Multipurpose neutron terminal
A multi-purpose, neutron technology, applied in the field of radiation protection, to achieve the effect of energy measurement performance evaluation and position-resolved evaluation, and various functions
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example 1
[0034] The arrangement scheme for generating beams that can be used for detector position resolution is as follows figure 2 , 3 and 4, the neutron source can be an Am-Be source. The source activity is 100mCi. There is a polyethylene disc with a diameter of about 25-30cm and a thickness of 40cm above it. The source is usually placed In a shielded well with a depth of about 1.31m and a platform with a certain depth relative to the ground, the equivalent dose rate close to the shielding material is about 0.9-1.0uSv / h. The slow down collimation system is a 90*90*70cm overall 3 The rectangular parallelepiped, which is partially hollowed out, includes the upper source and the collimation hole in the horizontal direction. The dimensions of each part are considered as follows: (1) Considering that the size of the source is a few centimeters, and the diameter of the polyethylene disc is about 25-30cm, choose L1=30cm, L2=10cm; (2) In order to support the polyethylene circle Disc, L3 is ...
example 2
[0037] The arrangement scheme for generating beams that can be used for the energy response of the detector is basically the same as in Example 1. The difference is that the diaphragm is replaced with a different moderating shield. The neutron beam passes through different moderators to get collimated beams of different energy intervals. By recording the number of times the detector responds to neutrons at different energies , The energy response curve of the detector can be obtained.
example 3
[0039] The layout scheme used to calibrate the neutron dose rate meter is as follows figure 1 , As shown in 2. First, transport the slow-down collimation system that is not needed in the calibration to a far enough position through orbit 1 to reduce the influence of scattering. Then the source is hoisted to a suitable height by controlling the elevator, and the inspected instrument can be transported to different distances from the source through the detection track 2 for measurement, and the total dose rate at different distances can be obtained. This dose rate includes the scattering neutron contribution. In order to eliminate the influence of the scattered beam, a shadow cone with proper geometry and position is placed between the source and the inspected instrument. Under this condition, the measured dose rate contributed by the scattered beam is obtained by subtracting the dose rate to obtain the main beam at different distances. The dose rate of the beam completes the c...
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