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Radiological impact of very slightly radioactive copper and aluminium recovered from dismantled nuclear facilities; Impact radiologique du au cuivre et a l`aluminium tres faiblement radioctifs provenant du demantelement d`installations nucleaires

Technical Report:

Abstract

This work is in keeping with a large evaluation of doses likely to be received by public and non nuclear workers when dismantling nuclear installations. A bibliographic study and inquiries are realized, in the nuclear field to evaluate quantities of very slightly radioactive materials, in the conventional copper and aluminium recovery fields: waste recovery, metal refinery and processing, occupational or domestic uses of the metals or their alloys. In fact copper and aluminium waste arising from the dismantling of nuclear installations are mainly electrical cables constituents including insulation material which is mainly polyvinyle chloride (PVC). Estimated quantities are relatively low compared to steel quantities arising from dismantling. The study is based on the hypothesis of two PWRs dismantled per year, estimated quantities are 200 tonnes of copper, 40 tonnes of aluminium and 500 tonnes of PVC. A special case is also studied, which is the dismantling of low and medium uranium enrichment plant in Pierrelatte (France); the plant pipework is mainly made of an aluminium and magnesium alloy: AG3. From these informations, one can define exposure scenarios which may occur with a non negligible probability. The doses likely to be received under the foreseen conditions are calculated. Reference doses are  More>>
Authors:
Garbay, H; Chapuis, A M; Cahuzac, O; Guetat, P; Haristoy, D; Renaud, P [1] 
  1. CEA Centre d`Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire
Publication Date:
Dec 31, 1991
Product Type:
Technical Report
Report Number:
EUR-13160
Reference Number:
SCA: 210200; 560101; 220900; 054000; PA: FRD-92:000044; SN: 92000658006
Resource Relation:
Other Information: PBD: 1991
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 61 RADIATION PROTECTION AND DOSIMETRY; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; REACTOR DISMANTLING; ENVIRONMENTAL IMPACTS; HUMAN POPULATIONS; RADIATION DOSES; PERSONNEL; NUCLEAR FACILITIES; NUCLEAR POWER PLANTS; COPPER; ALUMINIUM; LOW-LEVEL RADIOACTIVE WASTES; RECYCLING; ENVIRONMENTAL EXPOSURE PATHWAY; OCCUPATIONAL EXPOSURE; RECOMMENDATIONS; ACTIVITY LEVELS; 210200; 560101; 220900; 054000; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; DOSIMETRY AND MONITORING; REACTOR SAFETY; HEALTH AND SAFETY
OSTI ID:
10116509
Research Organizations:
Commission of the European Communities, Luxembourg (Luxembourg)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
Other: ON: TI92767102; CNN: Contract FI1D-0052; TRN: FR9200044
Availability:
OSTI; NTIS (US Sales Only)
Submitting Site:
FRN
Size:
157 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Garbay, H, Chapuis, A M, Cahuzac, O, Guetat, P, Haristoy, D, and Renaud, P. Radiological impact of very slightly radioactive copper and aluminium recovered from dismantled nuclear facilities; Impact radiologique du au cuivre et a l`aluminium tres faiblement radioctifs provenant du demantelement d`installations nucleaires. France: N. p., 1991. Web.
Garbay, H, Chapuis, A M, Cahuzac, O, Guetat, P, Haristoy, D, & Renaud, P. Radiological impact of very slightly radioactive copper and aluminium recovered from dismantled nuclear facilities; Impact radiologique du au cuivre et a l`aluminium tres faiblement radioctifs provenant du demantelement d`installations nucleaires. France.
Garbay, H, Chapuis, A M, Cahuzac, O, Guetat, P, Haristoy, D, and Renaud, P. 1991. "Radiological impact of very slightly radioactive copper and aluminium recovered from dismantled nuclear facilities; Impact radiologique du au cuivre et a l`aluminium tres faiblement radioctifs provenant du demantelement d`installations nucleaires." France.
@misc{etde_10116509,
title = {Radiological impact of very slightly radioactive copper and aluminium recovered from dismantled nuclear facilities; Impact radiologique du au cuivre et a l`aluminium tres faiblement radioctifs provenant du demantelement d`installations nucleaires}
author = {Garbay, H, Chapuis, A M, Cahuzac, O, Guetat, P, Haristoy, D, and Renaud, P}
abstractNote = {This work is in keeping with a large evaluation of doses likely to be received by public and non nuclear workers when dismantling nuclear installations. A bibliographic study and inquiries are realized, in the nuclear field to evaluate quantities of very slightly radioactive materials, in the conventional copper and aluminium recovery fields: waste recovery, metal refinery and processing, occupational or domestic uses of the metals or their alloys. In fact copper and aluminium waste arising from the dismantling of nuclear installations are mainly electrical cables constituents including insulation material which is mainly polyvinyle chloride (PVC). Estimated quantities are relatively low compared to steel quantities arising from dismantling. The study is based on the hypothesis of two PWRs dismantled per year, estimated quantities are 200 tonnes of copper, 40 tonnes of aluminium and 500 tonnes of PVC. A special case is also studied, which is the dismantling of low and medium uranium enrichment plant in Pierrelatte (France); the plant pipework is mainly made of an aluminium and magnesium alloy: AG3. From these informations, one can define exposure scenarios which may occur with a non negligible probability. The doses likely to be received under the foreseen conditions are calculated. Reference doses are established from recommendations of international organisations as ICRP, IAEA, NEA. Comparing the calculated doses and the reference doses, the activity level of the initial waste can be deduced as to follow the recommendations. The mean specific activity of main beta-gamma emitters in copper, aluminium and PVC are of the same order of magnitude, 10Bq.g{sup -1}. In the case of alpha emitters specific activity levels depend on the material and on the radionuclide, from 2 Bq.g{sup -1} to 10 Bq.g{sup -1} in copper, from 10 Bq.g{sup -1} to 50 Bq.g{sup -1} in aluminium.}
place = {France}
year = {1991}
month = {Dec}
}