Behaviour of Core Materials and Fission Product Release in Accident Conditions in Lwrs (proceedings of A Technical Committee Meeting, Aix-en-provence, 16-19 March 1992)

Home / Publications / Scientific and Technical Publications /

Behaviour of Core Materials and Fission Product Release in Accident Conditions in Lwrs (proceedings of A Technical Committee Meeting, Aix-en-provence, 16-19 March 1992)

IAEA TECDOC No. 706

Subject Classification: 0802-Fuel fabrication and performance

English IAEA-TECDOC-706; 260 pp.; € 15.00; Date Published: 1993

Electronic version not available.

Rights and permissions

More Information on reusing IAEA copyright material

How to Order IAEA Publications

Ordering Locally

Please use the following links for an up-to-date list of IAEA distributors:

Distributors of IAEA Publications

Orders and requests for information may also be addressed to:

Marketing and Sales Unit
International Atomic Energy Agency
Vienna International Centre
PO Box 100, A-1400 Vienna,
Austria

Tel.: +43 1 2600 22529
+43 1 2600 22530
Fax: +43 1 2600 29302
Email: [email protected]

Download Order Form PDF

You might also like

Accident Tolerant Fuel Concepts for Light Water Reactors ...

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

Modelling of Water Cooled Fuel Including Design Basis and Severe Accidents ...

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

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

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

BN-600 MOX Core Benchmark Analysis ...

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

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

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

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

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

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

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

Spent Fuel Performance Assessment and Research ...