Research Reactor Modernization and Refurbishment

IAEA TECDOC No. 1625

Subject Classification: 0703-Reactor technology

English IAEA-TECDOC-1625; (ISBN:978-92-0-109609-8); 224 pp.; 96 figures; € 15.00; Date Published: 2009

Download PDF (2.81 MB)

Over two thirds of the world’s operating research reactors are more than 30 years old. The long life of these reactors has raised some concern among operators, regulators and, to some extent, the general public. Within this context the IAEA launched a special project on research reactor modernization and refurbishment. The present publication is the outcome of a meeting on the topic and contains recommendations, guidelines and information on the implementation of modernization and refurbishment projects at different research reactors and a general discussion of project challenges unique to research reactors.

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