Community Research and Development Information Service - CORDIS


Over the past decade several large-scale, in-pile experiments have been performed in the USA, in order to obtain detailed information on the release of radionuclides from light water reactor fuel, when it overheats in a severe accident situation. The main experiments have been the FP series in the LOFT facility in Idaho, the SFD (Severe Fuel Damage) series in the Power Burst Facility in Idaho, the STEP tests in the TREAT reactor at Argonne and the ACRR (Annular Core Research Reactor) ST series at Sandia. Although much useful information on release rates has emerged from these tests, they have been less successful in answering questions on the chemical and physical forms of fission products, the nature of aerosol-vapour interactions and the effectiveness of the voided Reactor Coolant System pipework as a trap for emerging aerosols and reactive vapours. This report provides a detailed reassessment of the information on radionuclide release, transport and chemistry which has resulted from these tests.

Additional information

Authors: HARMAN N F, AEA Technology, SRD Culcheth (GB);CLOUGH P N, AEA Technology, SRD Culcheth (GB)
Bibliographic Reference: EUR 14230 EN (1992) 114 pp., FS, ECU 12
Availability: (2)
ISBN: ISBN 92-826-4166-X
Record Number: 199210770 / Last updated on: 1994-12-02
Original language: en
Available languages: en