OECD MCCI Project: Category 4 Integral Test to Validate Severe Accident Codes and Core-Concrete Interaction Test Six (CCI-6) (Rev. 2, Final Report)

Farmer, M. T.; Kilsdonk, D. J.; Lomperski, S.; Aeschlimann, R. W.

doi:10.2172/1177565

Cited by 1 publication

(1 citation statement)

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“…Melt eruption events are most frequently observed in tests which employed high gas content concrete such as limestone or limestone common sand concrete. However, recently, CCI-6 [263] showed that even for siliceous concrete, melt eruption may occur.…”

Section: Debris Coolability Modelmentioning

confidence: 99%

U.S. Efforts in Support of Examinations at Fukushima Daiichi: 2019 Evaluations

Amway¹,

Andrews²,

Basu³

et al. 2019

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Much is still not known about the end-state of core materials in each unit that was operating on March 11, 2011 at the Fukushima Daiichi Nuclear Power Station (Daiichi). Information obtained from Daiichi is required to inform Decontamination and Decommissioning (D&D) activities, improving the ability of the Tokyo Electric Power Company Holdings, Incorporated (TEPCO Holdings) to characterize potential hazards and to ensure the safety of workers involved with cleanup activities. This document, which has been updated to include Fiscal Year 2019 (FY2019) information, summarizes results from a U.S. effort to review Daiichi information and extract insights to enhance the safety of existing and future nuclear power plant designs. This U.S. effort, which was initiated in 2014 by the Department of Energy Office of Nuclear Energy (DOE-NE), is completed by a group of experts in reactor safety and plant operations that identify examination needs and evaluate recent Daiichi examination data to address these needs. Each year, annual reports are issued that document significant safety insights being obtained in areas of special emphasis. For FY2019, the areas emphasized by the expert panel include component performance, radionuclide surveys and sampling, debris end-state location, combustible gas effects, and plant operations and maintenance. In addition to reducing uncertainties related to severe accident modeling progression, these insights have and continue to be used to update guidance for severe accident prevention, mitigation, and emergency planning. Reduced uncertainties in modeling the events at Daiichi improve the realism of reactor safety evaluations that inform future D&D activities. In addition, the process established by this U.S. effort provides an example that Japan may wish to implement in future international efforts to support D&D.

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Section: Debris Coolability Modelmentioning

confidence: 99%