ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events
ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events
ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events
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Session 44 Abstracts<br />
test is to establish construction methodology and procedures which ensure the required quality of the engineered barrier system<br />
(EBS) on-site. By fiscal 2010 some parts of the facilities has been constructed, and the test has demonstrated both practicability of<br />
the construction and achievement of the quality. They are respectively taken as low-permeability of less than 5E-13 m/s and lowdiffusion<br />
of less than 1E-12 m2 /s at the time of completion of construction. This paper covers the test results obtained by the construction<br />
of some parts of a bentonite and cement materials.<br />
3) DEMONSTRATION OF GAS PERMEABLE SEALS FOR RADIOACTIVE WASTE<br />
REPOSITORIES LABORATORY AND IN-SITU EXPERIMENTS (wP-59224)<br />
Joerg Rueedi, Paul Marschall, Nagra (Switzerland)<br />
In low/intermediate-level waste (L/ILW) repositories, anaerobic corrosion of metals and degradation of organic materials produce<br />
hydrogen, methane, and carbon dioxide. Gas migration in a L/ILW repository is one of the processes evaluated in the safety<br />
assessment of deep geological disposal in low-permeability formations, in particular with respect to the development of gas pressures<br />
in the repository caverns which could negatively affect the host rock or the engineered barrier system (EBS). In order to<br />
restrict build-up of gas overpressures in the emplacement caverns, Nagra (National Cooperative for the Disposal of Radioactive<br />
Waste, Switzerland) has proposed design options aimed at increasing the gas transport capacity of the backfilled underground structures,<br />
compromising neither the low hydraulic conductivity nor the radionuclide retention capacity of the EBS (Nagra, 2008). They<br />
involve specially designed backfill and sealing materials such as high porosity mortars as backfill materials for the emplacement<br />
caverns and sand/bentonite (S/B) mixtures with a bentonite content of 20% to 30% for the seals themselves and for backfilling other<br />
underground structures. These increased gas permeability materials can supplement the gas flow that is expected to occur through<br />
the excavation damaged zone (EDZ) and avoid the creation of overpressures.<br />
Preliminary experimental studies have confirmed the gas…<br />
4) POST-IODINE PRODUCTION NORM REPOSITORY TECHNICAL DESIGN AND<br />
RECONSTRUCTION EXPERIENCE IN TURKMENISTAN (wP-59183)<br />
Alexander Gelbutovsky, Peter Cheremisin, Alexander Troshev, Alexander Egorov,<br />
Mikhail M. Boriskin, Mikhail Bogod, ECOMET-S (Russia)<br />
Continuous extraction of the iodine, bromine and other elements from the underground mineral waters at the Balkanabat<br />
Iodine and Khazar chemical plants (Turkmenistan) resulted in their territories NORM contamination and significant waste quantities<br />
formation. Sites radiation safety is the major issue. Usually there are no any radiation monitoring systems and staff providing<br />
personnel, population and environment radiation safety and negative influence elimination. The most dangerous sites are the ones<br />
which are situated in the Caspian Sea coastal area. In 2009 the remediation project was initiated to prevent NORM distribution and<br />
eliminate environmental threat. The project frame covers a number of preparation and design works, charcoal sorption shops demolition,<br />
territories remediation, production waste conditioning and transportation to the repository for further safe storage. For that<br />
purposes the repository has been built in the near-by natural hollow. In the given report the materials related to repository design,<br />
reconstruction and operations start are presented. The brief data on the facilities condition, contamination characteristics and waste<br />
quantities are indicated. It is shown that that the mechanical method has been chosen for contaminated materials collecting and disposal.<br />
Main demolition, remediation and transportation decisions, activities and results are mentioned also.<br />
SESSION 44 — DISPOSAL SITE AND WASTE FORM CHARACTERIZATION<br />
AND PERFORMANCE ASSESSMENT - PART 1 OF 2 (1.13)<br />
1) RADIOLOGICAL CHARACTERIZATION OF THE DUTCH INTERIM<br />
WASTE STORAGE FACILITY SITE (w/oP-59023)<br />
Jeroen Welbergen, COVRA; Leo P.M. Velzen, Nuclear Research and Consultancy Group (Netherlands)<br />
The Central Organization for Radioactive Waste (COVRA) in the Netherlands operates since 1993 in the south-west of the<br />
Netherlands a facility for treatment of radioactive waste including interim storage buildings for HLW, LILW and NORM wastes as<br />
calcinate and depleted uranium (U3O8 ). The site of the interim waste storage facility has a size of about 200,000 m2 and is situated<br />
close to the Dutch nuclear power plant Borssele and a large phosphate production plant.<br />
It is evident that the waste storage site is subjected at regular time intervals at non-intrusive radiological measurements (e.g.<br />
dose-rate and contamination) to detect elevated radiation levels. However, these radiological measurements have not yet been performed<br />
according to approaches as described in the Environment Radiation Site Survey Execution Manual EURSSEM or the Multi<br />
Agency Radiation Site Survey Inspection Manual MARSSIM .<br />
The aim of the paper is threefold, first to describe in detail the process how to apply EURSSEM and especially for fast nonintrusive<br />
multi radiological detection techniques with control measurements. Second aim is to present and discuss the analyze<br />
results and follow up actions. The third and last aim is to discuss the advantages and disadvantages of combining the analyze results<br />
of fast non-intrusive measurements…<br />
2) CLIMATE CHANGE IMPACTS ON THE DISPOSAL ENVIRONMENT:<br />
A CLIMATE ANALOGUE APPROACH (wP-59274)<br />
Bertrand Leterme, Dirk Mallants, SCK●CEN (Belgium)<br />
The Belgian Agency for Radioactive Waste and Enriched Fissile Materials (ONDRAF/NIRAS) aims to develop a surface disposal<br />
facility for L/ILW in Dessel (North-East of Belgium). The objective of this study is to provide estimates for the next few millennia<br />
of both infiltration through the planned earth cover and groundwater recharge in the vicinity of the Dessel site. Available predictions<br />
of future temperature and precipitation often extend until AD 2100 only (e.g. IPCC). To circumvent this data limitation,<br />
we use existing records of climatic analogue stations deemed representative of future climates in Belgium. The following climate<br />
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