Status of Fast Reactor Research and Technology Development

IAEA TECDOC No. 1691

Subject Classification: 0703-Reactor technology

English IAEA-TECDOC-1691; (ISBN:978-92-0-130610-4); 844 pp.; € 35.00; Date Published: 2013

Download PDF (31.27 MB)

Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and academics. The main issues discussed are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. The summary includes national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance of fast reactors.

Download Order Form PDF
You might also like

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

Performance Assessment of Passive Gaseous Provisions (PGAP) ...

Read more