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 of terrorism
Creators
- 1. Russian Federal Nuclear Center - All-Russian Research Inst. of Experimental Physics, Sarov (Russian Federation)
- 2. All-Russian Research Inst. of Inorganic Materials, Moscow (Russian Federation)
- 3. All-Russian Research Inst. of Applied Chemistry, Moscow (Russian Federation)
- 4. Oak Ridge National Lab., Oak Ridge (United States)
Description
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-design-basis 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
Files
37088557.pdf
Files
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Additional details
Publishing Information
- Imprint Title
- PATRAM 2004 - The 14th international symposium on the packaging and transportation of radioactive materials. Conference proceedings
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- 8 p.
- Report number
- INIS-DE--0129
Conference
- Title
- 14. international symposium on the packaging and transportation of radioactive materials
- Acronym
- PATRAM 2004
- Dates
- 20-24 Sep 2004
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 37088557
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; CAPACITY; CARBON STEELS; CERMETS; COMPLIANCE; DEPLETED URANIUM; DESIGN; GAMMA RADIATION; IAEA; REGULATIONS; SABOTAGE; SHIELDING; SPENT FUEL CASKS; SPENT FUEL STORAGE; STABILITY; STAINLESS STEELS; STANDARDS; TRANSPORT
- Descriptors DEC
- ACTINIDES; ALLOYS; CARBON ADDITIONS; CASKS; COMPOSITE MATERIALS; CONTAINERS; ELECTROMAGNETIC RADIATION; ELEMENTS; HIGH ALLOY STEELS; INTERNATIONAL ORGANIZATIONS; IONIZING RADIATIONS; IRON ALLOYS; IRON BASE ALLOYS; LAWS; MATERIALS; METALS; RADIATIONS; STEELS; STORAGE; TRANSITION ELEMENT ALLOYS; URANIUM
Optional Information
- Notes
- Paper No. 018