Shift and adjusted reference temperature for a boiling water reactor vessel

Measurements of gamma emission rates from Fe and Cu dosimeters extracted fr om a boiling water reactor-type reactor vessel rr ere carried out to determ ine their total activity. The dosimeter's activity is related to the neutro n flux at that location by taking into account the reactor material's embri ttlement caused by neutron bombardment. The dosimeters were taken out after the first reactor operation cycle. From gamma radioactivity measurements o f these dosimeters, neutron flux and fluence were calculated. These paramet ers are used in the determination of the shift and adjusted reference tempe rature values needed for the development of pressure-temperature curves use d during reactor operation.