Design and full-scale testing of nuclear waste glass melter technology developed by INE for application in China
- Forschungszentrum Karlsruhe (Germany). Inst. fuer Nukleare Entsorgungstechnik
In the scope of a technology transfer project with China, a large-scale ceramic waste glass melter, designated BVPM, had been designed and constructed at the Institut fuer Nukleare Entsorgungstechnik (INE) of the Forschungszentrum Karlsruhe. Before its delivery to China, the melter was operated in INE`s V-W1 vitrification mock-up facility under Chinese participation. Within two continuous long-term test runs 45 m{sup 3} of HLLW simulate were converted to 29 tons of glass product. The simulated feed was composed according to analytic data of radioactive HLLW solutions currently stored in China. In the second test run, about 20 m{sup 3} of simulate with a content of 70 kg of noble metals were processed to demonstrate the noble metals compatibility of the melter. A description of the BVPM melter and the mock-up facility is given. The results of the test runs, especially the process behavior, the operation of the glass pouring systems, the noble metals removal efficiency, and the performance of a new glass level detection device are reported. The melter feed contained a significant concentration of sulphur, which is one of the most troublesome elements in vitrification. The sulphur incorporation data is given as well. The overall test results of the BVPM melter indicated that the technology is well applicable for use in China`s mock-up test facility at the Sichuan Nuclear Fuel Plant (SNFP). It is not only suitable for the considered waste solutions but also works convincingly when processing highly noble metals-containing melter feed (3--4 g/l).
- OSTI ID:
- 178099
- Report Number(s):
- CONF-950917--; ISBN 0-7918-1219-7
- Country of Publication:
- United States
- Language:
- English
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