Design and Commissioning of a Continuous Transferred ARC Plasma Melter for the Vitrification of Nuclear Waste

1987 ◽  
Vol 98 ◽  
Author(s):  
R. J. Munz ◽  
G. Q. Chen
Keyword(s):  
Nuclear Waste ◽  
Operating Temperature ◽  
Glass Ceramics ◽  
Underground Storage ◽  
Residence Times ◽  
Arc Plasma ◽  
Liquid Holdup ◽  
Transferred Arc ◽  
High Level Nuclear Waste ◽  
High Level

ABSTRACTA 40-kW transferred arc plasma melter has been designed and constructed to test the potential of this type of system for the vitrification of high level nuclear waste. Present technology relies on joule or induction heaters which are limited in operating temperature and are characterized by large liquid holdup and long residence times. The use of a plasma melter will allow the production of higher melting glasses and glass ceramics which are more durable and leach resistant in underground storage. The use of a plasma greatly decreases residence times in the heater and may even reduce the loss of volatiles by control of the melting atmosphere and continuous removal of the product as a solid ingot. Standard borosilicate glass has been melted with continuous withdrawal of product in a series of commissioning runs.

Advanced Ceramics and Glass-Ceramics for Immobilisation of ILW and HLW

2012 ◽  
Vol 1475 ◽  
Author(s):  
E. R. Vance ◽  
M. W. A. Stewart ◽  
S. Moricca
Keyword(s):  
Nuclear Waste ◽  
Hot Isostatic Pressing ◽  
Glass Ceramics ◽  
Steady Increase ◽  
Waste Forms ◽  
Regulatory Guidelines ◽  
Small Footprint ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Interim Storage

ABSTRACTSince the 1970s there has been a steady increase in research on candidate ceramic and glass-ceramics for immobilisation of HLW and ILW, both from the aspects of crystal-chemical design and processing technology. The variety of ceramics and glass-ceramics designed for different types of HLW and ILW will be presented, notably those which are problematic for vitrification. Several of these materials are optimally processed by hot isostatic pressing (HIP), a technology which can consolidate calcined intermediate-level and high-level nuclear waste. Thus we are targeting such wastes for development of alternative waste forms. The essential process steps during the HIP cycle will be outlined. Effective consolidation of a wide variety of tailored glass-ceramic and ceramic waste forms has been demonstrated. The principal advantages of the HIP technology include negligible offgas during the high temperature consolidation step, relatively small footprint, and high waste/volume loadings. While it can be argued that the “nuclear waste problem” is essentially solved technically, at least with current regulatory guidelines, different perceptions of the “best” waste form and processing method for a given waste, together with the general current lack of agreed locations for final repositories, or even interim storage sites, create uncertainties.

Synthesis of pyrochlore-borosilicate glass-ceramics for immobilization of high-level nuclear waste

2020 ◽  
Vol 46 (5) ◽  
pp. 6085-6094 ◽  
Author(s):  
Kangming Wu ◽  
Fu Wang ◽  
Qilong Liao ◽  
Hanzhen Zhu ◽  
Dongsheng Liu ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
Borosilicate Glass ◽  
Glass Ceramics ◽  
High Level Nuclear Waste ◽  
High Level

Transmutation of high-level nuclear waste by means of accelerator driven system

2013 ◽  
Vol 3 (1) ◽  
pp. 60-69 ◽  
Author(s):  
Hamid Aït Abderrahim ◽  
Didier De Bruyn ◽  
Gert Van den Eynde ◽  
Sidney Michiels
Keyword(s):  
Nuclear Waste ◽  
Driven System ◽  
High Level Nuclear Waste ◽  
Accelerator Driven System ◽  
High Level

Effect of Al and Fe sources on conversion of high-level nuclear waste feed to glass

2021 ◽  
pp. 153423
Author(s):  
José Marcial ◽  
Jaroslav Kloužek ◽  
Miroslava Vernerová ◽  
Pavel Ferkl ◽  
SeungMin Lee ◽  
...  
Keyword(s):  
Nuclear Waste ◽  
High Level Nuclear Waste ◽  
High Level
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