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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Abstracts Session 43<br />
velocity and turbulence characteristics and of inter-species interactions in bidisperse suspensions has been investigated. Results of<br />
particle characterisation are presented, along with mean and turbulent velocity profiles over a range of Reynolds number and particle<br />
concentration. The implications of the work for waste processing within the industrial context will be discussed in the full<br />
paper.<br />
6) APPLICATION OF A NEW TECHNOLOGY FOR REPROCESSING OF WASTES WITHIN THE FRAMEWORK<br />
OF REHABILITATION OF URANIUM MINES OPERATED BY IN SITU LEACHING (wP-59403)<br />
Gagik Martoyan, Garik Nalbandyan, Lavrenti Gagiyan,<br />
AREV SI CJS Company; Gagik Karamyan, Artak Barseghyan, Gagik Brutyan, Ecoatom LLC (Armenia)<br />
It is essential the environmentally safe industrial production of nuclear fuel especially in the case of uranium extraction by In<br />
Situ Leaching, when the environment and the deep extraction of uranium are important problems. In the presented paper it is studied<br />
the feasibility of the application of an electrodialysis method for the deep extraction of uranium and radium from liquid (acid)<br />
streams. It is proposed to apply a new electrodialysis method to ensure the necessary extraction level of elements. In the same time<br />
the new method ensures the recycling of acids used in the process.<br />
7) A FULLY OPERATIONAL PILOT PLANT FOR ELIMINATING RADIOACTIVE<br />
OILS MIXED WITH CHLORINATED SOLVENTS (wP-59044)<br />
Albert Jacobs, William Everett, Dewdrops Company (France)<br />
Disposal of organic liquid waste has become an increasing issue for many nuclear sites. Existing disposal solutions such as<br />
incineration or super critical water techniques are not compatible with wastes containing chlorinated solvents or fluorine owing to<br />
corrosion problems. As an example several hundred cubic meters of lubricating oils mixed with trichloroethylene (TCE) or perchloroethylene<br />
(PCE) are stockpiled on several French nuclear sites. For several years Dewdrops has been developing an original<br />
combination of mineralization processes for waste oils and solvents particularly well suited to the nuclear field. The patented technology<br />
relies on the alternation of chemical and biological oxidation mechanisms. The oxidized organic material predominately<br />
forms carbon dioxide, water and inorganic salts. This paper details the procedure and the results obtained for a particular case at<br />
the Tricastin nuclear site of Areva NC (South France). The organic waste used in this study was a 85/15 v/v ratio mix of lubricating<br />
oil and TCE. The pilot plant build upon the technology has a daily treatment capacity of approximately 10 liters. In the first<br />
step the TCE is mineralized by the photo Fenton reaction. Using hydrogen peroxide with an ultraviolet regenerated iron catalyst,<br />
TCE is transformed to carbon dioxide, water and…<br />
8) ADSORPTION OF CESIUM RADIONUCLIDES BY THE COMPOSITE SORBENTS<br />
CARBON FIBER/TRANSITION METALS FERROCYANIDES (wP-59255)<br />
Irina Sheveleva, Veniamin Zheleznov, Svetlana Bratskaya, Valeriy Kuryavyi,<br />
Valentin Avramenko, Institute of Chemistry FEBRAS (Russia)<br />
Among various methods of cesium removal from aqueous solutions, sorption using transition metals (Ni, Zn, Cu, Fe) ferrocyanides<br />
is the most efficient method due to extremely high affinity of cesium ions to ferrocyanides. Preparation of selective sorbents<br />
by fixation of ferrocyanides crystals in porous matrix of natural clinoptilolite, synthetic zeolites, alumosilicates, and carbon<br />
materials is an efficient way to increase decontamination factors and reduce sorbents expenditure in treatment of 137Cs-containing<br />
wastewaters.<br />
It is known that the efficiency of transition metals ferrocyanides application depends on the crystal size being the highest for<br />
nanocrystals. Although nanocrystals are difficult to handle in a direct application, they can be used in composite materials. In this<br />
case two main problems arise: how to control the crystal size of transition metals ferrocyanides and how to fix them reliably in the<br />
supporting matrix.<br />
In this paper we suggest a new route to preparation of composite materials selective to cesium ions using transition metals ferrocyanides<br />
stabilized by siloxane-acrylate latexes. The size of transition metals ferrocyanides is controlled by the size of the latex<br />
particles and their stability is determined by ionization of polyacrylic acid carboxylic groups on the functionalized latex surface.<br />
These functionalized particles can be used as…<br />
SESSION 43 — SITING, DESIGN, CONSTRUCTION, AND OPERATION<br />
OF L/ILW DISPOSAL FACILITIES - PART 2 OF 2 (1.19)<br />
1) 20 YEARS OF OPERATION FOR CENTRE DE L’AUBE<br />
DISPOSAL FACILITY: LESSONS LEARNED (w/oP-59235)<br />
Patrice Torres, Laurent Schacherer, Franck Duret, Pascal Lecoq, Alain Delaplanche, Michel Dutzer, Andra (France)<br />
The presentation will show the evolution of the facility during thes 20 years: in terms of deliveries, of type of waste packages,<br />
in terms of lexibility to answer the needs of waste generators, in terms of disposal vault design. Lessons leanrd will be emphasized.<br />
It will provide information on the environmental monitoring of the facility.<br />
2) DEMONSTRATION TEST OF UNDERGROUND CAVERN-TYPE<br />
DISPOSAL FACILITIES FISCAL 2010 STATUS (w/oP-59180)<br />
Yoshihiro Akiyama, Kenji Terada, Nobuaki Oda, Tsutomu Yada,<br />
Takahiro Nakajima, Radioactive Waste Management Funding And Research Center (Japan)<br />
The underground cavern-type disposal facilities for low-level waste (LLW) with relatively high radioactivity levels mainly generated<br />
from power reactor decommissioning and for part of transuranic (TRU) waste mainly from spent fuel reprocessing are<br />
designed to be constructed in a cavern around 100 meters below ground, and to employ an engineered barrier system (EBS) of a<br />
combination of bentonite and cement materials in Japan. In order to advance the feasibility study for this disposal, The Demonstration<br />
Test for Underground Cavern-Type Disposal Facilities has commissioned by Japanese government since fiscal 2005, and since<br />
fiscal 2007 a full-scale mock-up test facilities has been constructed under actual subsurface environment. The main objective of the<br />
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