Nuclear Analysis of the Circular High Buruup Element to be Tested in the OMRE

摘要

The heat generation rate of the OMRE element in position 6 or 11 was determined by the uranium content – neutron flux method. This estimate of the heat generation rate differed considerably from the flow-temperature difference estimation and a deference in the calculated sent generation rates was noticed, it was assumed that the flowmeter was met recording accurately. After a failure of the high burnup element, it a neared that the flowmeter was perhaps more accurate than originally assumed. At the moment limited analyses of the burnup in the flat plate high burnup element are being made. From these analyses the flux can be calculated and POMRE can be adjusted.