Community Research and Development Information Service - CORDIS

Abstract

The report summarizes the results of the activities of the CONT Expert Group, a subgroup of the CEC Fast Reactor Safety Working Group (SWG). The CONT group's work has over the last 12 years (1975-87) covered a wide spectrum of problems related to the behaviour of the primary containment of a sodium-cooled fast reactor following an accident releasing a large amount of mechanical energy. In particular the CONT group followed closely the code development and validation (COVA) programme carried out at the JRC-Ispra. This activity also included an assessment of related material programmes. From a comparison of containment codes and a sensitivity analysis, it was concluded that the codes developed in the EC Member States and at the JRC-Ispra allow to treat the consequences of a hypothetical core- disruptive accident on the primary containment with adequate accuracy. Consequently the group considered its mandate fulfilled and terminated its activities.

Additional information

Authors: BALZ W CEC-BRUSSELS DUFRESNE J CEA, F , CEC-BRUSSELS;CEA, F
Bibliographic Reference: EUR 11364 EN (1988) FS, PP 40, ECU 5.00, AVAILABILITY: CEC-LUXEMBOURG, BP 1003, GDL
Availability: Can be ordered online
Record Number: 1989126070600 / Last updated on: 1989-05-01
Category: PUBLICATION
Available languages: en