Safety Concept and Safety Assessment for a HLW Repository in Bedded Salt in Germany - 18253
- Gesellschaft fuer Anlagen- und Reaktorsicherheit - GRS gGmbH, Theodor-Heuss-Str. 4, D-38122 Braunschweig (Germany)
The German site selection act for a repository for vitrified HLW and SNF demands the consideration of various host rock formations for deep geological disposal. One of the eligible and presently investigated host rock formations is bedded rock salt. Within the framework of the national R and D project KOSINA the scientific bases for the design and safety assessment of a repository for HLW and SNF in bedded salt formations were provided. The research findings presented in this paper include the formulation of a safety concept and safety demonstration concept as well as exemplary radiological consequences analysis for a generic repository in bedded rock salt formations. The safety concept describes in a verbal, argument-based way how the natural conditions, processes and technical measures at large yield a status of safety. Fundamental principle of the safety concept is the concentration and containment of the radioactive and other pollutants in the waste in the containment providing rock zone (CRZ), which ensures isolation from the biosphere. Based on the principle of safe containment inside the CRZ guiding principles, design objectives and strategic measures are derived. The safety demonstration concept describes the means, such as analyses and arguments, which are used in the safety case to demonstrate the safety of a repository system in bedded salt on the basis of the safety concept and its guiding principles and design objectives. The decisive elements are: the demonstration of integrity of the geological barrier, the demonstration of integrity of the geotechnical barriers, the scenario analysis, and the evaluation of the identified scenarios. These elements are complemented in the safety demonstration by concepts on how to consider criticality, non-radiological protection goals and operational safety. The radiological consequences analysis primarily consists of the calculation of the radiological safety indicator for different test cases and scenarios for the various repository design and waste emplacement options. Within the KOSINA project the disposal concepts of drift disposal, horizontal and vertical borehole disposals were investigated in detail by means of computational flow and transport modelling of the repository mine (near field) and assessment of the radiological consequences (biosphere model). The applied software package RepoTREND is introduced; the modelling concept and employed radiological indicators are explained. Examples of the modelling results for the reference cases of the drift disposal repository concept for bedded salt will be given, demonstrating the capabilities of the model and the applicability to close-to-reality repository systems for deep geological disposal. (authors)
- Research Organization:
- WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)
- OSTI ID:
- 22975411
- Report Number(s):
- INIS-US--20-WM-18253
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BIOSPHERE
BOREHOLES
COMPUTERIZED SIMULATION
CONTAINMENT
DESIGN
ECOLOGICAL CONCENTRATION
FEDERAL REPUBLIC OF GERMANY
RADIATION PROTECTION
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE STORAGE
RISK ASSESSMENT
SAFETY
SALT DEPOSITS
SITE SELECTION
VITRIFICATION
WASTE TRANSPORTATION