干旱区生态环境知识资源中心(Arid): Granite disposal of U.S. high-level radioactive waste.

Arid

DOI	10.2172/1029794
报告编号	SAND2011-6203
来源ID	OSTI_ID: 1029794
	Granite disposal of U.S. high-level radioactive waste.
	Freeze, Geoffrey A.; Mariner, Paul E.; Lee, Joon H.; Hardin, Ernest L.; Goldstein, Barry; Hansen, Francis D.; Price, Ronald H.; Lord, Anna Snider
英文摘要	This report evaluates the feasibility of disposing U.S. high-level radioactive waste in granite several hundred meters below the surface of the earth. The U.S. has many granite formations with positive attributes for permanent disposal. Similar crystalline formations have been extensively studied by international programs, two of which, in Sweden and Finland, are the host rocks of submitted or imminent repository license applications. This report is enabled by the advanced work of the international community to establish functional and operational requirements for disposal of a range of waste forms in granite media. In this report we develop scoping performance analyses, based on the applicable features, events, and processes (FEPs) identified by international investigators, to support generic conclusions regarding post-closure safety. Unlike the safety analyses for disposal in salt, shale/clay, or deep boreholes, the safety analysis for a mined granite repository depends largely on waste package preservation. In crystalline rock, waste packages are preserved by the high mechanical stability of the excavations, the diffusive barrier of the buffer, and favorable chemical conditions. The buffer is preserved by low groundwater fluxes, favorable chemical conditions, backfill, and the rigid confines of the host rock. An added advantage of a mined granite repository is that waste packages would be fairly easy to retrieve, should retrievability be an important objective. The results of the safety analyses performed in this study are consistent with the results of comprehensive safety assessments performed for sites in Sweden, Finland, and Canada. They indicate that a granite repository would satisfy established safety criteria and suggest that a small number of FEPs would largely control the release and transport of radionuclides. In the event the U.S. decides to pursue a potential repository in granite, a detailed evaluation of these FEPs would be needed to inform site selection and safety assessment.
出版年	2011
报告类型	Technical Report
语种	英语
国家	美国
来源学科分类	12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES ; BOREHOLES ; BUFFERS ; GRANITES ; HIGH-LEVEL RADIOACTIVE WASTES ; IGNEOUS ROCKS ; LICENSE APPLICATIONS ; METAMORPHIC ROCKS ; PRESERVATION ; RADIOACTIVE WASTE DISPOSAL ; RADIOISOTOPES ; SAFETY ; SAFETY ANALYSIS ; SITE SELECTION ; STABILITY ; TRANSPORT ; UNDERGROUND DISPOSAL ; WASTE FORMS
URL	http://www.osti.gov/scitech/servlets/purl/1029794
资源类型	科技报告
条目标识符	http://119.78.100.177/qdio/handle/2XILL650/270291
推荐引用方式 GB/T 7714	Freeze, Geoffrey A.,Mariner, Paul E.,Lee, Joon H.,et al. Granite disposal of U.S. high-level radioactive waste.,2011.