Community Research and Development Information Service - CORDIS


Fuel element modelling has involved decades of research and code development for different reactor systems and very different situations such as normal operation, off-normal situations and severe accidents. Modern computer technology makes it possible to take full advantage of detailed model developments performed in the past for daily design analyses, safety analyses, conception of new experiments and investigation of an improved nuclear fuel utilisation and fuel element performance. Areas of interest are transient phenomena - especially the fission product behaviour, burnup-enhanced phenomena, PCI and fuel reliability, severe core damage and chemical aspects. The seminar presentations reflect this variety.

Additional information

Authors: LASSMANN K, JRC Karlsruhe (DE)
Bibliographic Reference: EUR 13660 EN (1991) 276 pp., FS, ECU 22.50
Availability: (2)
ISBN: ISBN 92-826-2886-8
Record Number: 199111156 / Last updated on: 1994-12-02
Original language: en
Available languages: en