A boron coated straw detector for use in a neutron detection system is disclosed comprising a boron coated straw having at least one boron-coated septum radially oriented and extending a pre-determined distance towards the center of the straw. Preferably, the straw comprises a plurality of septa comprising a rigid surface, coated on both sides with a boron composition. Preferably, the septa run the length of the straw detector from one end of the straw to the other. The area coated on the septa adds to the area coated on the arc segments offering a significant benefit in sensitivity of the neutron detector.

Disclosed are a radioisotope activity surveillance system and methods. The system includes a fuel rod assembly having a plurality of nuclear fuel rods and a target assembly having a top nozzle including an orifice plate and at least one target material rod fixedly coupled to the orifice plate. The least one target material rod is slidably disposed within the fuel rod assembly. A sensing assembly defines an opening sized and configured to receive the target assembly therethrough. The sensing assembly includes a self-powered detector assembly to detect radioisotope activity of the target rod material. Also disclosed is a method for measuring a self-powered detector signal to calculate radioisotope activity of a target assembly and a method for analyzing total activity of a desired radioisotope.

A detector for generating an electrical current that is proportional to a flux of neutrons includes a neutron sensitive emitter, a conductive collector, an insulator between the neutron-sensitive emitter and the collector, an electrical connection to the neutron sensitive emitter, and an electrical connection to the conductive collector. The neutron sensitive emitter includes an emitter material with no more than 2 stable isotopes, and which upon impact by a neutron having an energy of from 100 keV to 1000 keV will generate electrons in proportion to the flux of neutrons in less than 10 minutes, and any generated electrons not generated in less than 10 minutes will be generated in no less than 30 days. A method of detecting neutrons generated by a nuclear reactor is also disclosed.

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.

A power sensor system for monitoring a subcritical neutron generator is provided. The power sensor system comprises a self-powered sensor insert. The self-powered sensor insert comprises an insert thimble and a detector assembly. The insert thimble includes an outer housing, a power generator configured to produce an electrical power based on an incident radiation and a first electrical interface electrically connected to the power generator. The detector assembly includes a solid state radiation detector able to provide a detector signal directly proportional to a neutron flux level, a transmitter configured to wirelessly output a transmitter signal based on the detector signal and a second electrical interface configured to electrically couple to the first electrical interface. A power monitor system comprising a power sensor system and a control system and a method for optimizing a subcritical neutron generator are also provided.

Detectors, a system and a method for detecting ionizing radiation are provided. In some aspects, a detector includes a first layer comprising a first conducting material, and a second layer comprising a second conducting material, wherein at least one of the first layer and second layer is configured to produce secondary particles upon irradiation by an ionizing radiation. The detector also includes a separating layer positioned between the first and second layer configured to transport therebetween at least one of charges associated with the secondary particles and charges produced by the secondary particles, wherein an electric current generated by the charges, and collected between the first and second layer, is indicative of properties the ionizing radiation.

A method of determining radiation exposure during a criticality excursion of a dosimeter having at least one fluorescent nuclear track detector (FNTD) element includes determining the power spectrum integral (PSI) value of the fluorescent images obtained from FNTD element at each of a plurality of different depths using laser induced fluorescent microscopy; normalizing the depth profile to the shallowest depth; fitting a double exponential function to the normalized depth profile; determining the median neutron energy from the E=f(1/e) function; and determining a neutron energy dose correction factor (NCF) from the NCF=f(E) function. The neutron dose, D, can then be calculated by dividing absolute value of the neutron-induced PSI by a sensitivity factor S and multiplying it by the neutron energy dose correction factor NCF.

A boron coated straw detector for use in a neutron detection system is disclosed comprising a boron coated straw having at least one boron-coated septum radially oriented and extending a pre-determined distance towards the center of the straw. Preferably, the straw comprises a plurality of septa comprising a rigid surface, coated on both sides with a boron composition. Preferably, the septa run the length of the straw detector from one end of the straw to the other. The area coated on the septa adds to the area coated on the arc segments offering a significant benefit in sensitivity of the neutron detector.

Disclosed are a radioisotope activity surveillance system and methods. The system includes a fuel rod assembly having a plurality of nuclear fuel rods and a target assembly having a top nozzle including an orifice plate and at least one target material rod fixedly coupled to the orifice plate. The least one target material rod is slidably disposed within the fuel rod assembly. A sensing assembly defines an opening sized and configured to receive the target assembly therethrough. The sensing assembly includes a self-powered detector assembly to detect radioisotope activity of the target rod material. Also disclosed is a method for measuring a self-powered detector signal to calculate radioisotope activity of a target assembly and a method for analyzing total activity of a desired radioisotope.

A radiographic imaging apparatus includes: a radiographic imager that performs imaging; a built-in power storage device that supplies electric power to the imager, an attachment portion to which an external power storage device that supplies electric power to the imager is to be detachably attached; a connector that is electrically connectable to an external apparatus; and a hardware processor that, in a case where the processor is connected to the external apparatus by the connector and the imager is performing imaging, performs control to supply electric power supplied from the external apparatus to the imager, and in a case where the processor is connected to the external apparatus by the connector and the imager is not performing imaging, performs control to supply the electric power supplied from the external apparatus to the built-in power storage device or the external power storage device attached to the attachment portion.