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Argentina: Disposal aspects of RA-1 research reactor decommissioning waste

Technical Report:

Abstract

The objective of the project is to analyze disposal aspects of waste from total dismantling of Argentinean research reactors, starting with the oldest one, 48 years old RA-1. In order to estimate decommissioning waste, data was collected from files, area monitoring, measurements, sampling to measure activity and composition, operational history and tracing of operational incidents. Measurements were complemented with neutron activation calculations. Decommissioning waste for RA-1 is estimated to be 71.5 metric tons, most of it concrete (57 tons), the rest being steels, lead and reflector graphite (4.8 tons). Due to their low specific activities, no disposal problems are foreseen in the case of metals and concrete. Disposal of aluminium, steel, lead and concrete is analyzed. On the contrary, as the country has no experience in managing graphite radioactive waste, work was concentrated on that material. Stored (Wigner) energy may exist in RA-1 graphite reflectors irradiated at room temperature. Evaluation of stored energy by calorimetric methods is proposed, and its annealing by inductive heating; HEPA filters should be used to deal with gaseous activity emissions, mainly Cl-36 and C-14. Galvanic corrosion, dust explosion, ignition and oxidation can be addressed and should not become disposal problems. Care must be taken with  More>>
Authors:
Harriague, S; Barberis, C; Cinat, E; Grizutti, C; Scolari, H [1] 
  1. Comision Nacional de Energia Atomica, Buenos Aires (Argentina)
Publication Date:
Dec 15, 2007
Product Type:
Technical Report
Report Number:
IAEA-TECDOC-1572(companion CD)
Resource Relation:
Other Information: 14 refs, 1 fig., 5 tabs; Related Information: In: Disposal aspects of low and intermediate level decommissioning waste. Results of a coordinated research project 2002-2006, 159 pages.
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; ARGENTINA; CALORIMETRY; CARBON 14; CHLORINE 36; CONCRETES; DECOMMISSIONING; INTERMEDIATE-LEVEL RADIOACTIVE WASTES; LOW-LEVEL RADIOACTIVE WASTES; RA-1 REACTOR; RADIOACTIVE WASTE DISPOSAL; STEELS
OSTI ID:
21003821
Research Organizations:
International Atomic Energy Agency, Waste Technology Section, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISBN 978-92-0-109107-9; ISSN 1011-4289; TRN: XA08N0064027949
Availability:
Available from INIS in electronic form; Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/TE_1572_companion_CD_web.pdf and on 1 CD-ROM attached to the printed IAEA-TECDOC-1572
Submitting Site:
INIS
Size:
page(s) 1-12
Announcement Date:
Apr 19, 2008

Technical Report:

Citation Formats

Harriague, S, Barberis, C, Cinat, E, Grizutti, C, and Scolari, H. Argentina: Disposal aspects of RA-1 research reactor decommissioning waste. IAEA: N. p., 2007. Web.
Harriague, S, Barberis, C, Cinat, E, Grizutti, C, & Scolari, H. Argentina: Disposal aspects of RA-1 research reactor decommissioning waste. IAEA.
Harriague, S, Barberis, C, Cinat, E, Grizutti, C, and Scolari, H. 2007. "Argentina: Disposal aspects of RA-1 research reactor decommissioning waste." IAEA.
@misc{etde_21003821,
title = {Argentina: Disposal aspects of RA-1 research reactor decommissioning waste}
author = {Harriague, S, Barberis, C, Cinat, E, Grizutti, C, and Scolari, H}
abstractNote = {The objective of the project is to analyze disposal aspects of waste from total dismantling of Argentinean research reactors, starting with the oldest one, 48 years old RA-1. In order to estimate decommissioning waste, data was collected from files, area monitoring, measurements, sampling to measure activity and composition, operational history and tracing of operational incidents. Measurements were complemented with neutron activation calculations. Decommissioning waste for RA-1 is estimated to be 71.5 metric tons, most of it concrete (57 tons), the rest being steels, lead and reflector graphite (4.8 tons). Due to their low specific activities, no disposal problems are foreseen in the case of metals and concrete. Disposal of aluminium, steel, lead and concrete is analyzed. On the contrary, as the country has no experience in managing graphite radioactive waste, work was concentrated on that material. Stored (Wigner) energy may exist in RA-1 graphite reflectors irradiated at room temperature. Evaluation of stored energy by calorimetric methods is proposed, and its annealing by inductive heating; HEPA filters should be used to deal with gaseous activity emissions, mainly Cl-36 and C-14. Galvanic corrosion, dust explosion, ignition and oxidation can be addressed and should not become disposal problems. Care must be taken with graphite dust generation and disposal, due to wetting and flotation problems. Lessons learned from the project are presented, and the benefits of sharing international experience are stressed. (author)}
place = {IAEA}
year = {2007}
month = {Dec}
}