Study of radiation dosage to structural components in nuclear reactors. Final report. [BWR; PWR]

This study was sponsored in order to provide the nuclear industry with an analysis of the radiation levels inside typical light water reactor pressure vessels with emphasis on those components designed to function the lifetime of the system. The report describes the calculation of the neutron and gamma ray fluxes and spectra determined by applying two dimensional radiation transport computer codes to physical models of a pressurized water reactor and a boiling water reactor. The calculated neutron and gamma ray distributions may be used to estimate the total radiation exposure to which a reactor component is exposed over a period of time for the two generic reactor systems studied. The accurate knowledge of these radiation levels can be used to estimate the safety and licensibility of the pressure vessel and in-vessel components.