Published 1989 | Version v1
Book Metadata-only

Mechanical properties of swelling clays

Creators

  • 1. Atomic Energy Commission, DRDD/SESD, CEN Fontenay-aux-Roses (France)
  • 2. Lille Univ., 59 - Valenciennes (France). Centre Universitaire

Description

The safety of vitrified radioactive waste disposal in granite is based on the concept of multiple barriers, which include an engineered clay barrier placed between the waste package and the granite. The authors discuss the mechanical properties of the swelling clays used studied with a view to practical application for storage facility dimensioning. This involved a macroscopic examination of the clays swelling capacities (for sealing of storage boreholes) and fracture criteria (mechanical stability)

Additional details

Publishing Information

Publisher
Materials Research Society.
Imprint Place
Pittsburgh, PA (USA)
ISBN
0-931837-97-9
Imprint Title
Scientific basis for nuclear waste management XII
Imprint Pagination
1001 p.
Series
Materials Research Society symposium proceedings. Volume 127.
Journal Page Range
p. 669-676.

Conference

Title
12. international symposium on the scientific basis for nuclear waste management.
Dates
10-13 Oct 1988.
Place
Berlin (Germany, F.R.).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21037510
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CLAYS; CONTAINERS; DIFFUSION BARRIERS; FRACTURE PROPERTIES; GRANITES; MECHANICAL PROPERTIES; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; VITRIFICATION
Descriptors DEC
IGNEOUS ROCKS; MANAGEMENT; MATERIALS; MINERALS; PLUTONIC ROCKS; RADIOACTIVE MATERIALS; ROCKS; SILICATE MINERALS; STORAGE; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE STORAGE; WASTES

Optional Information

Secondary number(s)
CONF-881066--.