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손희동,김종경 한국원자력학회 2011 Nuclear Engineering and Technology Vol.43 No.1
The neutron multiplication factor in spent fuel storage racks, in which a stainless steel plate encloses a fuel assembly,was evaluated according to the variation of distance between the fuel assembly and stainless steel plate, as well as the pitch.The stainless steel plate position with the lowest multiplication factor on each pitch consistently appeared as 6mm or 9mmaway from the outmost surface of the fuel assembly. Because the stainless steel plate has a thermal neutron absorption crosssection, its ability to absorb neutrons can work best only if it is installed at the position where thermal neutrons can begathered most easily. Therefore, the stainless steel plate position should not be too close or too far away from the fuelassembly, but it should be kept a pertinent distance from the fuel assembly.
손희동,김종경 대한방사선방어학회 2011 방사선방어학회지 Vol.36 No.4
With the reactor operation conditions ‐ 4.3 wt% ^(235)U initial enrichment, burn‐up 55,000 MWd/MTU, average power 34 MW/MTU for three periods burned time for 539.2 days per period and cooling time for 100 hours after shut down, to set up the condition to determine the minimum height (depth) of spent fuel storage pool to shut off the radiation out of the spent fuel storage pool and to store spent fuels safely, the dose rate on the specific position directed to the surface of spent fuel storage pool induced by the neutron and gamma‐ray from spent fuels are evaluated. The length of spent fuel is 381 cm, and as the result of evaluation on each position from the top of spent fuel to the surface of spent fuel storage pool, it is difficult for neutrons from spent fuels to pass through the water layer of maximum 219 cm (600 cm from the floor of spent fuel storage pool) and 419 cm (800 cm from the floor of spent fuel storage pool) for gamma‐ray. Therefore, neutron and gamma‐ray from spent fuels can pass through below 419 cm (800 cm from the floor) water layer directed to the surface of spent fuel storage pool.