University of California

Triad National Security, LLC

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

Los Alamos National Security, LLC

Kiril Dimitrov Ianakiev

Martyn Thomas Swinhoe

Michael Browne

Metodi Iliev

James L Smith

Markus Peter Hehlen

Peter Brent Littlewood

Jason Charles Lashley

Krastan B Blagoev

Andrea Favalli

Clair J Sullivan

Boian S Alexandrov

Sin Tao Hsue

Adrienne LaFleur

Jeffrey M Audia

Thomas Roy Hill

John Paul Lestone

Improved, high count rate thermal neutron counters and electronics enabling new, higher measurement capabilities are disclosed. Next generationHe andB tubes may include an electronics package capable of operating at higher count rates and in higher gamma fields and providing more efficient use ofHe gas. Conventional detector systems may also be upgraded, providing a possible solution to measure spent nuclear fuel with high neutron efficiency previously not possible inU fission counter systems. Switching the number of tubes per amplifier allows use of the measured nuclear material for a calibration standard for dead time correction, increasing accuracy of neutron measurements systems. An optimized detector geometry and advanced electronics with double pulse filtering and a dual channel readout may be provided. A bipolar shaper may improve dead time, provide efficient detector use, reduce double pulsing, facilitate high count rate measurements, and allow remote threshold setting.

High count rate thermal neutron detectors and electronics

Devices/apparatuses are disclosed that include a photoemitting component, a photosensitive component deposited on the photoemitting component, a charge collection component, and a hollow enclosure for housing the photoemitting component, the photosensitive component, the charge collection component, or combinations thereof. Methods for making and using the apparatuses are also disclosed.

Scintillation detectors

A system and method are disclosed for determining the enrichment ofU in Uranium Hexafluoride (UF6) utilizing synthesized X-rays which are directed at a container test zone containing a sample of UF6. A detector placed behind the container test zone then detects and counts the X-rays which pass through the container and the UF6. In order to determine the portion of the attenuation due to the UF6 gas alone, this count rate may then be compared to a calibration count rate of X-rays passing through a calibration test zone which contains a vacuum, the test zone having experienced substantially similar environmental conditions as the actual test zone. Alternatively, X-rays of two differing energy levels may be alternately directed at the container, where either the container or the UF6 has a high sensitivity to the difference in the energy levels, and the other having a low sensitivity.

Method and apparatus for measuring enrichment of UF6

A neutron detector has a compound of lithium in a single crystal form as a neutron sensor element. The lithium compound, containing improved charge transport properties, is either lithium niobate or lithium tantalate. The sensor element is in direct contact with a monitor that detects an electric current. A signal proportional to the electric current is produced and is calibrated to indicate the neutrons sensed. The neutron detector is particularly useful for detecting neutrons in a radiation environment. Such radiation environment may, e.g. include gamma radiation and noise.

Semiconductor neutron detector

The present invention includes an apparatus and corresponding method for temperature correction and count rate expansion of inorganic scintillation detectors. A temperature sensor is attached to an inorganic scintillation detector. The inorganic scintillation detector, due to interaction with incident radiation, creates light pulse signals. A photoreceiver processes the light pulse signals to current signals. Temperature correction circuitry that uses a fast light component signal, a slow light component signal, and the temperature signal from the temperature sensor to corrected an inorganic scintillation detector signal output and expanded the count rate.

Apparatus and method for temperature correction and expanded count rate of inorganic scintillation detectors

A detector for detecting neutrons and gamma radiation includes a cathode that defines an interior surface and an interior volume. A conductive neutron-capturing layer is disposed on the interior surface of the cathode and a plastic housing surrounds the cathode. A plastic lid is attached to the housing and encloses the interior volume of the cathode forming an ionization chamber, into the center of which an anode extends from the plastic lid. A working gas is disposed within the ionization chamber and a high biasing voltage is connected to the cathode. Processing electronics are coupled to the anode and process current pulses which are converted into Gaussian pulses, which are either counted as neutrons or integrated as gammas, in response to whether pulse amplitude crosses a neutron threshold. The detector according to the invention may be readily fabricated into single or multilayer detector arrays.

Neutron and gamma detector using an ionization chamber with an integrated body and moderator

Growing community of inventors

Los Alamos, NM, United States of America

Kiril Dimitrov Ianakiev