Community Research and Development Information Service - CORDIS

Framework programme


Previous programme


Successor programme


Programme funding

EUR 192 million

Official Journal Reference

L 3 of 1984-01-05

Legislative Reference

of 1983-12-22
To investigate ways of protecting populations and environments against the risk of the accidental release of radioactivity through collaboration among national institutions in the field of reactor safety and by developing analytical tools, simulation models and test methodologies as well as by compiling safety and accident analysis data.


Part of first Framework Programme (1984-1987) under sub-activity 5.1.: "Nuclear Fission".

The research focused on:
- Accident Prevention:
Dealing with problems related to improvement of reactor systems and instrumentation, inspection methodologies and procedures for early detection of structural defects or malfunctions;
- Accident Analysis, Control and Mitigation:
Directed towards a deeper understanding of accident-related phenomena and the development of models and computer codes simulating the successive phases of an accident.

The studies on accident prevention and accident analysis concerned thermal reactors cooled and moderated by Light Water (LWR) and also Liquid Metal Fast Breeder Reactors (LMFBR).


Eight areas:

- Reliability and Risk Evaluation:
Development and implementation of the databanks forming the European Reliability Data System (ERDS), ongoing since 1980;

- PISC (Project for Inspection of Steel Components):
A series of international comparison exercises, started in 1979, is devoted to the assessment of non-destructive examination methodologies and procedures to detect, locate and measure flaws in reactor structures; PISCs are conducted under the aegis of the OECD and the CEC;

- LWR (Light Water Reactor) Primary Circuit Components Life Prediction:
Contributed to an integral approach for reliable prediction of the end-of-life of reactor pressure components affected by ageing and damage during reactor operation;

- Study of Abnormal Behaviour of LWR Cooling Systems:
Provided experimental data on the thermohydraulic behaviour of the reactor cooling system and assessing models and codes for the analysis of loss of cooling accidents and special transients;

- Source Term:
Investigated the fission product and aerosol behaviour in LWR reactor containment, with particular reference to model development and code assessment;

- LMFBR Accident Modelling:
Included analytical and experimental activities on phenomena occurring during hypothetical severe accidents in fast breeder reactors;

- PAHR (Post Accident Heat Removal) In-Pile:
Dealt with the study of phenomena occurring during LMFBR severe accidents. In particular, the goal is to assess the long-term coolability of a particulate debris bed which could be deposited on the reactor structures when part, or all, of the case materials are melted;

- LMFBR Material Properties and Structural Behaviour:
Was devoted to the investigation of the mechanical properties of materials used for the construction of reactor components and to the improvement of the analytical tools for the prediction of structural behaviour.


The Commission, assisted by the board of governors of the Joint Research Centre (JRC), was responsible for carrying out the programme, which was executed by the JRC's Institute for Safety Technology at Ispra.

Much of the research on reactor safety was carried out in the JRC, the rest being pursued under JRC management in national laboratories as shared-cost contracts between the Commission and public or private organizations within the Member States.

The programme was reviewed during the third year, as a result of which the possibility of a further four-year programme was envisaged. Before this, however, the Commission was under an obligation to submit a critical independent analysis of JRC programmes to the Council and the European Parliament.


Nuclear Fission - Safety
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