Management of high-level radioactive wastes by vitrifying (in Japanese)
With the rapid advance of atomic energy utilization recovery and storage of radioactive wastes, instead of dilution and release thus far, is essential necessity. In fuel reprocessing plants, amount of high-level radioactive liquid wastes produced is very considerable. To cope with the problem, process of vitrifying is most suitable, because of little escape of contained radionuclides and good properties of heat conduction and radiation resistance. Reviewing first the world situation in this field and types of glass to be used, the vitrifying process currently available is described: namely spray and calcination, phosphate process, pot vitrification in the U. K., the U. S. and France, and and rotary-furnace calcination method. (JA)
- Research Organization:
- Power Reactor and Nuclear Fuel Development Corp., Tokai, Japan
- NSA Number:
- NSA-29-029185
- OSTI ID:
- 4300629
- Journal Information:
- Genshiryoku Kogyo, v. 19, no. 6, pp. 38-44, Journal Name: Genshiryoku Kogyo, v. 19, no. 6, pp. 38-44; ISSN GKOGA
- Country of Publication:
- Japan
- Language:
- Japanese
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CALCINATION
GLASS
LIQUID WASTES
N40430* --Chemistry--Radiochemistry & Nuclear Chemistry-- Radioactive Waste Treatment
N52200 --Nuclear Materials & Waste Management--Disposal & Storage
RADIOACTIVE WASTES
SOLIDIFICATION
WASTE MANAGEMENT
WASTE STORAGE