National Technical Reports Library

The National Technical Information Service acquires, indexes, abstracts, and archives the largest collection of U.S. government-sponsored technical reports in existence. The NTRL offers online, free and open access to these authenticated government technical reports. Technical reports and documents in its repository may be available online for free either from the issuing federal agency, the U.S. Government Publishing Office’s Federal Digital System website, or through search engines.

Details

Regulatory Aspects of Borosilicate Glass High-Level Waste Forms the Process, the Product and the Disposal.

DE2001780497

Publication Date	2001
Personal Author	Hennelly, E. J.
Page Count	7
Abstract	Immobilization of high-level radioactive waste (HLW) in borosilicate glass is acknowledges world-wide as an acceptable method for preparing HLW for geologic disposal. A waste acceptance process is underway in the United States that will provide specifications and procedures for waste producers well in advance of the availability of a federal repository. Extensive experimental data and rigorous quality assurance and control for plant operation are expected to provide convincing evidence that borosilicate glass waste forms produced in the vitrification plants meet the specifications and can be disposed of safely in a geologic repository.
Keywords	Borosilicate glass High-level radioactive wastes Waste forms Radioactive waste disposal Quality assurance Specifications Vitrification
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Department of Energy, Aiken, SC. Savannah River Site.; Department of Energy, Washington, DC.
Document Type	Conference Proceedings
NTIS Issue Number	200125
Contract Number	AC09-76SR00001

Regulatory Aspects of Borosilicate Glass High-Level Waste Forms the Process, the Product and the Disposal.

Regulatory Aspects of Borosilicate Glass High-Level Waste Forms the Process, the Product and the Disposal.
DE2001780497

Publication Date	2001
Personal Author	Hennelly, E. J.
Page Count	7
Abstract	Immobilization of high-level radioactive waste (HLW) in borosilicate glass is acknowledges world-wide as an acceptable method for preparing HLW for geologic disposal. A waste acceptance process is underway in the United States that will provide specifications and procedures for waste producers well in advance of the availability of a federal repository. Extensive experimental data and rigorous quality assurance and control for plant operation are expected to provide convincing evidence that borosilicate glass waste forms produced in the vitrification plants meet the specifications and can be disposed of safely in a geologic repository.
Keywords	Borosilicate glass High-level radioactive wastes Waste forms Radioactive waste disposal Quality assurance Specifications Vitrification
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Department of Energy, Aiken, SC. Savannah River Site.; Department of Energy, Washington, DC.
Document Type	Conference Proceedings
NTIS Issue Number	200125
Contract Number	AC09-76SR00001