Westinghouse Electric Company LLC

Westinghouse Electric Corporation

The United States of America As Represented by the United States

Abdul R Dulloo

Thomas V Congedo

John G Seidel

Francis H Ruddy

Frank H Ruddy

Arnold H Fero

Randy G Lott

William A Byers

David F McLaughlin

Brandon Damon Thomas

Alex Levinsky

Stanwood L Anderson

John M Iacovino, Jr

Vefa N Kucukboyaci

Richard F Wright

Randall O Wilson

Ernest Sirianni

Charles D Brandt

Bojan Petrovic

John G Siedel

A heat pipe configured to remove heat from a nuclear reactor core is disclosed herein. The heat pipe can include an inner housing defining an inner volume configured to accommodate a heat source and an outer housing configured about the inner housing and the heat source. A wick can be positioned between at least a portion of the inner housing and at least a portion of the outer housing, wherein the wick can include a capillary material, and wherein the wick can define an intermediate volume between the inner housing and the outer housing. A working fluid can be positioned within the intermediate volume, wherein the working fluid can evaporate at a first end of the heat pipe and condense at a second end of the heat pipe adjacent to a heat exchanger, and wherein the wick can return condensed working fluid to the first end of the heat pipe.

Heat pipe having a wick between concentric inner and outer housings, for use in heat removal from a nuclear reactor core

A method and associated apparatus for detecting concealed fissile, fissionable or special nuclear material in an article, such as a shipping container, is provided. The article is irradiated with a source of fast neutrons, and fast neutrons released by the fissile or fissionable material, if present, are detected between source neutron pulses. The method uses a neutron detector that can detect and discriminate fast neutrons in the presence of thermal neutrons and gamma radiation. The detector is able to process high count rates and is resistant to radiation damage, and is preferably a solid state neutron detector comprised of silicon carbide.

Nonintrusive method for the detection of concealed special nuclear material

A method of monitoring a nuclear reactor includes monitoring the nuclear reactor with a plurality of radiation sensors having spaced apart attachments to a radiation hard cable; providing signal processing equipment at each end of the cable for processing signals from the radiation sensors; establishing signal time intervals based upon differences in time of arrival of signals from the radiation sensors to the signal processing equipment at each end of the cable; producing a plurality of output signals each of which has an amplitude proportional to a difference in time of arrival of a signal to the signal processing equipment at each end of the cable; and rejecting output signals which have a difference in time of arrival outside of the signal time intervals.

Method and system for monitoring radiation and rejecting noise

Detectors are used to monitor the status of spent nuclear fuel storage containers non-invasively while they remain in storage casks. The detectors measure neutron flux and &ggr;-ray flux and may also measure temperature variations of the spent nuclear fuel. The measurements can be accomplished actively or passively, with minimal exposure of individuals to radiation fields or other hazardous conditions. Preferred neutron and &ggr;-ray detectors have a semiconductor active region that is resistant to neutron damage. Incipient structural failures may also be detected using measurements based on electrical continuity, with data being transmitted to an external pickup coil.

In-situ self-powered monitoring of stored spent nuclear fuel

An improved method and apparatus for performing measurements related to spent nuclear fuel burnup is disclosed. The use of temperature- and radiation-resistant semiconductor detectors permits simultaneous monitoring of neutron and gamma ray emission rates from spent fuel, as well as providing axial burnup gradient information. The semiconductor detectors preferably comprise SiC. The method and apparatus provide significant cost reductions, lowered radiation exposures and increased operational safety during spent fuel monitoring operations.

Monitoring of neutron and gamma radiation

A neutron detector array is capable of measuring a wide range of neutron fluxes. The array includes multiple semiconductor neutron detectors. Each detector has a semiconductor active region that is resistant to radiation damage. In one embodiment, the array preferably has a relatively small size, making it possible to place the array in confined locations. The ability of the array to detect a wide range of neutron fluxes is highly advantageous for many applications such as detecting neutron flux during start up, ramp up and full power of nuclear reactors.

Solid state neutron detector array

Prompt Gamma Neuteon Activation Analysis (PGNAA) is employed to determined in situ the content of nickel, copper, or other embrittlement-enhancing elements within the weld metal joints of nuclear reactor pressure vessels.

PGNAA system for non-invasively inspecting RPV weld metal in situ, to

A radiation resistant solid state neutron detector is disclosed. The detector uses a neutron convertor material such as boron or lithium to react with neutrons to create charged particles that are received in a semiconductor active region of the detector. The active thickness of the detector is smaller than the range of the charged particles. Since most of the radiation damage produced by impinging charged particles occurs near the end of the range of the particles, displacement damage predominantly occurs outside of the active region. Although the charged particles pass through the semiconductor material, the particles cause electron excitation within the semiconductor material which is detected in the form of an electronic pulse. A preferred semiconductor material for the active region is silicon carbide. The detectors provide increased resistance to radiation damage, improve high temperature operation, and the ability to obtain real time measurements of neutron flux in reactor cavities and other previously inaccessible locations.

Growing community of inventors

Pittsburgh, PA, United States of America

Abdul R Dulloo