Eight organizations of five countries (CRIEPI, IAE, JAEA and NRA, Japan; IRSN France; PSI, Switzerland; SNL, USA; VTT, Finland) submitted results of their calculated severe accident scenarios for Unit 3 at the Fukushima Daiichi site using different severe accident codes (ASTEC, MAAP, MELCOR, SAMPSON, THALES).
The present paper for Unit 3 describes the findings of the comparison of the participants’ results against each other and against plant data, the evaluation of the accident progression and the final status inside the reactors. Special focus is on the status of the reactor pressure vessel, melt release and fission product release and transport. Unit 3 specific aspects will be highlighted and points of consensus as well as remaining uncertainties and data needs will be summarized. The results for Units 1 and 2, and an overall summary are presented in separate papers.
|Title of host publication||Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18|
|Publisher||American Nuclear Society ANS|
|Number of pages||14|
|Publication status||Published - 2019|
|MoE publication type||A4 Article in a conference publication|
|Event||18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States|
Duration: 18 Aug 2019 → 23 Aug 2019
|Conference||18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019|
|Period||18/08/19 → 23/08/19|
- Accident analysis
- Fission products
- OECD/NEA BSAF project
- Unit 3