Selection of Refractory Materials for Electric Furnaces Used for Radioactive Waste Vitrification

2019 ◽  
Vol 59 (6) ◽  
pp. 612-615
Author(s):  
V. A. Sokolov ◽  
M. D. Gasparyan ◽  
M. B. Remizov ◽  
P. V. Kozlov
Keyword(s):  
Radioactive Waste ◽  
Refractory Materials ◽  
Waste Vitrification ◽  
Selection Of

scholarly journals Selection of refractory materials for vitrification electric furnaces of radioactive waste

2018 ◽  
pp. 53-56
Author(s):  
V. A. Sokolov ◽  
M. D. Gasparyan ◽  
M. B. Remizov ◽  
P. V. Kozlov
Keyword(s):  
Radioactive Waste ◽  
Refractory Material ◽  
Chromium Content ◽  
Refractory Materials ◽  
Next Generation ◽  
Cast Refractory ◽  
High Chromium ◽  
Material Type ◽  
Lining Material ◽  
Selection Of

It was shown that fused-cast chrome-containing refractories are the most promising as the lining material of designed glass-making electric furnaces and smallsized melters of the next generation. To provide a long (up to 10 years) life of the furnace, its elements that are subject to intensive wear must be made of refractories of HPL-85 type with a high chromium content. The bakor furnace masonry of other elements can be replaced with fused-cast refractory material type HAC-26M with a low content of chromium oxide.Ill.2. Ref. 11. Tab. 5.

On the use of ion beams for the selection of radioactive waste matrices

2005 ◽  
Vol 196 (1-3) ◽  
pp. 63-68 ◽  
Author(s):  
Frédérico Garrido ◽  
Aurélie Gentils ◽  
Lionel Thomé
Keyword(s):  
Radioactive Waste ◽  
Ion Beams ◽  
Selection Of

Subliquidus Phase Relations in the Low-Alumina Section of the Na2O–Al2O3–P2O5 System and the Radioactive Waste Vitrification

2018 ◽  
Vol 44 (6) ◽  
pp. 591-600 ◽  
Author(s):  
K. V. Martynov ◽  
A. N. Nekrasov ◽  
A. R. Kotelnikov ◽  
A. A. Shiryaev ◽  
S. V. Stefanovsky
Keyword(s):  
Radioactive Waste ◽  
Phase Relations ◽  
Waste Vitrification ◽  
P2o5 System

Initial Investigation Into the Vitrification of High Molybdenum Solids in Borosilicate Glass

2009 ◽  
Vol 1193 ◽  
Author(s):  
Barbara F. Dunnett ◽  
Nick R. Gribble ◽  
Andrew D. Riley ◽  
Carl J. Steele
Keyword(s):  
Phase Separation ◽  
Borosilicate Glass ◽  
Spent Nuclear Fuel ◽  
Storage Tanks ◽  
Waste Storage ◽  
Waste Vitrification ◽  
Durability Testing ◽  
Glass Formulation ◽  
Selection Of ◽  
Scanning Electron

AbstractSellafield Ltd operates a Waste Vitrification Plant (WVP) to immobilise the arisings from the reprocessing of spent nuclear fuel. Washout of solids from the base of waste storage tanks in preparation for decommissioning is likely to produce feeds enriched in molybdenum to the WVP. Vitrification of such feeds in the borosilicate glass formulation currently used by the WVP for vitrification of reprocessing waste has been investigated to determine the maximum achievable loading of MoO3.The vitrification of molybdenum in the absence and presence of reprocessing waste was studied. A number of glasses were manufactured in the laboratory containing various waste loadings. The resultant glasses were examined both visually and under the scanning electron microscope for the presence of any phase separation. Additional aluminium was added to the glasses manufactured in the absence of reprocessing waste to improve the durability of the glass. In borosilicate glass containing 3.5 wt% Al2O3 the onset of a molybdenum phase separation was observed in glasses containing 2.6 wt% MoO3. In the presence of Magnox reprocessing waste, phase separation was observed when the product contained >3.8 wt% MoO3. Soxhlet durability testing of a selection of the glasses manufactured was carried out. The Soxhlet durability of glasses in the absence of phase separation was good.

NUMO’s Open Solicitation of Volunteer Municipalities for a Potential Disposal Site

2003 ◽  
Author(s):  
Kazumi Kitayama
Keyword(s):  
Radioactive Waste ◽  
Preliminary Investigation ◽  
Disposal Site ◽  
Nuclear Waste Management ◽  
The Public ◽  
Construction Operation ◽  
High Level ◽  
Year 2000 ◽  
Selection Of

In the year 2000, the Japanese geological disposal program for high-level radioactive waste (HLW) moved from the phase of generic research and development into the phase of implementation. Following legislation entitled the “Specified Radioactive Waste Final Disposal Act” (hereafter “the Act”), the Nuclear Waste Management Organization of Japan (NUMO) was established as the implementing organization in October 2000. The assigned activities of NUMO include repository site selection, developing relevant license applications and construction, operation and closure of the repository. To initiate the first stage, NUMO has chosen an “open solicitation” approach for finding candidate sites in the belief that the support of local communities is essential to the success of this highly public, long-term project extending over more than a century. Based on this concept, NUMO announced the start of open solication for volunteer municipalities for selection of Preliminary Investigation Areas to the public on December 19, 2002. This paper describes NUMO’s open solicitation of volunteer municipalities for a potential disposal site.

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