G01T3/00

Boron Trifluoride as a Quench Gas for Neutron Proportional Counters
20230045923 · 2023-02-16 ·

A neutron proportional counter is provided. The proportional counter can include a chamber and a gas mixture. The chamber includes an anode and a cathode. The gas mixture is contained within the chamber and includes at least one neutron sensitive fill gas and a quench gas including BF.sub.3. In certain embodiments, the neutron sensitive fill gas can be configured for detection of thermal neutrons (e.g., He-3), fast neutrons (e.g., He-4, H.sub.2), or both (e.g., UF6).

ACCELERATING FISSILE MATERIAL DETECTION WITH A NEUTRON SOURCE
20180003832 · 2018-01-04 ·

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly to count neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a Poisson neutron generator for in-beam interrogation of a possible fissile neutron source and a DC power supply that exhibits electrical ripple on the order of less than one part per million. Certain voltage multiplier circuits, such as Cockroft-Walton voltage multipliers, are used to enhance the effective of series resistor-inductor circuits components to reduce the ripple associated with traditional AC rectified, high voltage DC power supplies.

ACCELERATING FISSILE MATERIAL DETECTION WITH A NEUTRON SOURCE
20180003832 · 2018-01-04 ·

A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly to count neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a Poisson neutron generator for in-beam interrogation of a possible fissile neutron source and a DC power supply that exhibits electrical ripple on the order of less than one part per million. Certain voltage multiplier circuits, such as Cockroft-Walton voltage multipliers, are used to enhance the effective of series resistor-inductor circuits components to reduce the ripple associated with traditional AC rectified, high voltage DC power supplies.

Ion implanter and ion implantation method

An ion implanter includes: a plurality of devices which are disposed along a beamline along which an ion beam is transported; a plurality of neutron ray measuring instruments which are disposed at a plurality of positions in the vicinity of the beamline and measure neutron rays which are generated at a plurality of locations of the beamline due to collision of a high-energy ion beam; and a control device which monitors at least one of the plurality of devices, based on a measurement value in at least one of the plurality of neutron ray measuring instruments.

Ion implanter and ion implantation method

An ion implanter includes: a plurality of devices which are disposed along a beamline along which an ion beam is transported; a plurality of neutron ray measuring instruments which are disposed at a plurality of positions in the vicinity of the beamline and measure neutron rays which are generated at a plurality of locations of the beamline due to collision of a high-energy ion beam; and a control device which monitors at least one of the plurality of devices, based on a measurement value in at least one of the plurality of neutron ray measuring instruments.

Boron nitride nanotube coated optical waveguide and uses thereof

A solution is provided comprising boron nitride nanotubes (BNNTs) in a liquid solvent. An optical waveguide, such as an optical fiber, is contacted with the solution so as to form a layer of the solution supported on at least a portion of the optical waveguide. The liquid solvent is then removed from the layer of the solution supported on the optical waveguide in order to form a coating of the BNNTs on the optical waveguide. Further provided is a BNNT coated optical waveguide for use as a sensor.

SYSTEM FOR MEASURING FAST NEUTRON FLUENCE FOR A NUCLEAR REACTOR, ASSOCIATED INSTALLATION, MEASUREMENT METHOD AND COMPUTER PROGRAM PRODUCT

A measuring system includes a detector having an optical waveguide including a primary dopant capable of transmuting, by neutron capture, into a stable secondary dopant that is less neutron-absorbent than the primary dopant, a moderation layer suitable for slowing down fast neutrons, and an analysis device connected to the detector. The analysis device is configured to inject, into the waveguide, an interrogation wave having a wavelength corresponding to an absorption peak of the secondary dopant, detect a response wave emitted by the waveguide, calculate, from the detected response wave, a piece of information relating to a concentration of secondary dopant in the waveguide, and, based on the information relating to the calculated concentration of secondary dopant, determine a fluence of fast neutrons during a predetermined secondary period.

SYSTEM FOR MEASURING FAST NEUTRON FLUENCE FOR A NUCLEAR REACTOR, ASSOCIATED INSTALLATION, MEASUREMENT METHOD AND COMPUTER PROGRAM PRODUCT

A measuring system includes a detector having an optical waveguide including a primary dopant capable of transmuting, by neutron capture, into a stable secondary dopant that is less neutron-absorbent than the primary dopant, a moderation layer suitable for slowing down fast neutrons, and an analysis device connected to the detector. The analysis device is configured to inject, into the waveguide, an interrogation wave having a wavelength corresponding to an absorption peak of the secondary dopant, detect a response wave emitted by the waveguide, calculate, from the detected response wave, a piece of information relating to a concentration of secondary dopant in the waveguide, and, based on the information relating to the calculated concentration of secondary dopant, determine a fluence of fast neutrons during a predetermined secondary period.

DEVICE FOR DETECTING NEUTRONS WITH IONIZATION CHAMBER AND WITH OPTICAL TRANSDUCTION COMPRISING A PLURALITY OF OPTICAL CAVITIES, EACH ACCOMMODATING THE FREE END OF AN OPTICAL FIBER

Device for detecting neutrons with ionization chamber and with optical transduction comprising a plurality of optical cavities, each accommodating the free end of an optical fiber.

The invention relates to a device (1) for detecting neutrons comprising at least one sealed ionization chamber (2) and with optical transduction with a plurality of cavities whose operation is each based on optical transduction using an optical fiber whose free end is within the cavity, which allows multipoint neutron-flux measurement, the measurement points being axially distributed.

Self-powered in-core detector arrangement for measuring flux in a nuclear reactor core

A self-powered in-core detector arrangement for measuring flux in a nuclear reactor core includes a first in-core detector and a second in-core detector. The first in-core detector includes a first flux detecting material, a first lead wire extending longitudinally from a first axial end of the first flux detecting material, a first insulating material surrounding outer diameters of the first flux detecting material and the first lead wire and a first sheath surrounding the first insulating material. The first sheath includes a first section surrounding the first flux detecting material and a second section surrounding the first lead wire. The first section of the first sheath has a greater outer diameter than the second section of the first sheath. The second in-core detector includes a second flux detecting material, a second lead wire extending longitudinally from a first axial end of the second flux detecting material, a second insulating material surrounding outer diameters of the second flux detecting material and the second lead wire, and a second sheath surrounding the second insulating material. The second sheath includes a first section surrounding the second flux detecting material and a second section surrounding the second lead wire. The first section of the second sheath has a greater outer diameter than the second section of the second sheath. The first section of the first sheath is axially offset from the first section of the second sheath and radially aligned with the second section of second sheath.