TH33  Forensics of the Fukushima Dai-ichi Accident

There is uncertainty in our understanding of phenomena affecting boiling-water reactor (BWR) in-vessel and ex-vessel core damage progressions during severe accidents, and the end states of core materials within the three units at the Fukushima Dai-ichi Nuclear Power Station (Fukushima Dai-ichi) are still unknown. The Fukushima Dai-ichi units offer the United States and international communities a means to reduce uncertainties in severe accident progression modeling by obtaining prototypic data from multiple full-scale BWR severe accidents similar to what occurred after the accident at Three Mile Island Unit 2. In addition to reducing the modeling uncertainties, these insights are being used to update guidance for severe accident prevention, mitigation, and emergency planning. Furthermore, reduced uncertainties in modeling the events at Fukushima Dai-ichi will improve the realism of reactor safety evaluations and inform future decontamination and decommissioning. This session will provide an overview of recent forensics information from Fukushima Dai-ichi and current developments in the use of this information to reduce uncertainties in severe accident computer codes. The industry will also discuss the use of forensics insights to improve severe accident management strategies.



  • Don Marksberry, Reactor Systems Engineer, Division of Systems Analysis, , RES/NRC tel: 301-415-1543, e-mail:

Page Last Reviewed/Updated Monday, June 04, 2018