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Two steps forward for U.K. advanced nuclear
This week, two significant announcements have emerged from the United Kingdom’s advanced reactor sector.
On June 14, Rolls-Royce, the United Kingdom National Nuclear Laboratory, and the Japan Atomic Energy Agency announced that they had signed two trilateral memorandums of cooperation to collaborate on “advanced modular reactor (AMR) technology, specifically high-temperature gas-cooled reactors (HTGR), and the coated particle fuel these reactors will use.”
Separately, on June 16, Bellevue, Wash.–based TerraPower announced that its Natrium reactor design has been formally submitted for U.K. regulatory review. The company also announced the formation of a new subsidiary, TerraPower UK Ltd.
Özlem Yilmaz, Michael Buck, Jöoerg Starflinger (Univ of Stuttgart)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 900-909
In case of a severe accident in a light water reactor, core melt can be released from the reactor pressure vessel and dislocate to the reactor cavity where it attacks the concrete structures. In order to avoid possible containment failure due to molten corium concrete interaction, the molten corium is to be retained and cooled. Core-catcher concepts considering water-injection via the bottom into the melt layer can lead to rapid quenching and solidification of the melt layer, forming a highly porous structure. The COMET-PC concept relies on porous concrete layers to distribute the water below the melt layer. This paper presents investigations on hydraulics of prototypical porous concretes that have been being used for the experimental verification of the COMET-PC core-catcher system. Pressure losses within these concretes were measured for various water flow rates to determine permeability and passability of the porous concretes. Measurement results were applied in simulations of COMET-PC experiments and reactor application with the COCOMO3D code. The simulation results show that using these concretes in large reactor cavity would not provide sufficiently homogeneous cooling of the entire corium layer unless additional water distribution systems are installed.