1988OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)Requires access

Operating experience in a radioactive liquid-fed ceramic melter vitrification facility

L.K. Holton, R.D. Dierks, R.W. Goles, Y.B. Katayama, J.E. Surma, Noël Thomas

Open publisher page 1 citations

Abstract

Between October 1984 and March 1987 the Pacific Northwest Laboratory (PNL) operated a pilot-scale radioactive liquid-fed ceramic melter (RLFCM) to convert radioactive solutions to a solid vitrified form (borosilicate glass). The facility was operated to test vitrification equipment components in a radioactive environment and to develop design and operating data that can be applied to US Department of Enrgy (DOE) production-scale operations. The radioactive testing scope of the RLFCM has concentrated on testing vitrification flowsheets that simulate waste stored at West Valley, New York, and on preparing radioactive canisters for a special repository test in the Federal Republic of Germany. During radioactive testing in the RLFCM 38 canisters of glass wre produced. This paper summarizes equipment and process experience obtained from the operations of equipment systems for waste feeding, waste vitrification, canister filling, canister handling, and vitrification off-gas treatment. 2 refs., 6 fgis., 2 tabs.

About this research paper

What this paper is about

Between October 1984 and March 1987 the Pacific Northwest Laboratory (PNL) operated a pilot-scale radioactive liquid-fed ceramic melter (RLFCM) to convert radioactive solutions to a solid vitrified form (borosilicate glass). The facility was operated to test vitrification equipment components in a radioactive environment and to develop design and operating data that can be applied to US Department of Enrgy (DOE) production-scale operations. The radioactive testing scope of the RLFCM has concentrated on testing vitrification flowsheets that simulate waste stored at West Valley, New York, and on preparing radioactive canisters for a special repository test in the Federal Republic of Germany. During radioactive testing in the RLFCM 38 canisters of glass wre produced. This paper summarizes equipment and process experience obtained from the operations of equipment systems for waste feeding, waste vitrification, canister filling, canister handling, and vitrification off-gas treatment. 2 refs., 6 fgis., 2 tabs.

Why it matters

OpenAlex reports 1 citations for this work. Citation counts describe recorded attention and do not establish research quality.

Key contribution

A contribution statement is not available in the OpenAlex record.

Method / approach

Method details are not available in the OpenAlex metadata.

Main findings

Findings are not separately available in the OpenAlex metadata.

Limitations

Limitations are not available in the OpenAlex metadata.

Applications

Application details are not available in the OpenAlex metadata.

Available abstract

Between October 1984 and March 1987 the Pacific Northwest Laboratory (PNL) operated a pilot-scale radioactive liquid-fed ceramic melter (RLFCM) to convert radioactive solutions to a solid vitrified form (borosilicate glass). The facility was operated to test vitrification equipment components in a radioactive environment and to develop design and operating data that can be applied to US Department of Enrgy (DOE) production-scale operations. The radioactive testing scope of the RLFCM has concentrated on testing vitrification flowsheets that simulate waste stored at West Valley, New York, and on preparing radioactive canisters for a special repository test in the Federal Republic of Germany. During radioactive testing in the RLFCM 38 canisters of glass wre produced. This paper summarizes equipment and process experience obtained from the operations of equipment systems for waste feeding, waste vitrification, canister filling, canister handling, and vitrification off-gas treatment. 2 refs., 6 fgis., 2 tabs.

Key concepts: Vitrification, Radioactive waste, Borosilicate glass, Waste management, Savannah River Site, High-level waste, Environmental science, Engineering

Related papers

Back to paper searchBrowse research topicsOriginal source
Operating experience in a radioactive liquid-fed ceramic melter vitrification facility — Research Paper | ScholarLens