Published 2004
| Version v1
Miscellaneous
Open
Development of new type concrete for spent fuel storage cask
- 1. Kobe Steel, Ltd., Hyogo (Japan)
- 2. Taisei Corp., Tokyo (Japan)
- 3. Transnuclear, Ltd., Tokyo (Japan)
Description
Heat resistant concrete has been developed to make it possible to design a new type cask that has been designed on the same concept of metal cask technologies for use in high temperature conditions. The allowable temperature of conventional concrete is limited to less than 100 degrees Celsius because most of its moisture is free water and therefore hydrogen, which is effective for neutron shielding, can be easily lost. Our newly developed concrete uses chemically bonded water and as a result can be used under high temperatures
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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
- 37088713
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPRESSION STRENGTH; CONCRETES; DENSITY; HEAT RESISTANT MATERIALS; MOISTURE; NEUTRONS; SHIELDING MATERIALS; SPENT FUEL CASKS; SPENT FUEL STORAGE; THERMAL CONDUCTIVITY
- Descriptors DEC
- BARYONS; BUILDING MATERIALS; CASKS; CONTAINERS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; MATERIALS; MECHANICAL PROPERTIES; NUCLEONS; PHYSICAL PROPERTIES; STORAGE; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- st Paper No. 023