AN APPARATUS FOR NEUTRON COUNTING WITH REDUCING THE GAMMA-RAY EFFECTS IN SPENT FUEL MEASUREMENT

摘要

PURPOSE: An apparatus for counting neutrons for measuring spent fuel is provided to efficiently measure fissile materials using pure water as a neutron moderator. CONSTITUTION: A body(100) has a cylindrical shape. A sample holder(200) is arranged inside the body to receive spent nuclear fuel samples. A neutron counter holder(300) is arranged between the sample holder and the body and receives the neutron counter for counting the neutrons emitted from the spent nuclear fuel. Pure water(400) is filled in the body and is used as the neutron moderator for reducing the number of neutrons from the spent nuclear fuel. A cover(500) is arranged on the body to shield the neutrons from the spent nuclear fuel.