Brian Scott Triplett

US Patent:

20130166223, Jun 27, 2013

Filed:

Dec 23, 2011

Appl. No.:

13/336229

Inventors:

Brian S. Triplett - Wilmington NC, US

Assignee:

GE-HITACHI NUCLEAR ENERGY AMERICAS LLC - Wilmington NC

International Classification:

G06F 19/00

US Classification:

702 23

Abstract:

Methods implemented by at least one electronic processor for generating pointwise fast neutron spectra may include receiving composition data; receiving source data or calculating the source data; receiving nuclear data; and calculating the pointwise fast neutron spectrum based on numerical integration using the composition, source, and nuclear data. Systems for generating pointwise fast neutron spectra may include a bus; at least one electronic processor connected to the bus; an input device connected to the bus; and a communication link connected to the bus. The at least one electronic processor may be configured to receive composition data from the input device via the bus, to receive source data from the input device via the bus or to calculate the source data, to receive nuclear data from the communication link via the bus, and to calculate the pointwise fast neutron spectrum based on numerical integration using the composition, source, and nuclear data.

US Patent:

20130272468, Oct 17, 2013

Filed:

Apr 11, 2012

Appl. No.:

13/444535

Inventors:

Eric P. Loewen - Wilmington NC, US
Brian S. Triplett - Wilmington NC, US
Brett J. Dooies - Wilmington NC, US

Assignee:

GE-HITACHI NUCLEAR ENERGY AMERICAS LLC - Wilmington NC

International Classification:

G21C 17/00

US Classification:

376247, 376245, 376254

Abstract:

A system for monitoring a state of a reactor core in a nuclear reactor may include an internal monitoring device located inside the reactor core, the internal monitoring device including one or more internal sensor arrays configured to take measurements of conditions of the reactor core at different vertical regions within the reactor core to generate internal measurement data; an external monitoring device located in the reactor structure outside the reactor core, the external monitoring device including one or more external sensor arrays configured to take measurements of conditions of the reactor core at positions outside the reactor core corresponding the plurality of different vertical regions within the reactor core to generate external measurement data, and a transmitter configured to wirelessly transmit the external measurement data; and a receiver station configured to determine a state of the reactor core based on the external and internal measurement data.

US Patent:

20130272469, Oct 17, 2013

Filed:

Apr 11, 2012

Appl. No.:

13/444478

Inventors:

Eric P. Loewen - Wilmington NC, US
Brian S. Triplett - Wilmington NC, US
Brett J. Dooies - Wilmington NC, US

Assignee:

GE-HITACHI NUCLEAR ENERGY AMERICAS LLC - Wilmington NC

International Classification:

G21C 17/00

US Classification:

376249

Abstract:

A device for monitoring a reactor during normal and off-normal operating conditions may include a case formed of a rigid material, the case including a shielding layer configured to insulate an internal portion of the device from external heat and radiation; a coupling unit configured to adhere the case to a surface location of a reactor; a sensing unit configured to generate environmental measurements by measuring environmental conditions in the vicinity of the reactor; a data processing unit configured to generate measurement data by processing the environmental measurements; a transmitter configured to transmit the measurement data externally from the device; and a power unit configured to power the device independently of an external power source.

US Patent:

20130287163, Oct 31, 2013

Filed:

Apr 26, 2012

Appl. No.:

13/456640

Inventors:

Eric P. Loewen - Wilmington NC, US
Brian S. Triplett - Wilmington NC, US
Brett J. Dooies - Wilmington NC, US
Scott L. Pfeffer - Wilmington NC, US

Assignee:

GE-HITACHI NUCLEAR ENERGY AMERICAS LLC - Wilmington NC

International Classification:

G21C 3/336
G21C 3/338

US Classification:

376441

Abstract:

In one embodiment, the fuel bundle for a liquid metal cooled reactor includes a channel, a nose assembly secured to a lower end of the channel, and a plurality of fuel rods disposed within the channel. At least one of the fuel rods has at least one guard ring surround the fuel rod and spacing the fuel rod from adjacent fuel rods.

US Patent:

20130308742, Nov 21, 2013

Filed:

May 15, 2012

Appl. No.:

13/471806

Inventors:

Eric P. Loewen - Wilmington NC, US
Brian S. Triplett - Wilmington NC, US
Brett J. Dooies - Wilmington NC, US
Scott L. Pfeffer - Wilmington NC, US

Assignee:

GE-HITACHI NUCLEAR ENERGY AMERICAS LLC - Wilmington NC

International Classification:

G21C 3/322

US Classification:

376443

Abstract:

In one embodiment, a fuel bundle for a liquid metal cooled reactor includes a channel, a nose assembly secured to a lower end of the channel, a plurality of fuel rods disposed within the channel, and an internal mixer disposed within the channel above the plurality of fuel rods. The internal mixer includes peripheral flow control members and interior flow control members. The peripheral flow control members are located near walls of the channel, and the interior flow control members are located towards a longitudinal center of the housing. At least one of the peripheral flow control members is configured to direct liquid metal flowing through the channel towards an interior of the channel, and at least one of the interior flow control members is configured to direct liquid metal flowing through the channel away from the interior of the channel.

US Patent:

20140069468, Mar 13, 2014

Filed:

Sep 11, 2012

Appl. No.:

13/609824

Inventors:

Eric P. LOEWEN - Wilmington NC, US
Brian S. TRIPLETT - Wilmington NC, US
Brett J. DOOIES - Wilmington NC, US

Assignee:

GE-HITACHI NUCLEAR ENERGY AMERICAS LLC - Wilmington NC

International Classification:

B08B 3/02

US Classification:

134 34

Abstract:

A method of cleaning a submerged surface covered by a liquid medium includes injecting a cleaning liquid with a submerged fluid jet through the liquid medium at the submerged surface. The method may also include introducing at least one of a non-reactive gas and a reactive gas with the cleaning liquid through the submerged fluid jet.

US Patent:

20140073829, Mar 13, 2014

Filed:

Sep 11, 2012

Appl. No.:

13/609890

Inventors:

Eric P. LOEWEN - Wilmington NC, US
Brian S. TRIPLETT - Wilmington NC, US
Brett J. DOOIES - Wilmington NC, US

Assignee:

GE-HITACHI NUCLEAR ENERGY AMERICAS LLC - Wilmington NC

International Classification:

G21F 9/02
B01J 7/00

US Classification:

588 1, 422119

Abstract:

A method of stabilizing a fuel containing a reactive sodium metal may include puncturing a cladding of a fuel pin enclosing the fuel containing the reactive sodium metal to form an injection passage and an extraction passage. A reaction gas may be injected into the fuel pin through the injection passage to react with the reactive sodium metal to form a stable sodium compound. A ratio of a product gas and a remaining quantity of the reaction gas exiting the fuel pin through the extraction passage is subsequently measured, wherein the product gas is a reaction product of the reaction gas and the reactive sodium metal within the fuel pin. Once the measured ratio indicates that a reaction between the reaction gas and the reactive sodium metal is complete, the injection passage and the extraction passage are sealed so as to confine the stable sodium compound within the fuel pin.

US Patent:

20170369239, Dec 28, 2017

Filed:

Aug 21, 2017

Appl. No.:

15/681856

Inventors:

- Wilmington NC, US
Brian Scott TRIPLETT - Wilmington NC, US
Brett Jameson DOOIES - Wilmington NC, US
Jordan E. HAGAMAN - Wilmington NC, US

Assignee:

GE-Hitachi Nuclear Energy Americas LLC - Wilmington NC

International Classification:

B65D 90/22
G21C 9/012
B01D 29/01
G21C 15/18

Abstract:

An entrainment-reducing assembly may include a container configured to hold a liquid. A venting arrangement may extend into an upper portion of the container and be configured to direct condensable and non-condensable gases into the container. A suction structure may extend into a lower portion of the container and be configured to carry out an extraction of excess liquid from the container caused by condensed gases. A deflector may be disposed between the suction structure and the venting arrangement within the container. As a result, an entrainment of uncondensed gases during the extraction of the liquid by the suction structure may be reduced or prevented, thereby protecting the pump from cavitation and failure.