Westinghouse Electric Corporation

Westinghouse Electric Company LLC

Other

The United States of America As Represented by the United States

Frank H Ruddy

John G Seidel

Thomas V Congedo

Abdul R Dulloo

David F McLaughlin

Arnold H Fero

Joseph L Gonzalez

Randy G Lott

Edward Jean Lahoda

Thomas S Snyder

George J Collins

David C Grant

William A Byers

John Bartko

Brandon Damon Thomas

John M Iacovino, Jr

Ellen V Gray

William H Carder

Randall O Wilson

Ernest Sirianni

Charles D Brandt

John G Siedel

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

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

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.

Radiation resistant solid state neutron detector

The present invention provides for methods for on-line monitoring of a molten process phase to determine the extent of extraction of radioactive species from a waste metal contaminated with the radioactive species. The waste metal is mixed with an inorganic flux material in a furnace, wherein the flux material extracts the radioactive species from the waste metal. Periodically, a portion of the furnace composition is sampled from the furnace and separated into a molten flux phase and a molten metal phase. Either of these phases is then analyzed in its molten state to determine the extent of the extraction process.

Metal decontamination process and systems for accomplishing same

A system for determining depth profiles of concentrations of hazardous elements in soils comprises a neutron source for generating neutrons of a first energy level and irradiating a volume of soil with the neutrons. Nuclear reactions are effected within the soil and gamma radiation is emitted from the soil. The system also includes an array of gamma detectors for detecting gamma radiation emitted from the soil; source electronics for controlling the width of regularly repeated pulses of neutrons generated by the neutron source; detector electronics associated with the gamma detectors for amplifying and digitalizing signals generated by the gamma detectors and storing data representing the digitalized signals; spectral analysis software for analyzing the data and determining the concentrations of selected target elements in the soil; and an acquisition interface module (AIM). The AIM controls the timing of the source and detector electronics such that the neutron source generates neutrons in regularly repeated bursts of a prescribed pulse width and the detectors and detector electronics detect gamma rays during a plurality of time intervals associated with the burst and acquire groups of data. Each group is indicative of a number of gamma rays emitted and their energy levels during a corresponding time interval. The system also includes a mobile platform carrying the neutron source, array of gamma ray detectors and software for determining a depth profile of a target element. Trace elements can also be detected with the disclosed system.

Prompt gamma neutron activation analysis system

A method for determining the depth of a gamma emitting element beneath the surface of a volume of soil is disclosed. The disclosed method includes the steps of detecting gamma rays at a first height h.sub.1 above the surface; detecting gamma rays at a second height h.sub.2 above the surface; determining a ratio R representative of the ratio of the number of gamma rays detected at h.sub.2 to the number of gamma rays detected at h.sub.1, or vice versa; and inferring, on the basis of the ratio R, an estimate of the depth of the gamma emitting element beneath the surface.

Method and apparatus for determining the depth of a gamma emitting

An integrated temperature monitor (ITM) is placed in a protective carrier and the carrier is placed in a base. Thermally conductive adhesive is injected around the carrier. A cover is placed on the base, forming a container around the ITM. The adhesive holds the carrier in the container holding the base and cover together. Two screws also hold the base and cover together as the adhesive cures. The base has slots for seizing wire. The container is attached to a device with thermally conductive adhesive and the seizing wire. A bar code label is placed on the container. The end of the container is cut to expose the carrier and monitor and create an opening to remove the ITM from the container.

Method and apparatus for passive contact temperature measurements

Growing community of inventors

Monroeville, PA, United States of America

Frank H Ruddy