Westinghouse Electric Company LLC

Robert W Flammang

Michael D Heibel

Jorge V Carvajal

Melissa M Walter

Michael A James

Nicola G Arlia

David M Sumego

Lyman J Petrosky

John G Seidel

Jeffrey L Arndt

Shawn C Stafford

Joonhyung Choi

Melissa M Heagy

Michael S Norrell

John R Abel, Ii

Yung-An Chao

Michael R Ickes

Patrick J Sebastiani

Ho Q Lam

Vefa N Kucukboyaci

Sabryna D Henze

William H Slagle

Tim M Crede

An enclosure for non-organic electronic components is provided which includes an inner cavity for housing non-organic electronic components and a neutron shielding barrier surrounding the inner cavity and the electronic components housed within the cavity. The barrier is formed from a neutron reflecting material in solid or powdered form and a neutron absorbing material in solid or powdered form. An optional structural support is provided in certain aspects of the enclosure design.

Electronic enclosure with neutron shield for nuclear in-core applications

A method and a system for performing real-time, continuous, measurements of the boron concentration in the water entering a nuclear reactor coolant system. The invention utilizes knowledge of the impact that boron contained in liquid water has on the attenuation of acoustic or ultrasonic waves. This information, coupled with radiation damage resistant and high temperature operability capable transmitter and receiver equipment, provides the means to place the measurement system sensors and signal processing electronics on the reactor coolant system charging flow piping or the hot leg or cold leg of the reactor coolant loop. This will allow the reactor operator to directly monitor both the reactor coolant system boron concentration value and detect changes in the reactor coolant system boron concentration relative to a reference value as they occur.

Real-time reactor coolant system boron concentration monitor utilizing an ultrasonic spectroscpopy system

A system that measures the temperature distribution of the reactor coolant flowing through the hot leg or cold leg pipes by measuring the speed of sound time delay. This concept uses radiation hardened and temperature tolerant ultrasonic signal drivers based on vacuum micro-electronic technology. The system employs ultrasonic signals propagated through water, and relies on the characteristic that the speed of sound changes as the density and temperature of the water changes. Thus, a measured difference in the speed of sound in water may be directly correlated to a temperature change of the water.

Reactor coolant system piping temperature distribution measurement system

A vacuum micro-electronics device that utilizes fissile material capable of using the existing neutron leakage from the fuel assemblies of a nuclear reactor to produce thermal energy to power the heater/cathode element of the vacuum micro-electronics device and a self-powered detector emitter to produce the voltage/current necessary to power the anode/plate terminal of the vacuum micro-electronics device.

Nuclear powered vacuum microelectronic device

Apparatus for amplifying low level signals within a nuclear plant's containment building, derived from the ex-core nuclear instrumentation system. The system employs vacuum micro-electronic devices in place of conventional pre-amplifier assemblies to position the pre-amplifier assemblies closer to and within the vicinity of the ex-core detector outputs.

In-containment ex-core detector system

A pulsed sonar-based wireless rod position indication system that utilizes nuclear radiation and high temperature tolerant hardware. The pulsed sonar-based rod position indication system can precisely locate the rod position by measuring the time of flight of a transmitted signal and by using the phase and amplitude information of the same transmitted signal. Primary and secondary antenna probes located in the interior of the control rod drive rod travel housing and full hardware redundancy provide for improved accuracy. The time of flight, phase and amplitude raw signals are inputted to a wireless data transmitter capable of sending the raw signals to a receiver antenna located elsewhere inside a containment for further processing.

Nuclear control rod position indication system

A silicon carbide Schottky diode solid state radiation detector that has an electron donor layer such as platinum placed over and spaced above the Schottky contact to contribute high energy Compton and photoelectrical electrons from the platinum layer to the active region of the detector to enhance charged particle collection from incident gamma radiation.

Solid state radiation detector with enhanced gamma radiation sensitivity

A method includes detecting on an ongoing basis the currently existing dose rates while a worker is performing a maintenance or other operation within the RCA, and visually outputting information that pertains to the ionizing radiation to which the worker is being exposed during the operation. The information that is visually output can include information such as the current dose rate and the overall dose to which the worker has been subjected, but can additionally include information such as the time remaining before which the worker will have been exposed to the maximum allowable dose. Furthermore, it is possible for the visual display to output visual indicia that represent a comparison the exposure to ionizing radiation that had been planned as a function of time prior to the operation being commenced with the actual exposure to ionizing radiation as the operation is performed.

Method of detecting and outputting radiation dose rate information

A system and method for measuring and monitoring axial flux to determine subcriticality in a spent fuel pool of a nuclear power plant. In certain embodiments of this invention, one or more neutron detectors are operable to generate signals resulting from neutron interactions in the spent fuel pool, a counting device counts the signals which are generated by the one or more neutron detectors, a connecting means electrically connects the one or more neutron detectors to the counting device, a signal analyzer is used to determine reactivity of the fuel assemblies in the spent fuel pool based on the counted signals, a power supply provides power for the neutron detectors, the counting device and the system analyzer, and a software code containing an axial flux curve index is used to correlate the counted signals to determine the subcriticality of the spent fuel pool.

Systems and methods for spent fuel pool subcriticality measurement and monitoring

A nuclear power distribution measurement assembly that is sized to fit within an instrumentation thimble of a nuclear fuel assembly, that employs a spaced tandem arrangement of thermo-acoustic engines, each of which has a heat source side that is insulated from the reactor coolant traversing the nuclear core in which the fuel assembly is to be placed and a cold side housing a resonator chamber with enhanced thermal conductance to the coolant. The resonator chamber of each of the thermo-acoustic engines is of a different length to generate a different frequency whose amplitude is proportional to the neutron activity at the axial and radial position of the thermo-acoustic engine. The frequency identifies the measurement assembly's position. Acoustic telemetry is employed to monitor the acoustic waves generated by the individual thermo-acoustic engines to provide a remote reading of the axial and radial power distribution of a reactor core.

Thermo-acoustic nuclear power distribution measurement assembly

An in-core neutron monitor that employs vacuum microelectronic devices to configure an in-core instrument thimble assembly that monitors and wirelessly transmits a number of reactor parameters directly from the core of a nuclear reactor without the use of external cabling. The in-core instrument thimble assembly is substantially wholly contained within an instrument guide tube within a nuclear fuel assembly.

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Pittsburgh, PA, United States of America

Robert W Flammang