Conception of transport cask with advanced safety, aimed at transportation and storage of spent nuclear fuel of power reactors, which meets the requirements of IAEA in terms of safety and increased stability during beyond-design-basis accidents and acts o

Year
2004
Author(s)
R.I. Il’kaev - Russian Federal Nuclear Center – All-Russian Research Institute of Experimental Physics
V.Z. Matveev - Russian Federal Nuclear Center - All-Russian Research Institute of Experimental Physics, Russia
A.I. Morenko - Russian Federal Nuclear Center - All-Russian Research Institute of Experimental Physics, Russia
V.I. Shapovalov - Russian Federal Nuclear Center - All-Russian Research Institute of Experimental Physics, Russia
A.G. Semenov - Bochvar Institute of Inorganic Materials (VNIINM), Moscow
V.M. Sergeyev - Bochvar Institute of Inorganic Materials (VNIINM), Moscow
V.K. Orlov - Bochvar Institute of Inorganic Materials (VNIINM), Moscow
V.V. Shatalov - All-Russian Research Institute of Applied Chemistry
V.A. Seredenko - All-Russian Research Institute of Applied Chemistry
V.T. Gotovchikov - All-Russian Research Institute of Applied Chemistry
M. Jonathan Haire - Oak Ridge National Laboratory
C. W. Forsberg - Oak Ridge National Laboratory
File Attachment
1-6_018.pdf949.57 KB
Abstract
The report is devoted to the problem of creation of a new generation of multi-purpose universal transport cask with advanced safety, aimed at transportation and storage of spent nuclear fuel (SNF) of power reactors, which meets all requirements of IAEA in terms of safety and increased stability during beyond-design-basis accidents and acts of terrorism. Meeting all IAEA requirements in terms of safety both in normal operation conditions and accidents, as well as increased stability of transport cask (TC) with SNF under the conditions of beyond-designbasis accidents and acts of terrorism has been achieved in the design of multi-purpose universal TC due to the use of DU (depleted uranium) in it. At that, it is suggested to use DU in TC, which acts as effective gamma shield and constructional material in the form of both metallic depleted uranium and metal-ceramic mixture (cermet), based on stainless or carbon steel and DU dioxide. The metal in the cermet is chosen to optimize cask performance. The use of DU in the design of multi-purpose universal TC enables getting maximum load of the container for spent nuclear fuel when meeting IAEA requirements in terms of safety and providing increased stability of the container with SNF under conditions of beyond-design-basis accident and acts of terrorism.