Hygrothermal performance of an engineered clay barrier during sustained heating
Creators
- 1. Carleton Univ., Ottawa, Ontario (Canada). Dept. of Civil and Environmental Engineering
- 2. AECL Research, Pinawa, Manitoba (Canada). Whiteshell Labs.
Description
Bentonitic clay buffers, with a potential for swelling, form an integral part of the natural (geological formation)/engineered multi-barrier concepts being proposed for the disposal of heat-generating radioactive nuclear fuel wastes. The integrity of such barriers during thermal loadings is of primary interest to the assessment of their reliability. This paper discusses the results of a series of experiments performed to assess the performance of buffer material under sustained heating. These experiments were conducted in a large-scale granite block facility. The laboratory modeling approximately simulates the local environment that can be encountered in a disposal vault in a granitic rock mass. Experiments in which the power supply to an embedded heater was held constant are described. The temperature distributions within the buffer and the granite block together with the residual moisture content distributions are documented. Also discussed is the application of a computational model of coupled heat and moisture flows. Moisture and heat transfer in the buffer under coupled gradients is described by the Philip-de Vries-type model in which the hygrothermal parameters are determined separately
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0691-X
- Imprint Title
- Proceedings of the 1993 international conference on nuclear waste management and environmental remediation. Volume 1: Low and intermediate level radioactive waste management
- Imprint Pagination
- 776 p.
- Journal Page Range
- p. 17-28.
Conference
- Title
- '93 international conference on nuclear waste management and environmental remediation.
- Dates
- 5-11 Sep 1993.
- Place
- Prague (Czech Republic).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27008978
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENTONITE; CONTAINMENT SYSTEMS; FUNCTIONAL MODELS; GRANITES; GROUND WATER; HEAT TRANSFER; HYDROLOGY; MASS TRANSFER; PERFORMANCE; RADIOACTIVE WASTE DISPOSAL; TEST FACILITIES; UNDERGROUND DISPOSAL
- Descriptors DEC
- CLAYS; CONTAINMENT; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; HYDROGEN COMPOUNDS; IGNEOUS ROCKS; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; MANAGEMENT; MATERIALS; MINERALS; OXYGEN COMPOUNDS; PLUTONIC ROCKS; ROCKS; SILICATE MINERALS; WASTE DISPOSAL; WASTE MANAGEMENT; WATER
Optional Information
- Secondary number(s)
- CONF-930906--.