Abstract: A method for determining neutron flux by utilizing a portable Radionuclide Identification Device (RID) as it is used in homeland security applications is provided. The RID has an inorganic crystal comprising iodine, a light detector and electronics for the evaluation of the output signals of the light detector. The method includes a step of detecting, with the light detector, light emitted by the crystal following the interaction of nuclear radiation with the crystal. The intensity of the light measured is a function of the energy deposed in the crystal by said nuclear radiation during the interaction with the crystal.

Abstract: Provided are transparent molded bodies for use as a scintillator for measuring the type and intensity of ionizing and non-ionizing radiation, including an organic polymer and, if desired, at least one additive which, under the influence of at least one of ionizing and non-ionizing radiation, emits scintillation radiation in the range from UV to IR light, the aim is to improve optical and mechanical properties, robustness against, environmental influences and the manufacturability. This was achieved in that the organic polymer at least in part contains a polyaddition product of polyfunctional isocyanates and one or more polyfunctional hardener components.

Abstract: Provided are transparent molded bodies for use as a scintillator for measuring the type and intensity of ionizing and non-ionizing radiation, including an organic polymer and, if desired, at least one additive which, under the influence of at least one of ionizing and non-ionizing radiation, emits scintillation radiation in the range from UV to IR light, the aim is to improve optical and mechanical properties, robustness against environmental influences and the manufacturability. This was achieved in that the organic polymer at least in part contains a polyaddition product of polyfunctional isocyanates and one or more polyfunctional hardener components.

Abstract: A method for determining neutron flux by utilizing a portable Radionuclide Identification Device (RID) as it is used in homeland security applications is provided. The RID has an inorganic crystal comprising iodine, a light detector and electronics for the evaluation of the output signals of the light detector. The method includes a step of detecting, with the light detector, light emitted by the crystal following the interaction of nuclear radiation with the crystal. The intensity of the light measured is a function of the energy deposed in the crystal by said nuclear radiation during the interaction with the crystal.

Abstract: A method is provided for determining the dose rate {dot over (H)} of nuclear radiation field, namely a gamma radiation field, with a radiation detection system (RDS), comprising a scintillator, a photodetector, an amplifier and a pulse measurement electronics. The pulse measurement electronics includes a sampling analog to digital converter, where the nuclear radiation deposes at least some of its energy in the scintillator, thereby producing excited states in the scintillation material, with the excited states decaying thereafter under emission of photons with a decay time ?. Photons are absorbed by the photodetector under emission of electrons, those electrons forming a current pulse, said current pulse being amplified so that the resulting current signal can be processed further in order to determine the charge of the pulse measured.

Abstract: A method of measurement of both gamma radiation and neutrons with energies above 500 keV is provided utilizing a scintillation crystal. The method includes allowing gamma quanta and neutrons to interact with the scintillation crystal, collecting light emitted by the scintillation crystal and letting that light interact with a photo detector, and amplifying the signal output. The method then digitizes the amplifier output signal, determines a charge collection time for each interaction measured, determining light decay times, separating signals with distinct decay times, determining a total charge collected from signals with the distinct decay times, and sorting charge signals in a spectrum. The method then counts signals with a second decay time and determines a count rate.

Abstract: A method is provided for determining the dose rate {dot over (H)} of nuclear radiation field, namely a gamma radiation field, with a radiation detection system (RDS), comprising a scintillator, a photodetector, an amplifier and a pulse measurement electronics. The pulse measurement electronics includes a sampling analog to digital converter, where the nuclear radiation deposes at least some of its energy in the scintillator, thereby producing excited states in the scintillation material, with the excited states decaying thereafter under emission of photons with a decay time ?. Photons are absorbed by the photodetector under emission of electrons, those electrons forming a current pulse, said current pulse being amplified so that the resulting current signal can be processed further in order to determine the charge of the pulse measured.

Abstract: Provided are transparent molded bodies for use as a scintillator for measuring the type and intensity of ionizing and non-ionizing radiation, including an organic polymer and, if desired, at least one additive which, under the influence of at least one of ionizing and non-ionizing radiation, emits scintillation radiation in the range from UV to IR light, the aim is to improve optical and mechanical properties, robustness against environmental influences and the manufacturability. This was achieved in that the organic polymer at least in part contains a polyaddition product of polyfunctional isocyanates and one or more polyfunctional hardener components.

Abstract: A method of measurement of both gamma radiation and neutrons with energies above 500 keV is provided utilizing a scintillation crystal. The method includes allowing gamma quanta and neutrons to interact with the scintillation crystal, collecting light emitted by the scintillation crystal and letting that light interact with a photo detector, and amplifying the signal output. The method then digitizes the amplifier output signal, determines a charge collection time for each interaction measured, determining light decay times, separating signals with distinct decay times, determining a total charge collected from signals with the distinct decay times, and sorting charge signals in a spectrum. The method then counts signals with a second decay time and determines a count rate.

Abstract: A self-stabilizing scintillation detector system for the measurement of nuclear radiation, preferably gamma radiation, is provided, the system comprising a scintillation crystal, a photo detector, a photomultiplier (PMT) and one or two fast digital sampling analog to digital converters (ADC), where the scintillator is selected from a group of materials having a light decay time of at least 1 ns, and where the PMT is set to its highest possible gain. A first ADC for processing the single photo electron induced signals is connected to the PMT output, namely the anode output, this first ADC being set to operate with a very high sampling rate of at least 10 MHz, and a second ADC for processing the nuclear particle induced signals is connected to one of the PMT's dynodes with a significantly lower amplification.

Abstract: Readout circuitry for a PMT is provided, which is adapted for delivering a pair of first and second synchronous output voltage signals to a pair of outputs, the first output signal of the pair having a first AC portion being representative of a charge flow of an anode of the PMT over time, the second output signal of the pair having a second AC portion which corresponds to an inverted form of the first AC portion of the first output signal. The readout circuitry comprises a first sub-circuitry which is adapted to derive the first output signal from the charge flow over time of the anode, and a second sub-circuitry which is adapted to derive the second output signal from a charge flow over time of at least one dynode of the PMT.

Abstract: A method of distinguishing effective pulses from test pulses in a scintillation detector that generates measurement light pulses includes providing a regularly-pulsed test light source that produces individual test light pulses having a time-dependent course of relative light intensity, which differs from a time-dependent course of relative light intensity of the measurement light pulses. The test light pulses are provided to a light detector for measurement of the test light pulses. The time-dependent courses of the relative light intensities of the test light pulses are analyzed. The measured pulses are separated into the test light pulses and the measurement light pulses according to the different time-dependent courses of the relative light intensities. The detector includes a scintillator, a light detector, a regularly-pulsed test light source that is adapted provide test light pulses to the light detector for measurement, and an electronic measuring circuit.

Abstract: Readout circuitry for a PMT is provided, which is adapted for delivering a pair of first and second synchronous output voltage signals to a pair of outputs, the first output signal of the pair having a first AC portion being representative of a charge flow of an anode of the PMT over time, the second output signal of the pair having a second AC portion which corresponds to an inverted form of the first AC portion of the first output signal. The readout circuitry comprises a first sub-circuitry which is adapted to derive the first output signal from the charge flow over time of the anode, and a second sub-circuitry which is adapted to derive the second output signal from a charge flow over time of at least one dynode of the PMT.

Abstract: A self-stabilizing scintillation detector system for the measurement of nuclear radiation, preferably gamma radiation, is provided, the system comprising a scintillation crystal, a photo detector, a photomultiplier (PMT) with n dynodes and an evaluation system connected to the output port of the PMT, i.e. the anode of the PMT, the PMT comprising at least two connections to at least two different dynodes of the PMT, a device for measuring the electric current at the at least two dynodes, as well as an electronic device for determining the quotient of the measured at least two electric currents at the at least two dynodes, said quotient being a measure for the gain between the two dynodes, further comprising means for comparing the measured quotient with a reference value, and means for adjusting the gain of the PMT by utilizing the gain change over time.

Abstract: A method and device are provided for obtaining the energy of nuclear radiation from a scintillation detector system for the measurement of nuclear radiation the device comprising a scintillation crystal, a light readout detector and a fast digital sampling analog to digital converter. The method comprises obtaining the anode current at the LRD for at least one scintillation event with N photo electron charges at the entrance of the LRD, sampling the measured anode current, obtaining the function of the scintillation pulse charges Qdint(N, G) at the anode of the LRD from said scintillation events, obtaining the RMS of the noise power charge Qdrms(N, G), obtaining the function QdSN(N) by calculating the ratio of Qdint(N, G) and Qdrms(N, G), obtaining the constant gradient k from the function QdSN(N)=Qdint(N, G)/Qdrms(N, G)=k*N, and obtaining N.

Abstract: A method and device are provided for obtaining the energy of nuclear radiation from a scintillation detector system for the measurement of nuclear radiation the device comprising a scintillation crystal, a light readout detector and a fast digital sampling analog to digital converter. The method comprises obtaining the anode current at the LRD for at least one scintillation event with N photo electron charges at the entrance of the LRD, sampling the measured anode current, obtaining the function of the scintillation pulse charges Qdint(N, G) at the anode of the LRD from said scintillation events, obtaining the RMS of the noise power charge Qdrms(N, G), obtaining the function QdSN(N) by calculating the ratio of Qdint(N, G) and Qdrms(N, G), obtaining the constant gradient k from the function QdSN(N)=Qdint(N, G)/Qdrms(N, G)=k*N, and obtaining N.

Abstract: A method for correctly identifying at least one source, in particular at least one nuclide, enclosed in a human body and/or a container, is provided, the method comprising the following steps: detecting and measuring the at least one source by means of a gamma spectroscopic device; identifying, in a first estimation step, the at least one source by means of a standard nuclide identification procedure for evaluating a measured first spectrum of the at least one source; applying a second estimation step on the basis of the result of the first estimation step, wherein the result of the first estimation step is used for acquiring a plurality of second spectra of the at least one source found by the standard nuclide identification procedure for a plurality of absorption scenarios and for a plurality of scattering scenarios; and comparing the measured first spectrum with a scatter and absorber spectrum obtained from the plurality of second spectra generated in the second estimation step.

Abstract: A self-stabilizing scintillation detector system for the measurement of nuclear radiation, preferably gamma radiation, is provided, the system comprising a scintillation crystal, a photo detector, a photomultiplier (PMT) and one or two fast digital sampling analog to digital converters (ADC), where the scintillator is selected from a group of materials having a light decay time of at least 1 ns, and where the PMT is set to its highest possible gain.

Abstract: A self-stabilizing scintillation detector system for the measurement of nuclear radiation, preferably gamma radiation, is provided, the system comprising a scintillation crystal, a photo detector, a photomultiplier (PMT) with n dynodes and an evaluation system connected to the output port of the PMT, i.e. the anode of the PMT, the PMT comprising at least two connections to at least two different dynodes of the PMT, a device for measuring the electric current at the at least two dynodes, as well as an electronic device for determining the quotient of the measured at least two electric currents at the at least two dynodes, said quotient being a measure for the gain between the two dynodes, further comprising means for comparing the measured quotient with a reference value, and means for adjusting the gain of the PMT by utilizing the gain change over time.

Abstract: The invention relates to a detector for measuring nuclear radiation, especially gamma-radiation, comprising a scintillator crystal with a light decay time of less than 100 ns, a silicon drift detector (SDD) for the measurement of both direct hits of low energy radiation and the light, being emitted from the scintillator crystal, the silicon drift detector being mounted between the scintillation crystal and the radiation entry window, a preamplifier, connected to the SDD, electronic devices, being capable of determining the signal rise time of the measured signals and of separating the signals on the basis of said rise time, electronic devices, being capable of separately collecting the energy spectra of SDD and scintillator detection events on the basis of the different rise times.