Uchicago Argonne, LLC

The United States of America As Represented by the Department of Energy

University of Michigan

Raymond T Klann

Richard B Vilim

Douglas McGregor

Douglas Scott McGregor

Sergio De La Barrera

Young Soo Park

A system and method for determining the shielding thickness of a detected radiation source. The gamma ray spectrum of a radiation detector is utilized to estimate the shielding between the detector and the radiation source. The determination of the shielding may be used to adjust the information from known source-localization techniques to provide improved performance and accuracy of locating the source of radiation.

Method and system for determining radiation shielding thickness and gamma-ray energy

A system and method for determining a probability of the location of an illicit radiation source within an environment based on directional detectors. An embodiment includes a plurality of directional radiation detectors distributed about the environment and integrated with a processing unit adapted to determine the probability of the source location based on the radiation count data received from the plurality of detectors. The processing unit is further adapted to output information indicative of the location of the radiation source within the environment.

Source localization using multiple units of a tight-pitched detector array

A system for detecting unsecured nuclear materials. Whereas current portal monitors rely in part on physical prominence to deter materials from entering the country, their application at intra-modal transport points may actually serve to divert the movement of nuclear materials rather than aid in interception. A flexible and low-profile system has been developed for unobtrusive detection and tracking of radioactive sources in transit suited for deployment at traffic choke points such as rest stops, toll collection plazas, truck stops, and bridges. The system includes gamma radiation detectors, networking for linking these detectors, signal processing algorithms, and a central processing and control unit.

Tracking of moving radioactive sources

Neutron detectors, advanced detector process techniques and advanced compound film designs have greatly increased neutron-detection efficiency. One embodiment of the detectors utilizes a semiconductor wafer with a matrix of spaced cavities filled with one or more types of neutron reactive material such asB orLiF. The cavities are etched into both the front and back surfaces of the device such that the cavities from one side surround the cavities from the other side. The cavities may be etched via holes or etched slots or trenches. In another embodiment, the cavities are different-sized and the smaller cavities extend into the wafer from the lower surfaces of the larger cavities. In a third embodiment, multiple layers of different neutron-responsive material are formed on one or more sides of the wafer. The new devices operate at room temperature, are compact, rugged, and reliable in design.

High-efficiency neutron detectors and methods of making same

The detection efficiency, or sensitivity, of a neutron detector material such as of Si, SiC, amorphous Si, GaAs, or diamond is substantially increased by forming one or more cavities, or holes, in its surface. A neutron reactive material such as of elemental, or any compound of, B, Li, LiF, U, or Gd is deposited on the surface of the detector material so as to be disposed within the cavities therein. The portions of the neutron reactive material extending into the detector material substantially increase the probability of an energetic neutron reaction product in the form of a charged particle being directed into and detected by the neutron detector material.

Pocked surface neutron detector

A device for detecting neutrons includes a semi-insulated bulk semiconductor substrate having opposed polished surfaces. A blocking Schottky contact comprised of a series of metals such as Ti, Pt, Au, Ge, Pd, and Ni is formed on a first polished surface of the semiconductor substrate, while a low resistivity (&ldquo;ohmic&rdquo;) contact comprised of metals such as Au, Ge, and Ni is formed on a second, opposed polished surface of the substrate. In one embodiment, n-type low resistivity pinout contacts comprised of an Au/Ge based eutectic alloy or multi-layered Pd/Ge/Ti/Au are also formed on the opposed polished surfaces and in contact with the Schottky and ohmic contacts. Disposed on the Schottky contact is a neutron reactive film, or coating, for detecting neutrons. The coating is comprised of a hydrogen rich polymer, such as a polyolefin or paraffin; lithium or lithium fluoride; or a heavy metal fissionable material. By varying the coating thickness and electrical settings, neutrons at specific energies can be detected. The coated neutron detector is capable of performing real-time neutron radiography in high gamma fields, digital fast neutron radiography, fissile material identification, and basic neutron detection particularly in high radiation fields.

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Channahon, IL, United States of America

Raymond T Klann