ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events

Abstracts Session 9
11) INSTRUMENTED MEASUREMENTS ON RADIOACTIVE WASTE DISPOSAL
CONTAINERS DURING EXPERIMENTAL DROP TESTING (wP-59142)
Thomas Quercetti, Andre Musolff, Karsten Müller,
BAM - Federal Institute for Materials Research and Testing (Germany)
In context with disposal container safety assessment of containers for radioactive waste the German Federal Institute for Materials
Research and Testing (BAM) performed numerous drop tests in the last years. The tests were accompanied by extensive and
various measurement techniques especially by instrumented measurements with strain gages and accelerometers.
The instrumentation of a specimen is an important tool to evaluate its mechanical behavior during impact. Test results as deceleration-time
and strain-time functions constitute a main basis for the validation of assumptions in the safety analysis and for the
evaluation of calculations based on finite-element methods. Strain gauges are useful to determine the time dependent magnitude of
any deformation and the associated stresses. Accelerometers are widely used for the measuring of motion i.e. speed or the displacement
of the rigid cask body, vibration and shock events. In addition high-speed video technique can be used to visualize and analyze
the kinematical impact scenario by motion analysis.
The paper describes some selected aspects on instrumented measurements and motion analysis in context with low level
radioactive waste (LLW) container drop testing.
12) REGULATORY CLEARANCE OF SPENT STEEL DRUMS (wP-59405)
Dae-Seok Hong, Korea Atomic Energy Research Institute; Young-Yong Ji, Il-Sik Kang,
Kyoung-Kil Kwak, Woo-Seog Ryu, KAERI (Korea)
At KAERI(Korea Atomic Energy Institute), radioactive soil and concrete wastes with extremely low level of activity were regulatory
cleared in 2008 and large amount of spent drums were remained. After generation, drums having good physical integrity
were reused for packaging radioactive wastes and about 50 tons of drums unsuitable for reuse were stored as radioactive wastes.
Once having been used for packaging regulatory cleared radioactive wastes, these spent drums were determined to be cleared.
Before clearance, steel drums were radiation monitored, washed with pressurized water two times, compacted and stored at a designated
area. Based on radiological dose assessment result using a clearance scenario, the clearance of steel drums was permitted
by the regulatory body. And then, treatment of the cleared drums was committed to a scrap-metal dealer for recycling. In this study,
a process of the regulatory clearance for spent steel drums and a modified radiological dose assessment model for the scrap-metal
dealer will be discussed.
13) LIQUID WASTE TREATMENT PROCESS (w/oP-59061)
Bouchta Moussaif, Touria Lambarki el Allioui, CNESTEN (Morocco)
The law defined the responsibilities of the national center of nuclear energy in Morocco CNESTEN as the sole radioactive
waste operating organization and designated CNESTEN as responsible for the management of radioactive waste at the national
level in several social and economic sectors.
The goals of the unit of radioactive waste management are: -reduce the volume of the radioactive waste product; -convert the
radioactive waste into an appropriate waste for monitoring, storage and evacuation; -Recover if it’s possible an element of value.
The Moroccan products of radioactive liquid waste per year are 0.1m3 of organic liquid and 35 m3 of liquid aqueous. The
method adopted by CNESTEN was the evaporator for liquid aqueous and the solidification with the activated carbon for the organic
liquid. An evaporation installation to treat 5 m3 of aqueous liquid in each campaign, the volume of the sludge obtained is 200
liters and 4800 liters of distillate water. Concerning the management system is plan to collect the liquid aqueous in tanks in the bottom
of each nuclear installation. After characterization according to the technical specification of radioactive waste management
nuclear installation, the waste is transported in an appropriate tank to the treatment building to be evaporated. After treatment the
clean water is collect in a separate tank waiting its discharge if it complies with the requirements of release. The volume of sludge
issued from evaporator is conditioning with mortar (40 liters) in 120liters drum, the mixing operation is ensured by shingles introduced
in the drum and the rotation of the drum is ensured by a mixer named “turn drums”. The drum must respect the acceptance
criteria before transferred to storage building. About the liquid organic waste was collected in the polyethylene move tank; this kind
of waste is mixed to an absorbent product and conditioned like the sludge.
14) CAST IRON TRANSPORT, STORAGE AND DISPOSAL CONTAINERS FOR
USE IN UK NUCLEAR LICENSED SITES (w/oP-59412)
Joerg Viermann, Matthias P Messer, GNS Gesellschaft fuer Nuklear-Service mbH (UK)
Ductile Cast Iron Containers of the types GCVI (UK trademark -GNS YELLOW BOX®) and MOSAIK® have been in use in
Germany for transport, storage and disposal of intermediate level radioactive waste (ILW) for more than two decades. In 2009 a
number of containers of these types were delivered to various Magnox sites as so called pathfinders to test their suitability for Magnox
waste streams. The results were encouraging. Therefore the Letter of Compliance (LoC) procedure was started to prove the
suitability of packages using these types of containers for the future UK Geological Disposal Facility (GDF) and a conceptual Letter
of Compliance (cLoC) was obtained from RWMD in 2010. Waste stream specific applications for Interim Stage Letters of Compliance
(ILoC) for a number of waste streams from different Magnox sites and from the UKs only pressurised water reactor,
Sizewell B are currently being prepared and discussed with RWMD.
In order to achieve a package suitable for interim storage and disposal the contents of a Ductile Cast Iron Container only has
to be dried. Mobile drying facilities are readily available. Containers and drying facilities form a concerted system.
During treatment, interim storage and transport the containers provide shielding and structural integrity….
15) OPTIMIZATION OF RADIOACTIVE WASTE CEMENTATION FOR
DECOMMISSIONING OF SALASPILS RESEARCH REACTOR (wP-59066)
Gunta Abramenkova, Maris Klavins, University of Latvia; Andris Abramenkovs,
Latvian Environment, Geology and Meteorology Centre (Latvia)
This paper deals with information on the radioactive waste cementation technology for decommissioning of Salaspils Research
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