Method of designing bentonite/sand mixture to achieve the target permeability
- 1. Shimizu Corp., Tokyo (Japan). Power and Energy Project Div.
- 2. Central Research Inst. of Electric Power Industry, Abiko, Chiba (Japan)
Description
Bentonite/sand mixture is expected to be an effective component of barriers for radioactive waste disposal facility. Impermeable mixture can be obtained through enrichment of the bentonite content, but it is difficult to estimate a permeability of bentonite/sand mixture before permeability test. For the design of a bentonite/sand mixture, one has to decide which sand to use, and what bentonite content to use. In this report, the authors made many kinds of bentonite/sand mixtures using different kinds of sand with different bentonite content, and permeability tests were conducted for these mixtures. After examination of the permeability tests results, the effective void ratio of bentonite/sand mixture which was obtained by compaction test, is an efficient parameter for the estimation of the permeability. Last of all, the authors propose the method of designing bentonite/sand mixture using the effective void ratio
Additional details
Publishing Information
- Publisher
- Materials Research Society.
- Imprint Place
- Pittsburgh, PA (United States)
- ISBN
- 1-55899-253-7
- Imprint Title
- Scientific basis for nuclear waste management 18. Part 1
- Imprint Pagination
- 787 p.
- Series
- Materials Research Society symposium proceedings, Volume 353.
- Journal Page Range
- p. 247-252.
Conference
- Title
- 18. international symposium on the scientific basis for nuclear waste management.
- Dates
- 23-27 Oct 1994.
- Place
- Kyoto (Japan).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28006073
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENTONITE; BULK DENSITY; CONCENTRATION RATIO; CONTAINMENT SYSTEMS; DESIGN; MATERIALS TESTING; PARTICLE SIZE; PERMEABILITY; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; SAND; UNDERGROUND DISPOSAL; VOID FRACTION
- Descriptors DEC
- CLAYS; CONTAINMENT; DENSITY; ENGINEERED SAFETY SYSTEMS; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; MANAGEMENT; MATERIALS; MINERALS; NUCLEAR FACILITIES; PHYSICAL PROPERTIES; SILICATE MINERALS; SIZE; TESTING; WASTE DISPOSAL; WASTE MANAGEMENT
Optional Information
- Secondary number(s)
- CONF-941075--.