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Title: Electrochemistry of Water-Cooled Nuclear Reactors

Abstract

This project developed a comprehensive mathematical and simulation model for calculating thermal hydraulic, electrochemical, and corrosion parameters, viz. temperature, fluid flow velocity, pH, corrosion potential, hydrogen injection, oxygen contamination, stress corrosion cracking, crack growth rate, and other important quantities in the coolant circuits of water-cooled nuclear power plants, including both Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs). The model is being used to assess the three major operational problems in Pressurized Water Reactors (PWR), which include mass transport, activity transport, and the axial offset anomaly, and provide a powerful tool for predicting the accumulation of SCC damage in BWR primary coolant circuits as a function of operating history. Another achievement of the project is the development of a simulation tool to serve both as a training tool for plant operators and as an engineering test-bed to evaluate new equipment and operating strategies (normal operation, cold shut down and others). The development and implementation of the model allows us to estimate the activity transport or "radiation fields" around the primary loop and the vessel, as a function of the operating parameters and the water chemistry.

Authors:
; ;
Publication Date:
Research Org.:
The Pennsylvania State University
Sponsoring Org.:
USDOE - Office of Nuclear Energy, Science and Technology (NE)
OSTI Identifier:
890516
Report Number(s):
Final Report
TRN: US0703160
DOE Contract Number:  
FG07-02ID14334
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; CORROSION; CRACK PROPAGATION; ELECTROCHEMISTRY; FLUID FLOW; HYDROGEN; IMPLEMENTATION; NUCLEAR POWER PLANTS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RADIOACTIVITY TRANSPORT; REACTORS; STRESS CORROSION; THERMAL HYDRAULICS; WATER; WATER CHEMISTRY; materials science; corrosion; water-cooled nuclear reactions; electrochemistry; radiolysis

Citation Formats

Macdonald, Dgiby, Urquidi-Macdonald, Mirna, and Pitt, Jonathan. Electrochemistry of Water-Cooled Nuclear Reactors. United States: N. p., 2006. Web. doi:10.2172/890516.
Macdonald, Dgiby, Urquidi-Macdonald, Mirna, & Pitt, Jonathan. Electrochemistry of Water-Cooled Nuclear Reactors. United States. doi:10.2172/890516.
Macdonald, Dgiby, Urquidi-Macdonald, Mirna, and Pitt, Jonathan. Tue . "Electrochemistry of Water-Cooled Nuclear Reactors". United States. doi:10.2172/890516. https://www.osti.gov/servlets/purl/890516.
@article{osti_890516,
title = {Electrochemistry of Water-Cooled Nuclear Reactors},
author = {Macdonald, Dgiby and Urquidi-Macdonald, Mirna and Pitt, Jonathan},
abstractNote = {This project developed a comprehensive mathematical and simulation model for calculating thermal hydraulic, electrochemical, and corrosion parameters, viz. temperature, fluid flow velocity, pH, corrosion potential, hydrogen injection, oxygen contamination, stress corrosion cracking, crack growth rate, and other important quantities in the coolant circuits of water-cooled nuclear power plants, including both Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs). The model is being used to assess the three major operational problems in Pressurized Water Reactors (PWR), which include mass transport, activity transport, and the axial offset anomaly, and provide a powerful tool for predicting the accumulation of SCC damage in BWR primary coolant circuits as a function of operating history. Another achievement of the project is the development of a simulation tool to serve both as a training tool for plant operators and as an engineering test-bed to evaluate new equipment and operating strategies (normal operation, cold shut down and others). The development and implementation of the model allows us to estimate the activity transport or "radiation fields" around the primary loop and the vessel, as a function of the operating parameters and the water chemistry.},
doi = {10.2172/890516},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Aug 08 00:00:00 EDT 2006},
month = {Tue Aug 08 00:00:00 EDT 2006}
}

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