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Vitrification of reactor wastes

Abstract

The vitrification of low and intermediate level wastes from the NPP operation has been studied in the frame of a Franco-Czech agreement. The laboratory experiments concentrated on a search for a suitable borosilicate glass matrix which could incorporate relatively high quantities of boron and sodium, main components of liquid wastes from the WWER reactor type NPPs. A relatively wide area of waste compositions has been studied and properties of glasses suitable for the technology and waste disposal were measured. Great attention has been paid to the chemical stability (leachability), other properties like thermal dependence of viscosity and electrical conductivity of melts, and the microstructure of the final solidification product have also been evaluated. The feasibility of the vitrification process has been proved during pilot plant tests which were accomplished at the French establishment in Marcoule. The results of tests were promising. (authors). 4 tabs., 7 figs.
Authors:
Jouan, A; [1]  Sussmilch, J [2] 
  1. CEA Centre d`Etudes de la Vallee du Rhone, 30 - Marcoule (France). Dept. des Procedes de Retraitement
  2. Nuclear Research Institut, Rez (Czech Republic)
Publication Date:
Dec 31, 1993
Product Type:
Conference
Report Number:
CEA-CONF-12007; CONF-930906-
Reference Number:
SCA: 052001; 210200; PA: AIX-26:055014; EDB-95:101696; ERA-20:020770; NTS-96:004150; SN: 95001425655
Resource Relation:
Conference: `93 international conference on nuclear waste management and environmental remediation, Prague (Czech Republic), 5-11 Sep 1993; Other Information: PBD: 1993
Subject:
05 NUCLEAR FUELS; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; RADIOACTIVE WASTE PROCESSING; VITRIFICATION; BORON; BOROSILICATE GLASS; CEA MARCOULE; CLINOPTILOLITE; INTERMEDIATE-LEVEL RADIOACTIVE WASTES; LIQUID WASTES; SODIUM; TEMELIN-1 REACTOR
OSTI ID:
77543
Research Organizations:
CEA Centre d`Etudes de la Vallee du Rhone, 30 - Marcoule (France). Dept. des Procedes de Retraitement
Country of Origin:
France
Language:
English
Other Identifying Numbers:
Other: ON: DE95632473; TRN: FR9502135055014
Availability:
INIS; OSTI as DE95632473
Submitting Site:
FRN
Size:
5 p.
Announcement Date:

Citation Formats

Jouan, A, and Sussmilch, J. Vitrification of reactor wastes. France: N. p., 1993. Web.
Jouan, A, & Sussmilch, J. Vitrification of reactor wastes. France.
Jouan, A, and Sussmilch, J. 1993. "Vitrification of reactor wastes." France.
@misc{etde_77543,
title = {Vitrification of reactor wastes}
author = {Jouan, A, and Sussmilch, J}
abstractNote = {The vitrification of low and intermediate level wastes from the NPP operation has been studied in the frame of a Franco-Czech agreement. The laboratory experiments concentrated on a search for a suitable borosilicate glass matrix which could incorporate relatively high quantities of boron and sodium, main components of liquid wastes from the WWER reactor type NPPs. A relatively wide area of waste compositions has been studied and properties of glasses suitable for the technology and waste disposal were measured. Great attention has been paid to the chemical stability (leachability), other properties like thermal dependence of viscosity and electrical conductivity of melts, and the microstructure of the final solidification product have also been evaluated. The feasibility of the vitrification process has been proved during pilot plant tests which were accomplished at the French establishment in Marcoule. The results of tests were promising. (authors). 4 tabs., 7 figs.}
place = {France}
year = {1993}
month = {Dec}
}