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
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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}
}
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}
}