adhesive, or porous materials to capture debris without blocking a flow path. Filters can be disengaged, such as when clogged, such that coolant flows around the system. Nozzles can be installed on feedwater sparger assemblies in varying manner to distribute coolant from multiple nozzles.
Intermixing feedwater sparger nozzles and methods for using the same in nuclear reactors
Nozzles mix coolant from different sources together in an outlet to prevent differences in coolant output. Different flow path configurations are useable in the nozzle, including a multiple-path configuration with flows from different sources jacketed or concentrically arranged around flows from other sources. Swirl vanes may be installed in the nozzle to impart mixing or filtering the fluid flow. Diffusers may be used to passively suction or accelerate flow and mixing the same like a jet pump. Nozzles can be combined with filtration systems like trap filters that capture debris based on a momentum difference between the denser debris and fluid. Filters can use magnetic, adhesive, or porous materials to capture debris without blocking a flow path. Filters can be disengaged, such as when clogged, such that coolant flows around the system. Nozzles can be installed on feedwater sparger assemblies in varying manner to distribute coolant from multiple nozzles.