Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents
Proceedings of a Technical Meeting Held in Chengdu, China, 28 October–1 November 2013

IAEA TECDOC (CD-ROM) No. 1775

Subject Classification: 0802-Fuel fabrication and performance

English IAEA-TECDOC-CD-1775; (ISBN:978-92-0-158615-5); 381 pp.; 231 figures; € 18.00; Date Published: 2015

Download PDF (6.55 MB)

Nuclear fuel performance and management play an essential role in ensuring safety, competitiveness and public acceptance of nuclear power. Reliability of fuel depends on its proper design, manufacturing, and ability to withstand required normal operational conditions, as well as possible accidents. In-reactor loads on the core materials are extremely high, which defines a need for detailed R&D as a basis for prediction of in-pile fuel behaviour. The Fukushima Daiichi accident has demonstrated the need for adequate analysis of all aspects of fuel performance to prevent a failure, and also to mitigate consequences if an accident occurs. In order to satisfy these demands, new national and international programmes have been launched and advanced modelling codes have been developed. The experience and lessons learned during three sessions of an IAEA technical meeting on modelling of water cooled fuel, including design basis and severe accidents are presented in this publication.

Fuel Fabrication and Performance, Nuclear Accidents, Modelling of Fuel Behaviour, Nuclear Reactors, Fuel Cycles, Nuclear Fuels, Water Cooled Reactors, Steady State, Transient Conditions, Nuclear Safety, Safety Analysis, Fukushima Daiichi

Download Order Form PDF
You might also like

Accident Tolerant Fuel Concepts for Light Water Reactors ...

Read more

Evaluation of Conditions for Hydrogen Induced Degradation of Zirconium Alloys during Fuel Operation and Storage ...

Read more

Quality and Reliability Aspects in Nuclear Power Reactor Fuel Engineering ...

Read more

Pressurized Heavy Water Reactor Fuel: Integrity, Performance and Advanced Concepts ...

Read more

In-pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials ...

Read more

BN-600 MOX Core Benchmark Analysis ...

Read more

Improvement of Computer Codes Used for Fuel Behaviour Simulation (FUMEX-III) ...

Read more

Fuel Behaviour and Modelling under Severe Transient and Loss of Coolant Accident (LOCA) Conditions ...

Read more

Design, Manufacturing and Irradiation Behaviour of Fast Reactor Fuel ...

Read more

Advances in High Temperature Gas Cooled Reactor Fuel Technology ...

Read more

Structural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies-Operational Behaviour ...

Read more

Experiences and Trends of Manufacturing Technology of Advanced Nuclear Fuels ...

Read more

Fuel Modelling at Extended Burnup (FUMEX-II) ...

Read more

Spent Fuel Performance Assessment and Research ...

Read more

Role of Thorium to Supplement Fuel Cycles of Future Nuclear Energy Systems ...

Read more