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Hull melting

Conference:

Abstract

Irradiated fuel cladding scraps produced in reprocessing plants constitute contaminated and irradiating nuclear waste. While the cement embedding method currently used to condition such wastes is simple and inexpensive, an alternative method for conditioning zircaloy and stainless steel cladding wastes has been developed in France by the Commissariat a l`Energie Atomique (CEA) at Marcoule since 1982. The volume reduction factor is maximized and the final product is chemically stable, with a small potential leaching exchange surface area, and contains no tritium. Under some circumstances the decontaminating effect may be sufficient to allow storage under less stringent conditions. A nonradioactive industrial prototype has been built and qualified. Since 1988, a lab-scale hot-cell unit has also demonstrated process feasibility with actual radioactive clads while providing essential process data on volatilization and decontamination factors. A full-scale radioactive industrial prototype has been built in the Pilot Reprocessing Facility at Marcoule and should begin operation in 1992.
Publication Date:
Dec 31, 1991
Product Type:
Conference
Report Number:
CEA-CONF-10552; CONF-910413-
Reference Number:
SCA: 052001; 050800; PA: FRD-92:000066; SN: 92000658045
Resource Relation:
Conference: 3. international conference on nuclear fuel reprocessing and waste management,Sendai (Japan),14 Apr 1991; Other Information: PBD: 1991
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; RADIOACTIVE WASTE PROCESSING; MELTING; FUEL CANS; ALLOY-ZR98SN-4; STAINLESS STEELS; INDUCTION FURNACES; CRUCIBLES; PILOT PLANTS; 052001; 050800; WASTE PROCESSING; SPENT FUELS REPROCESSING
OSTI ID:
10116276
Research Organizations:
CEA Etablissement de la Vallee du Rhone, 30 - Bagnols-sur-Ceze (France)
Country of Origin:
France
Language:
English
Other Identifying Numbers:
Other: ON: DE92767141; TRN: FR9200066
Availability:
OSTI; NTIS (US Sales Only)
Submitting Site:
FRN
Size:
6 p.
Announcement Date:
Jun 30, 2005

Conference:

Citation Formats

Jacquet-Francillon, N, Piccinato, R, Roux, J P, Jouan, A, and Puyou, M. Hull melting. France: N. p., 1991. Web.
Jacquet-Francillon, N, Piccinato, R, Roux, J P, Jouan, A, & Puyou, M. Hull melting. France.
Jacquet-Francillon, N, Piccinato, R, Roux, J P, Jouan, A, and Puyou, M. 1991. "Hull melting." France.
@misc{etde_10116276,
title = {Hull melting}
author = {Jacquet-Francillon, N, Piccinato, R, Roux, J P, Jouan, A, and Puyou, M}
abstractNote = {Irradiated fuel cladding scraps produced in reprocessing plants constitute contaminated and irradiating nuclear waste. While the cement embedding method currently used to condition such wastes is simple and inexpensive, an alternative method for conditioning zircaloy and stainless steel cladding wastes has been developed in France by the Commissariat a l`Energie Atomique (CEA) at Marcoule since 1982. The volume reduction factor is maximized and the final product is chemically stable, with a small potential leaching exchange surface area, and contains no tritium. Under some circumstances the decontaminating effect may be sufficient to allow storage under less stringent conditions. A nonradioactive industrial prototype has been built and qualified. Since 1988, a lab-scale hot-cell unit has also demonstrated process feasibility with actual radioactive clads while providing essential process data on volatilization and decontamination factors. A full-scale radioactive industrial prototype has been built in the Pilot Reprocessing Facility at Marcoule and should begin operation in 1992.}
place = {France}
year = {1991}
month = {Dec}
}