Corrosion product transport in water‐cooled. nuclear reactors Part I: Pressurized water operation
Author:
- 1 February 1977
- journal article
- research article
- Published by Wiley in The Canadian Journal of Chemical Engineering
- Vol. 55 (1) , 54-61
Abstract
Corrosion of out‐core piping in the primary circuit of nuclear power reactors adds both dissolved and particulate metals and their oxides to the water coolant. The particles deposit on the fuel sheaths and pressure tubes in the reactor core and are irradiated there while they dissolve in the heated water. Transport of now‐radioactive solute around the circuit makes the out‐core surfaces radioactive, which increases radiation exposure to operators and maintainers.A mathematical model has been developed to describe these processes of deposition, irradiation and release of corrosion products on the fuel bundles and pressure tubes of CANDU pressurized water reactors. The model's predictions compare well with data from in‐reactor loop fuel, and data from fuel and pressure tubes from Pickering Generating Station. The model suggests ways to control the growth of out‐core radiation fields and keep them at the current low levels of Pickering. Hot filtration of the reactor water and an increase in water pH are two solutions analyzed with the model.Keywords
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