Westinghouse Electric Company LLC

Westinghouse Electric Corporation

Michael D Heibel

Jorge V Carvajal

Robert W Flammang

Jeffrey L Arndt

Michael Clare Prible

Melissa M Walter

David M Sumego

Albert J Impink, Jr

Michael A James

Nicola G Arlia

Luke D Czerniak

Matthew D McArdle

John H Nelson

Shawn C Stafford

Melissa M Heagy

Toshio Morita

Cory Hildebrand

Raymond Calvo

Daniel Walus

Thomas J Schildkamp

Daniel P Kistler

Jason Palmer

Lyman J Petrosky

Thomas V Congedo

Louis R Grobmyer

Eric M Weisel

Kenneth V Margotta

Joseph J Hahn

James L Yankel

Cenk Guler

Jeffrey J Taylor

David L Stucker

Jeffrey R Secker

Robert J Fetterman

Paolo Ferroni

Patrick J Sebastiani

Jianwei Chen

Stanwood L Anderson

Yung-An Chao

Walter G Lyman

William T Bogard

Donald James Hill

Larry E Erin

Michael J Prible

Kris Paserba

James Boyle

John Garing, Iii

Tim M Crede

Richard O Vollmer

Andrew M Bunker

Hugh J Murphy, Jr

Joanna C Sutton

Michael C Prible

Matthew D Mccardle

Shannon L Conner

A self-powered nuclear radiation detector. The self-powered nuclear radiation detector includes a cable assembly, a temperature compensation assembly, and a metallic outer sheath. The cable assembly includes a metallic signal lead, an insulative material surrounding the metallic signal lead, and a metallic sheath surrounding the insulative material. The temperature compensation assembly includes a second metallic signal lead, a second insulative material surrounding the second metallic signal lead, and a second metallic sheath surrounding the second insulative material. The metallic outer sheath surrounds the cable assembly and the temperature compensation assembly.

Self-powered nuclear radiation detector comprising a cable assembly and a temperature compensation assembly, and method of correcting a temperature related change of an output signal

A radioisotope production capsule is described. Each capsule includes generally an inner container for housing one of a target material and a neutron moderator, an outer container surrounding the inner container for housing the one of the target material and the neutron moderator not housed by the inner container, and cladding for isolating the target material from the neutron moderator. One or more modular capsules are placed in each of a plurality of plug fingers. Each single plug finger loaded with one or more capsules is inserted into a guide thimble of an array of guide thimbles in a fuel assembly.

Modular radioisotope production capsules and related method

A measuring device for measuring the activity of a specimen of a radioactive isotope is disclosed. The specimen of the radioactive isotope is contained within a capsule. The measuring device comprises an inner enclosure, a gamma-radiation sensitive self-power detector (SPD) positioned around the inner enclosure, and an outer enclosure positioned around the SPD and the inner enclosure. The inner enclosure comprises an internal cavity configured to receive the capsule containing the specimen. The inner enclosure defines a longitudinal axis. The outer enclosure secures the SPD to the inner enclosure such that the SPD does not move during operation and storage of the measuring device.

Device for measuring the activity of nuclear isotopes using a self-power detector

An in-core detector configured to measure a power distribution in a nuclear reactor is disclosed herein. The in-core detector includes a housing configured to be placed within a predetermined location of the nuclear reactor and a plurality of a gamma detectors. Each gamma detector of the plurality of gamma detectors includes a Schottky diode including an active semiconductor region and a Schottky contact, an Ohmic contact, a photoelectron source material configured to transfer electrons to the active region upon contact with gamma radiation, and a first and second lead. The plurality of gamma detectors are positioned within the housing such that each gamma detector of the plurality of gamma detectors is radially offset relative to an adjacent gamma detector of the plurality of gamma detectors, such that the first and second leads of each gamma detector are offset relative to the first and second leads of the adjacent gamma detector.

Devices, systems, and methods for detecting radiation with Schottky diodes for enhanced in-core measurements n-core measurements

A power sensor system for monitoring a subcritical neutron generator is provided. The power sensor system comprises a self-powered sensor insert. The self-powered sensor insert comprises an insert thimble and a detector assembly. The insert thimble includes an outer housing, a power generator configured to produce an electrical power based on an incident radiation and a first electrical interface electrically connected to the power generator. The detector assembly includes a solid state radiation detector able to provide a detector signal directly proportional to a neutron flux level, a transmitter configured to wirelessly output a transmitter signal based on the detector signal and a second electrical interface configured to electrically couple to the first electrical interface. A power monitor system comprising a power sensor system and a control system and a method for optimizing a subcritical neutron generator are also provided.

Wireless power level and power distribution monitoring and control system for subcritical spent fuel assembly array using removable SiC neutron detector thimble tube

A nuclear battery is provided. The nuclear battery comprises a radiation source layer, a first electrical insulator layer, a casing layer, a first electrode, and a second electrode. The radiation source layer comprises a composition configurable to emit beta radiation. The first electrical insulator layer is disposed over the radiation source layer. The casing layer is disposed over the first electrical insulator layer. The casing layer comprises a composition configured to inhibit traversal of beta radiation. The first electrode is in electrical communication with the radiation source layer. The second electrode is in electrical communication with the casing layer. A voltage potential is present between the first electrode and the second electrode when the radiation source layer emits beta radiation.

Nuclear battery

A method of removing an irradiated capsule from inside of a burnable absorber rodlet. The capsule can contain produced Co-60. The method includes inducing an electromagnetic flux into the capsule to magnetically lock the capsule with a capsule removal module. While locked, the capsule can be relatively moved along a longitudinal axis of the rodlet to remove the capsule from the rodlet.

Method of magnetically removing an irradiated capsule from a burnable absorber rodlet

A system for detecting a leak in a cladding tube in a nuclear reactor that has a plurality of cladding tubes housed in a plurality of horizontally arranged channels. A plurality of tubes are positioned adjacent to the channels. A plurality of solid state radiation detectors are in each of the tubes. The detectors are spaced from each other along the length of each tube. The detectors can detect the presence of radiation from a selected fission product within a channel. A processor calculates a leak location by receiving signals above a base line level from the detectors, determining differences in signal strength from the detectors over a period of time, and identifying location of the detector emitting the strongest signal.

System to detect and locate the in-core position of fuel bundles with cladding perforations in CANDU-style nuclear reactors

The present disclosure is generally related to methods, systems and devices for direct production of a radioisotope-based cancer treatment pharmaceutical directly from a corresponding non-radioactive drug molecule precursor by irradiating the non-radioactive drug molecule precursor using neutrons produced by an electronic neutron generator array or other neutron generator sources.

Method and device for direct production of radio-isotope based cancer treatment pharmaceuticals

Methods of manufacture for nuclear batteries are provided. The method comprises inserting a radiation source material into a cavity defined within a first component to form a radiation source layer. The first component comprises a first electrical insulator layer defining the cavity and a first casing layer disposed over the first electrical insulator layer. The method comprises contacting the first casing layer with a second casing layer of a second component to form an assembly. The second component comprises a second electrical insulator layer and the second casing layer disposed in contact with the second electrical insulator layer. The method comprises swaging the assembly to form the nuclear battery.

Methods of manufacture for nuclear batteries

Disclosed are a radioisotope activity surveillance system and methods. The system includes a fuel rod assembly having a plurality of nuclear fuel rods and a target assembly having a top nozzle including an orifice plate and at least one target material rod fixedly coupled to the orifice plate. The least one target material rod is slidably disposed within the fuel rod assembly. A sensing assembly defines an opening sized and configured to receive the target assembly therethrough. The sensing assembly includes a self-powered detector assembly to detect radioisotope activity of the target rod material. Also disclosed is a method for measuring a self-powered detector signal to calculate radioisotope activity of a target assembly and a method for analyzing total activity of a desired radioisotope.

Radioisotope activity surveillance apparatus, system, and method

A system for measuring gamma spectroscopy of a neutron irradiated material includes a plurality of semiconductor sensors. Each of the semiconductor sensors includes a gamma ray receiving surface disposed above a Schottky layer in contact with an n-doped active layer. The receiving surface is configured to emit electrons upon irradiation by gamma rays. The receiving surface contacts an adjustable telescoping mount configured to adjust the distance between the receiving surface and the Schottky layer. The n-doped layer is fabricated to have a thickness designed to pass through electrons having greater than a defined energy. The combination of adjustable receiving surface and active layer thickness define a minimum and maximum energy response of each of the sensors. Multiple sensors may be integrated in an array in which each sensor has its own energy response. An array of such sensors can measure the gamma spectrum of a material irradiated with neutrons.

Fixed in-core detector design using sic Schottky diodes configured with a high axial and radial sensor density and enhanced fission gamma measurement sensitivity

A system for measuring radiation activity of a target radioisotope being produced in a reactor core is disclosed. The system includes a cable assembly and a radiation detector. The cable assembly includes a housing, a target cable configured to position the housing, and a drive cable couplable and decouplable with the target cable. The target radioisotope is positioned within the housing. The drive cable is configured to drive the target cable. The radiation detector is configured to periodically measure the radiation activity of the target radioisotope being produced.

Method for periodically measuring the total gamma radiation activity of a target radioisotope being produced inside a nuclear reactor core

Wireless power level and power distribution monitoring and control system for subcritical spent fuel assembly array using removable SIC neutron detector thimble tube

A radioactivity measurement device for measuring an activity level of a radioisotope source is provided. The radioactivity measurement device comprises a housing and a self-powered detector. The housing comprises an outer shell and an inner shell, wherein the inner shell is adapted to house an insertable radioisotope source, and wherein the outer shell and the inner shell are configured to form a hollow annular region. The self-powered detector, positioned within the hollow annular region of the housing, comprises at least one tubular emitter configured to provide a source of electron emission proportional to a radioisotope activity level of the insertable radioisotope source and at least one tubular collector configured to sink the electron emission. A radioactivity level measurement system comprising at least one radioactivity measurement device, a shipping cask incorporating the radioactivity level measurement system and a method for shipping the shipping cask are also provided.

Device and method for rapidly measuring the activity of nuclear isotopes contained within a cylindrical enclosure using the current output from a lead self-powered detector element

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Harrison City, PA, United States of America

Michael D Heibel