Community Research and Development Information Service - CORDIS


In this report, the events, models and data currently available for analysis of accident source terms in liquid metal cooled fast neutron reactors are reviewed. The types of hypothetical accidents considered are the low probability, more extreme types of severe accident, involving significant degradation of the core, which may lead to the release of radionuclides. The base case reactor design considered is a commercial scale sodium pool reactor of the CDFR type. The feasibility of an integrated calculational approach to radionuclide transport and speciation (such as is used for LWR accident analysis) is explored. It is concluded that there is no fundamental obstacle, in terms of scientific data or understanding of the phenomena involved, to such an approach. However this must be regarded as a long-term goal because of the large amount of effort still required to advance development to a stage comparable with LWR studies. Particular aspects of LMFBR severe accident phenomenology which require attention are the behaviour of radionuclides during core disruptive accident bubble formation and evolution, and during the less rapid sequences of core melt under sodium. The basic requirement for improved thermal hydraulic modelling of core, coolant and structural materials, in these and other scenarios, is highlighted as fundamental to the accuracy and realism of source term estimations. The coupling of such modelling to that of radionuclide behaviour is seen as the key to future development in this area.

Additional information

Authors: KEIR D, UKAEA-SRD Culcheth, Safety and Reliability Directorate, Wigshaw Lane, Culceth, Warrington WA3 4NE (GB);CLOUGH P N, UKAEA-SRD Culcheth, Safety and Reliability Directorate, Wigshaw Lane, Culceth, Warrington WA3 4NE (GB)
Bibliographic Reference: EUR 12276 EN (1989)
Availability: (2)
ISBN: ISBN 92-826-0816-6
Record Number: 198911201 / Last updated on: 1994-12-01
Original language: en
Available languages: en