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U.S. Department of Energy
Office of Scientific and Technical Information

Control of radiation-field buildup in BWRs

Technical Report ·
OSTI ID:5535512
This document provides an interim report on the progress of Project 819-2, BWR Radiation Buildup Analysis. The analysis of existing data led to the development of a hypothesis that soluble zinc in the BWR reactor water minimizes radiation buildup by inhibiting the corrosion of stainless steel. Laboratory experimentation has substantiated the inhibiting effect that zinc has on corrosion and short term Co-60 buildup experiments have also demonstrated a zinc advantage. Testing will be continued to measure the longer term effects of zinc inhibition. Investigation into the factors controlling the concentration of Co-60 in BWR reactor water will also be a major focus of the balance of this project. 8 refs., 35 figs., 7 tabs.
Research Organization:
General Electric Co., San Jose, CA (USA)
OSTI ID:
5535512
Report Number(s):
EPRI-NP-4072; ON: TI85920670
Country of Publication:
United States
Language:
English