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WIPP: Lessons in transportation safety
As part of a future consent-based approach by the federal government to site new deep geologic repositories for nuclear waste, local communities and states that are considering hosting such facilities are sure to have many questions. Currently, the Waste Isolation Pilot Plant in New Mexico is the only example of such a repository in operation, and it offers the opportunity for state and local officials to visit and judge for themselves the risks and benefits of hosting a similar facility. But its history can also provide lessons for these officials, particularly the political process leading up to the opening of WIPP, the safety of WIPP operations and transportation of waste from generator facilities to the site, and the economic impacts the project has had on the local area of Carlsbad, as well as the rest of the state of New Mexico.
Tuomo Sevón
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 171-179
Technical Paper | doi.org/10.13182/NT16-108
Articles are hosted by Taylor and Francis Online.
The water ingression mechanism can enhance the coolability of a pool of molten corium in containment during a severe accident. A water ingression model was added to the MELCOR code in 2015. The purpose of this work was to test the new model. It was found that the water ingression model performed satisfactorily in core-concrete–interaction experiments in which gas bubbles were released to the melt from decomposing concrete. The new model had little effect in the Small-Scale Water Ingression and Crust Strength (SSWICS) experiments that were done without gas bubbling through the melt. When applied to the Fukushima Daiichi Unit 1 accident, the water ingression model slowed down concrete ablation by 19% but did not quench the melt. Because the water ingression model was added to MELCOR so recently, the default treatment is still to use multipliers for the boiling heat transfer coefficient and thermal conductivity instead of the proper water ingression model. These default parameters significantly overestimated melt coolability in all the experiments that were calculated.