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Radiological characterization of metal components in view of melting

Conference:

Abstract

Within the framework of one of their main activities to process and store radioactive wastes produced in Belgium, Belgoprocess compared different scenarios for treatment, conditioning and disposal or recycling of 9 heat exchangers and fuel racks. The 9 heat exchangers were mainly horizontal shell-in-tube aluminum heat exchangers with a total weight of about 42 ton and additionally about 2 ton of aluminum piping. The radioactive contaminated primary water was on the tube side and the cooling water on the shell side. So activity was limited to the inside of the tubes and the primary piping. THe 7 fuel racks were stainless steel constructions with a total weight of 32 ton. Data available on the material mentioned only limited use due to inadequate construction. For both kinds of material two alternative treatment methods were considered: cutting, melting, storing of ingots for decay and waste treatment and disposal of secondary wastes or cutting, supercompaction, cementation and shallow land burial as low level waste. Based on a cost evaluation the melting option has been chosen. Meanwhile transport of all the material to Sweden has started and is expected to be finished by the end of the year 1993. The paper deals with the  More>>
Authors:
Teunckens, L; Blommaert, W [1] 
  1. Belgoprocess, Dessel (Belgium)
Publication Date:
Jul 01, 1995
Product Type:
Conference
Report Number:
IAEA-TECDOC-807; CONF-9311144-
Reference Number:
SCA: 052001; 560180; PA: AIX-26:063936; EDB-95:128472; ERA-20:025310; SN: 95001458152
Resource Relation:
Conference: International Atomic Energy Association (IAEA) specialists meeting on experience in the application of exemption principles, Vienna (Austria), 1-5 Nov 1993; Other Information: PBD: Jul 1995; Related Information: Is Part Of Experience in the application of exemption principles. Proceedings of a specialists meeting held in Vienna, 2-4 November 1993; PB: 237 p.
Subject:
05 NUCLEAR FUELS; 56 BIOLOGY AND MEDICINE, APPLIED STUDIES; RADIOACTIVE WASTES; ACTIVITY LEVELS; TRANSPORT; COST ESTIMATION; FUEL RACKS; HEAT EXCHANGERS; MELTING; RADIOACTIVE WASTE PROCESSING
OSTI ID:
100521
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE95634722; TRN: XA9539852063936
Availability:
INIS; OSTI as DE95634722
Submitting Site:
INIS
Size:
pp. 201-207
Announcement Date:
Jan 16, 2004

Conference:

Citation Formats

Teunckens, L, and Blommaert, W. Radiological characterization of metal components in view of melting. IAEA: N. p., 1995. Web.
Teunckens, L, & Blommaert, W. Radiological characterization of metal components in view of melting. IAEA.
Teunckens, L, and Blommaert, W. 1995. "Radiological characterization of metal components in view of melting." IAEA.
@misc{etde_100521,
title = {Radiological characterization of metal components in view of melting}
author = {Teunckens, L, and Blommaert, W}
abstractNote = {Within the framework of one of their main activities to process and store radioactive wastes produced in Belgium, Belgoprocess compared different scenarios for treatment, conditioning and disposal or recycling of 9 heat exchangers and fuel racks. The 9 heat exchangers were mainly horizontal shell-in-tube aluminum heat exchangers with a total weight of about 42 ton and additionally about 2 ton of aluminum piping. The radioactive contaminated primary water was on the tube side and the cooling water on the shell side. So activity was limited to the inside of the tubes and the primary piping. THe 7 fuel racks were stainless steel constructions with a total weight of 32 ton. Data available on the material mentioned only limited use due to inadequate construction. For both kinds of material two alternative treatment methods were considered: cutting, melting, storing of ingots for decay and waste treatment and disposal of secondary wastes or cutting, supercompaction, cementation and shallow land burial as low level waste. Based on a cost evaluation the melting option has been chosen. Meanwhile transport of all the material to Sweden has started and is expected to be finished by the end of the year 1993. The paper deals with the practical problems encountered with the characterization of the material at the decision making process and at the preparation of the transport. (author). 1 ref.}
place = {IAEA}
year = {1995}
month = {Jul}
}