Abstract: A neutron detector having high sensitivity of detection for low energy neutrons is provided. The neutron detector 10 includes a detecting element including a Si semiconductor layer 2, a first electrode 1 formed on one main surface of the Si semiconductor layer 2 and a second electrode 4 formed on the other main surface of the Si semiconductor layer 2, in which the Si semiconductor layer 2 includes a P-type impurity region 2a in contact with the second electrode 4 and an N-type impurity region 2b in contact with the first electrode 1; and a radiator 8 arranged to face the first electrode 1. In addition, a personal dosemeter and a neutron fluence monitor including the same are provided.

Abstract: A neutron detector having high sensitivity of detection for low energy neutrons is provided. The neutron detector 10 includes a detecting element including a Si semiconductor layer 2, a first electrode 1 formed on one main surface of the Si semiconductor layer 2 and a second electrode 4 formed on the other main surface of the Si semiconductor layer 2, in which the Si semiconductor layer 2 includes a P-type impurity region 2a in contact with the second electrode 4 and an N-type impurity region 2b in contact with the first electrode 1; and a radiator 8 arranged to face the first electrode 1. In addition, a personal dosemeter and a neutron fluence monitor including the same are provided.

Abstract: In a neutron dosimeter, G(L) function data, which causes the tendency of a characteristic when neutron energy is plotted along the horizontal axis and the ambient dose equivalent (1 cm dose equivalent) is plotted along the vertical axis to approximate a neutron fluence-ambient dose equivalent (1 cm dose equivalent) conversion coefficient curve (neutron energy-ICRP 74 H* (10) response curve), is used to compensate the output of a mixed gas detector which encapsulates a gas mixture of a nitrogen gas and an organic compound gas and outputs detection pulse signals with peaks according to the energies of detected neutrons.