According to an embodiment, a neutron measurement apparatus has: a neutron detector; a gamma ray detector; a neutron detector signal processing unit which performs Fourier transform on the signals received for a prescribed period, generates neutron detector signal frequency data in a frequency domain, calculates the neutron-detection signal power spectrum and stores it; a gamma-ray detector signal processing unit which performs Fourier transform on the signals received for a prescribed period, generates gamma ray detector signal frequency data in a frequency domain, calculates gamma ray detector signal power spectrum and stores it; and a neutron calculation unit which generates a neutron signal by removing a part contributed by the gamma ray detector signal power spectrum from the neutron detector signal power spectrum.

A method and a system for fissile content measurement that utilizes a detector configured to detect fast neutrons. An external radiation source may be used to induce fission in a sample to allow the measurement of a fissile material of the sample with a low spontaneous fission probability. Analyzing the sample may be based on the energy spectrum of emitted neutrons. That is, the energy information regarding the energy of the fast neutrons is obtained, and the fast neutrons as having a high likelihood of originating in a nuclear fission process as opposed to originating in an (alpha,n) reaction by utilizing the obtained energy information are classified to analyze the sample. Alternatively, a position of interaction in the detector of neutron emitted by the sample is measured, and this position is retraced back through intervening material(s) between the detector and the sample to determine the spacial geometry of the sample.

According to an embodiment, a neutron measurement apparatus has: a neutron detector; a gamma ray detector; a neutron detector signal processing unit which performs Fourier transform on the signals received for a prescribed period, generates neutron detector signal frequency data in a frequency domain, calculates the neutron-detection signal power spectrum and stores it; a gamma-ray detector signal processing unit which performs Fourier transform on the signals received for a prescribed period, generates gamma ray detector signal frequency data in a frequency domain, calculates gamma ray detector signal power spectrum and stores it; and a neutron calculation unit which generates a neutron signal by removing a part contributed by the gamma ray detector signal power spectrum from the neutron detector signal power spectrum.

The present disclosure belongs to the technical field of neutron detection, and it relates to a structure for slow neutron detection and a method for energy spectrum measurement of slow neutrons, wherein the structure for slow neutron detection comprises: a shielding barrel, which is configured as square with an opening; and a detector unit, which is a slow neutron detector with position resolution function, wherein the detector unit is completely wrapped in the shielding barrel, and the detector unit is placed close to one of the sides of the shielding barrel that is perpendicular to the open side of the shielding barrel. When the structure for slow neutron detection moves at a set speed, the incident energy spectrum of slow neutrons can be inversely extrapolated on the basis of the number of slow neutrons at different depths.

The present disclosure belongs to the technical field of neutron detection, and it relates to a structure for slow neutron detection and a method for energy spectrum measurement of slow neutrons, wherein the structure for slow neutron detection comprises: a shielding barrel, which is configured as square with an opening; and a detector unit, which is a slow neutron detector with position resolution function, wherein the detector unit is completely wrapped in the shielding barrel, and the detector unit is placed close to one of the sides of the shielding barrel that is perpendicular to the open side of the shielding barrel. When the structure for slow neutron detection moves at a set speed, the incident energy spectrum of slow neutrons can be inversely extrapolated on the basis of the number of slow neutrons at different depths.

The present invention is to provide a System and methods for fast radiation signature generation and accurate mixture identification. In the past, remote detection of radioactive materials in mixtures using handheld or portal detectors was challenging due to low concentration, sensor noise, environmental, and other factors. The present invention presents an integrated system for fast mixture spectra generation and accurate radioactive material identification, using advanced signal processing algorithms. The signature generation and identification algorithms can be implemented by low-cost processors, making it feasible to achieve a low cost, accurate, and real-time radioactive material monitoring.

Methods and systems are presented for neutron spectroscopy that involves a modular neutron spectrometer that can be relatively easily customized for various measurement applications. In some embodiments, the modular neutron spectrometer may include a base and a plurality of ports, each configured for attaching a detector module. Different types and different numbers of detector modules may allow for such customization by changing total detector area, measurement collimation, and energy band sensitivity, just to name a few examples. Accordingly, features of a modular neutron spectrometer may be varied to accommodate a variety of experiments or measurement goals.