Backfilling of Geological Disposal Facilities - Development of Optimized Backfill Material - 18146
Creators
- 1. DBE TECHNOLOGY GmbH, Eschenstrasse 55, D-31224 Peine (Germany)
- 2. ONDRAF/NIRAS, Avenue des Arts 14, 1210 Brussels (Belgium)
Description
In Belgium, low- and intermediate-level waste (B-waste) will be conditioned in concrete monoliths and high-level waste (C-waste) in so-called Super-containers (SCs). The Belgian radioactive waste management program has focused on the disposal of these waste types in two emplacement fields of a geological disposal facility (GDF). When the disposal waste packages (DWP) have been emplaced, backfilling of the galleries is supposed to be carried out in order to stabilize the galleries, to reduce voids, to guarantee a favourable chemical milieu with regard to the retention of the radionuclides, to minimize a possible gas pressure build-up, to dissipate radioactive decay heat and to enable good conditions for a potential retrieval of the DWP. The current reference solution is to mix the backfill at the surface and then to pump the mixture through pipeline distribution systems into the underground structures. The catalogue of backfill material requirements comprises common, but also different requirements due to the characteristics of the B and C waste packages and differences in the backfilling systems. It was found that two backfill material recipes have to be developed. Different requirements, such as high porosity (low strength and low gas threshold pressure) and high thermal conductivity have contrary consequences for the material. In addition, during backfill production quality variations of the raw materials that influence the backfill material properties can occur. Different lengths of the delivery pipeline may require adjustments of the material composition. In order to consider the practical experiences of backfill material production, one focus of the development programs was to identify compositional ranges that guarantee the respective material property. A combination of the individual 'conformity fields' results in optimal solutions for the standard operating conditions as well as a compositional range that guarantees compliance with the required material specifications. (authors)
Availability note (English)
Available from: WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- INIS-US--20-WM-18146
Conference
- Title
- 44. Annual Waste Management Conference
- Acronym
- WM2018
- Dates
- 18-22 Mar 2018
- Place
- Phoenix, AZ (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52015377
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BACKFILLING; BELGIUM; CONTAINERS; INTERMEDIATE-LEVEL RADIOACTIVE WASTES; LOW-LEVEL RADIOACTIVE WASTES; PACKAGING; POROSITY; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE PROCESSING; STABILIZATION; THERMAL CONDUCTIVITY; UNDERGROUND DISPOSAL
- Descriptors DEC
- DEVELOPED COUNTRIES; EUROPE; MANAGEMENT; MATERIALS; PHYSICAL PROPERTIES; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; THERMODYNAMIC PROPERTIES; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; WESTERN EUROPE
Optional Information
- Notes
- 9 refs.; Available online at: https://www.xcdsystem.com/wmsym/2018/index.html