Data Processing Technologies and Diagnostics for Water Chemistry and Corrosion Control in Nuclear Power Plants (DAWAC)
Report of a Coordinated Research Project 2001–2005

IAEA TECDOC No. 1505

Subject Classification: 0703-Reactor technology

English IAEA-TECDOC-1505; (ISBN:92-0-107906-0); 108 pp.; € 15.00; Date Published: 2006

Download PDF (2.93 MB)

This publication provides information on the current status and development trends in monitoring, diagnostics and control of water chemistry and corrosion of core and primary circuit materials in water cooled power reactors. It summarizes the results of an IAEA Coordinated Research Project and focuses on the methods for development, qualification and implementation of water chemistry expert systems at nuclear power plants. This publication covers contributions from leading experts in water chemistry/corrosion, representing organizations worldwide.

Download Order Form PDF
You might also like

Benchmark Analysis for Condition Monitoring Test Techniques of Aged Low Voltage Cables in Nuclear Power Plants ...

Read more

Instrumentation and Control Systems for Advanced Small Modular Reactors ...

Read more

Severe Accident Mitigation through Improvements in Filtered Containment Vent Systems and Containment Cooling Strategies ...

Read more

Preparing and Conducting Review Missions of Instrumentation and Control Systems in Nuclear Power Plants ...

Read more

Application of Field Programmable Gate Arrays in Instrumentation and Control Systems of Nuclear Power Plants ...

Read more

Technical Challenges in the Application and Licensing of Digital Instrumentation and Control Systems in Nuclear Power Pl ...

Read more

Treatment of Residual Sodium and Sodium Potassium from Fast Reactors ...

Read more

Performance Analysis Review of Thorium TRISO Coated Particles during Manufacture, Irradiation and Accident Condition Hea ...

Read more

Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the Monju Reactor Vessel ...

Read more

Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs) ...

Read more

Benchmark Analyses on the Control Rod Withdrawal Tests Performed during the PHÉNIX End-of-Life Experiments ...

Read more

Evaluation of Advanced Thermohydraulic System Codes for Design and Safety Analysis of Integral Type Reactors ...

Read more

Design Features and Operating Experience of Experimental Fast Reactors ...

Read more

Advanced Surveillance, Diagnostic and Prognostic Techniques in Monitoring Structures, Systems and Components in Nuclear ...

Read more

Challenges Related to the Use of Liquid Metal and Molten Salt Coolants in Advanced Reactors ...

Read more