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The HRA/SOLARIUM Project: Processing of Historical Waste

[+] Author Affiliations
M. Willems, P. Luycx, R. Gilis

Belgoprocess, Dessel, Belgium

C. I. Renard

ONDRAF/NIRAS, Brussels, Belgium

H. Reyniers, J. M. Cuchet

Belgatom

Paper No. ICEM2003-4732, pp. 513-518; 6 pages
doi:10.1115/ICEM2003-4732
From:
  • ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
  • 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3
  • Oxford, England, September 21–25, 2003
  • Conference Sponsors: Nuclear Engineering Division and Environmental Engineering Division
  • ISBN: 0-7918-3732-7 | eISBN: 0-7918-3731-9
  • Copyright © 2003 by ASME

abstract

Starting in 2003, Belgoprocess will proceed with the treatment and conditioning of some 200 m3 of widely varying high- and medium-level waste from earlier research and development work, to meet standard acceptance criteria for later disposal. The gross volume of primary and secondary packages amounts to 2,600 m3 . The waste has been kept in decay storage for up to 30 years. The project was started in 1997. Operation of the various processing facilities will take 7–8 years. The overall volume of conditioned waste will be of the order of 800 m3 . All conditioned waste will be stored in appropriate storage facilities onsite. In November 2002, a new processing facility has been constructed, the functional tests of the equipment have been performed and the start-up phase has been started. Several cells of the Pamela vitrification facility onsite will be adapted for the treatment of high-level and highly α-contaminated waste; low-level β/γ waste will be treated in the existing facility for super compaction and conditioning by embedding into cement (CILVA). The bulk of these waste, of which 95% are solids, the remainder consisting of mainly solidified liquids, have been produced between 1967 and 1988. They originate from various research programmes and reactor operation at the Belgian nuclear energy research centre SCK-CEN, isotope production, decontamination and dismantling operations. The waste is stored in 4800 primary packages, of which 700 contain 120 g (5.1012 Bq) radium. Half the radium inventory is present in 25 containers. The presence of radium in waste packages, resulting in the emission of radon gas, requires particular measurements. The total activity at the moment of production amounted to 18,811 TBq β/γ and 34.4 TBq α, with individual packages emitting up to 555 TBq β/γ and 2.2 TBq α. According to calculations, the β/γ activity has decreased to some 2,000 TBq, with individual packages up to 112 TBq. The extreme diversity of the waste is not only expressed in their radiological characteristics, but also in their chemical composition, physical state, the nature and condition of the packages. Radioactivity ranges between 0.01 mCi to 1,000 Ci per package. Some packages contain resins, Na, NaK and Al containing waste, poison rods, residues of fuel elements. Although most of the liquid waste are solidified, a small fraction — both aqueous and organic — still remains liquid. Primary packages may be plastic bags, metal boxes, wire gauze, La Calène boxes; secondary packages may be steel drums and concrete containers. Solid waste may be sources, counters, nuclear fuel residues, filters, synthetic materials, metals, resins, granulates, rock, sludges, cables, glass, etc. Some 1000 primary packages are stored in a dry storage vault comprising 20 concrete cells, while 3800 primary packages are stored in some 2,000 concrete containers, on a concrete floor, surrounded by an earth bank to the height of the waste stacking and covered by a metal construction. At present, the annual production of similar waste amounts to 2 m3 divided over some 30 containers. Generally, the primary waste packages will be loaded in 80-1 drums (an average of 2 packages per drum), and compacted in a 150 ton hydraulic press. The pellets will be collected in 100 1 drums (an average of 3 pellets per drum). Low-level β/γ waste is transferred to the CILVA facility for further treatment, while the other 100-1 drums are filled up with sand and, in the case of radium-contaminated waste, tight-welded. Subsequently, the 100-1 drums are loaded into 400-1 drums and embedded into cement. Certain packages, for example solidified radium-contaminated liquids in welded metal containers, are conditioned as such in overpacks. Specific procedures will be established for the various non-standard waste, such as sources, control and poison rods, resins and filters, fuel residues. Highly active and/or heavily α-contaminated waste are transferred to the existing Pamela facility for treatment and conditioning. Ideally, gamma spectrometry measurements are carried out on the primary packages, but due to the extreme diversity of these packages, ranging from plastic bags containing cardboard to highly active steel valves, preference was given to measurements on the conditioned waste, or at least on already pre-compacted waste in the case of treatment in the 2,000 ton press of the CILVA facility. Thus tremendous problems of calibration can be largely avoided. All operations are remotely controlled. Transfers between buildings are carried out within appropriately shielded containers and secondary waste will be treated in existing facilities onsite. The new processing facility is being built partly over the dry storage vaults, in the immediate vicinity of the already covered storage area.

Copyright © 2003 by ASME

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