Ms
Yulia Voskresenskaya
(Andreevna)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
In this work, we studied the release of nitrogen oxides (N2O, NO, and NO2) during UN dissolution at different concentrations of HNO3 (3-16 mol/l) at a ratio between the solid (S) and liquid (L) phases of 1 : 7.5, as well as at an HNO3 concentration of 7.2 mol/l. and L : S ratios from 3 to 30. The UN amounts were varied from 50 mg to 500 mg. The experiments were carried out at a temperature...
Ms
Yulia Voskresenskaya
(Andreevna)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Nitrogen oxides (N2O, NO, and NO2) going into the gas phase during nitride fuel dissolution in HNO3 should be captured before emission into the environment. Very many decontamination technologies allowing an efficient trapping of NO and NO2 have been developed. On the other hand, N2O is not a salifiable compound that can hardly react with acids and alkali. However, there are literature data on...
Dr
Oleg Gromov
(Borisovich)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The vast majority of the known program complexes applied in simulation modeling uses this or that kind of language of very high level which allows to set computer procedures specific for the model without writing special program module for each kind of the systems of ordinary differential equations (SODE). Software for the solution of direct and reverse problems of chemical kinetics is no...
Mrs
Nadezhda Mishina
(Russian Federation)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
A large amount of intermediate level waste (ILW) containing ammonium nitrate, as well as some chelating agents and precipitator, such as diethylene triamine pentaacetic acid (DTPA) is generated during spent nuclear fuel reprocessing which can not be included into vitrified HLW due to the presence of explosive components. ILW processing is proposed which includes ammonium nitrate significant...
Ekaterina Potanina
(Lobachevsky State University of Nizhni Novgorod)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Promising technology of recycling spent nuclear fuel suggests dissolving it in melts chlorides of alkali elements, with extraction of valuable components (U, Pu, minor actinide, etc.) and the transferring of radioactive waste into insoluble compounds. Such technology is anhydrous, therefore, it is more advantageous environmentally compared to aqueous processes. Chloride melts are resistant to...
Dr
Ольга Горбунова
(ФГУП "РАДОН")
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The report reviews the ways of optimization the cementing of boron-containing liquid radioactive waste.
The most common way to hardening the low-level liquid radioactive waste (LRW) is the cementing. However, boron-containing liquid radioactive waste with low pH values can not be cemented without alkaline additives, to neutralize the acid forms of the borate compounds. Cement setting without...
Dr
Olga Gorbunova
(FSUE "RADON")
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Cementation of the solid radioactive waste (SRW), i.e. the inclusion of solid radioactive waste in the cement matrix without cavities - is one of the main technological processes during the conditioning of the low and intermediate radioactive waste. The main task in the process of mixing the solid radioactive waste with the cement solution is to maximize the radioactive waste filling of the...
Mr
Ivan Korchemkin
(Lobachevsky State University of Nizhni Novgorod)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The family of phosphates with a general formula A(I)B(II)PO4 (A(I) − monovalent metal; B(II) − divalent metal with a tetrahedral coordination) includes the groups of compounds with different structure types: β-tridymite, arcanite, glaserite, maricite, olivine. The compounds of this family have been studied because of their ferroelectric, electrochemical and luminescent properties, catalytic...
Dr
Evgeny Veselov
(Russia, Moscow, SIU "RADON")
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The construction and operation of storages of the radioactive waste brings indignations in structure and properties of containing rocks of a near zone of object. Containing rocks get new hydro-geological and geochemical parameters. Change of geochemical conditions in a zone of accommodation of storages defines speed of migration of components in rocks and parameters of process of degradation...
Rostislav Adam
(CTU in Prague, Department of Nuclear Chemistry, Prague 1, Břehová 7, Czech Republic)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Bentonite clay is proposed to be used as buffer material in final disposal of radioactive waste mainly because of its favorable swelling properties and significant sorption capacity for both cationic and anionic forms of many critical radionuclides present in spent fuel. The sorption properties of clay materials used to be described with two types of sorption sites: layer- and edge-sites. The...
Mr
Semen Zavarzin
(Federal State Budjetory Institution of Science A.N.Frumkin Institute of Physical Chemistry and Electrochemistry of Russian Academy of Sciences)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The intermetallic compounds (IMC) of uranium and plutonium with Ru-subgroup metals are expected to be as a principal chemical state of Ru, Rh and Pd in spent (U,Pu)N fuel (SNF) of fast breeder reactors. Their effective dissolution is required for quantitative recycling of fissile materials during the fuel reprocessing.
The corrosion and dissolution of IMC UPd3 and URu3 in 0.5 to 6 M HNO3...
Dr
Vladimir Kulemin
(Frumkin's Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Nuclear power plants with WWER and RBMK reactors annually generate 30000 to 100000 m3 of various liquid radioactive wastes. The increasingly growing amount of liquid radioactive waste of medium (MAW) and low activity (LAW) has made their reprocessing an acute issue. The main task is the separation of the long-lived radionuclides of fission products, the residual amounts of actinides (U, Np,...
Ms
Eva Hofmanová
(Department of Nuclear Chemistry, Czech Technical University in Prague)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Diffusion and sorption parameters are needed to assess the performance of a deep geological repository for high level waste (HLWR). Classical migration experiments are used to obtain these parameters but require long experimental time periods (months to years). The electromigration (EM) technique uses an electrical gradient as driving force to force ionic species to move, hence these data can...
Mr
Jussi Ikonen
(University of Helsinki)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
In many countries, high-level radioactive waste is planned to be disposed of in deep-lying crystalline rock. The role of the geosphere as a safety barrier is one of the most important issues in repository performance assessment. Repository safety evaluation today requires going from the laboratory and surface-based field work to the underground repository level. The diffusion and sorption of...
Ms
Elena Laura Ebert
(Forschungszentrum Jülich GmbH IEK-6)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
For the transmutation in accelerator-driven systems fuels with a high content of Pu and minor actinides (MA = Np, Am, and Cm) are favored. To increase the burn-up of transuranium elements (TRU) and to reduce the formation of new TRU inert matrix fuels (IMF)[1-3] are preferred. These are ceramic substrates or metallic matrices with high thermal conductivity, which are free of uranium and also...
Ms
Elena Laura Ebert
(Forschungszentrum Jülich GmbH IEK-6)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Plutonium and minor actinides (MA = Np, Am, and Cm) are of particular concern with respect to long term radio toxicity, heat load issues and proliferation risks. One possibility to cope with this problem may be the transmutation of plutonium and minor actinides in subcritical accelerator-driven reactors (ADS). Fuels with high Pu and MA contents are preferred for transmutation. To increase the...
Mr
Svyatoslav Nikitin
(Federal State Budjetory Institution of Science A.N.Frumkin Institute of Physical Chemistry and Electrochemistry of Russian Academy of Sciences)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The advantage of electrochemical dissolution of metal or alloy spent nuclear fuel (SNF) consists in the alloy surface oxidation by application of external oxidation potential without adding the chemicals complicating following recovery of fissile materials during SNF reprocessing. The present work deals with the study of electrochemical properties and dissolution of U – 5 mass. % Zr alloy...
Dr
Alexey Rodin
(Scientific and Engineering Centre for Nuclear and Radiation Safety)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Mixtures of reductant with nitrate oxidant are widely used or produced in technological operations radiochemical reprocessing SNF. The potential danger of these mixtures consists in the possibility of oxidation that can occur with a high rate and accompanied by the release of heat and gases, which may lead to the release of the contents of the apparatus or its deformation.
Some of the more...
Dr
Natallia Torapava
(Leibniz University of Hanover)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Iodine-129 being long-lived volatile fission product, among with cesium-135 and technitium-99, represents a challenge for the design of repository-suited matrices [1]. The present study investigates a possibility of iodine incorporation in the forms of iodide and iodate into apatite and layered double hydroxide matrices. The matrice should meet certain requirements, i.e. being cheap, safe,...
Mr
Christian Schreinemachers
(Forschungszentrum Jülich GmbH)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Partitioning and transmutation (P&T) is considered as one of the promising methods to safely handle minor actinides which origin from energy production by nuclear fission. Current focus is on the production of suitable particles which can be used for future fuels.
Promising types of particle fuels are Sphere-pac and Vipac fuels [1]. The Vipac method uses randomly shaped particles, whereas the...
Mrs
Václava Havlová
(Nuclear Research Institute Řež plc.)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The term matrix diffusion usually considers the process by which species, being transported in distinct flow paths, penetrate the surrounding rock through connected system of pores or microfractures. The importance of matrix diffusion is that it provides a mechanism for potential specie retention within enlarged area of rock surface in bulk rock pore network. This is especially crucial when...
Mr
Petr Večerník
(ÚJV Řež, a. s.)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
In several concepts of deep geological repository (DGR) development granites are considered as potential host rocks (Sweden, Finland, Czech Republic). Safety calculations, evaluating safety functions of DGR engineered and natural barriers, require information about radionuclide migration in fractured rock, both by advection and by diffusion in rock matrix. These two processes are the most...
Mr
GuoAn Ye
(China Inetitute of Atomic Energy , under CNNC(China Nation Nuclear Corporation0)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
In order to control Np path-way in plutonium purification process,the extraction behavior of Np(IV) and Np(V) were invastigated with experiment and numerical simulation.
19%-42% Np can be extracted into organic phase in the co-extraction unit while using 1-3mol/L nitric acid as scrubbing reagent,if Np(V) was added into feed solution,because of the oxidation of Np(V) to Np(VI) prompted by...
Mr
GuoAn Ye
(China Inetitute of Atomic Energy , under CNNC(China Nation Nuclear Corporation0)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
In order to control Np path-way in plutonium purification process,the extraction behavior of Np(IV) and Np(V) were invastigated with experiment and numerical simulation.
19%-42% Np can be extracted into organic phase in the co-extraction unit while using 1-3mol/L nitric acid as scrubbing reagent,if Np(V) was added into feed solution,because of the oxidation of Np(V) to Np(VI) prompted by...
Dr
Dagmar Trpkošová
(UJV Řež, a. s.)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
For the safety assessment of the deep geological repository it is necessary to define scenarios of possible repositories development in order to evaluate all possible variants of its development. The present work is devoted to influence of the scenarios defined by the model geometry and model parameters on the development of the main safety indicator, which embedded in the Czech legislation ....
Dr
Andrey Murzin
(Khlopin Radium Institute)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Selective stripping of plutonium from the organic phase is the common way for separation of plutonium from uranium in the first cycle of PUREX-process. The goal of process is conversion of plutonium (IV) to not extractable by TBP plutonium (III). Iron (II) or uranium (IV), with hydrazine as stabilizer, are typically used as reductive agents. In this case stabilizer is responsible for...
Dr
Lixin Sun
(the division of Radio Chemistry and Technology of Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Fluoride volatility method is regarded as a promising pyrochemical reprocessing technology, which might be used to reprocess spent fuels. How to monitor fluorination process on time and precisely is very important. Currently, the methods of monitoring fluorination in industry are mostly the weighting the product and sampling then off-line analysis. The former is poor in the precision, and the...
Mr
Kamil Vavřinec Mareš
(CTU in Prague)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The aim of this work is a separation of 137Cs from model solutions of ammonium molybdate, which probably will be issuing from a reprocessing of CerMet Mo-based transmutation fuel for ADS. Comparing the effectiveness of different sorbents were performed based on the Dg values. The best material KNiFC-PAN (inorganic-organic composite ion exchanger based on potassium-nickel hexacyanoferrate...
Mr
Eros Mossini
(Politecnico di Milano)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The public acceptance of the nuclear energy depends on many aspects, such as safety, environmental impact and sustainability. In this direction, the Partitioning and Transmutation strategy is crucial for an optimal resources utilization and a preferable radioactive waste management. The removal of Minor Actinides from Spent Nuclear Fuel and their transmutation into short-lived or stable...
Mrs
Zana Bikbajeva
(University of Manchester)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Innovative reprocessing methods of spent nuclear fuel are now under development worldwide in order to deliver reprocessing technology compatible with future reactor technologies and novel GEN-IV fuels, including carbide fuels proposed for gas cooled fast reactor (GFR). The main aim of this study, as a part of the ASGARD project (Advanced fuels for Generation IV reactors: Reprocessing and...
Prof.
Lan Zhang
(Shanghai Institute of Applied Physics, Chinese Academy of Sciences), Dr
Yuxia Liu
(Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
TMSR (Thorium-based Molten Salt Reactor) is one of the “Strategic Priority Research Program” of Chinese Academy of Sciences[1]. It offers attractions as power producers because of fuel utilization and safety characteristics. The molten mixture of ThF4, UF4 and LiF-BeF2 was used as fluid fuel in this reactor.
Now we are developing a totally new flow sheet for TMSR fuel cycle in which the...
Prof.
Weiqun Shi
(Institute of High Energy Physics,Chinese Academy of Sciences)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Selectivity for Actinides with N,N’-Diethyl-N,N’-Ditolyl-2,9-Diamide-1,10-
Phenanthroline Ligand: A Hard-Soft Donor Combined Strategy
Wei-Qun Shi*, Cheng-Liang Xiao, Li-Yong Yuan, Yu-Liang Zhao, Zhi-Fang Chai,
Key Laboratory of Nuclear Radiation and Nuclear Energy Technology, Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049, China
* Corresponding author:...
Mr
Josef Chudoba
(Technical University of Liberec)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
When evaluating Nuclear Waste DGR Safety [1] it is necessary to confirm its safety in a long run and above all its safety towards the biosphere, more precisely that the biosphere will not be in any hazard caused by radioactive substances. With the aid of geologists a model of a hypothetical area (the Melechov Massif) was elaborated and described with the use of geological (38 types of rocks...
Ms
Agata Oszczak
(Institute of Nuclear Chemistry and Technology)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Storage of radioactive wastes requires various protective barriers against leaking of the stored radionuclides: metal canisters (tanks), buffers made of adsorbent of metal ions, and often the surrounding rocks. On the other hand, humidity from the outside may penetrate the storage tanks. Various biopolymers and naturally occurring inorganic adsorbents were intensively examined as inexpensive...
Dr
Oleg Gromov
(Borisovich)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Impurity 106RuF5, 237NpF6 and 99TcF6 in regenerated of uranium hexafluoride are the most radiation-hazardous impurity. For decrease in a dose of radiation it is expedient to carry out extraction of these elements from UF6 [1, 2].
Researches on catching of radionuclides from dividing streams raw and perfect of uranium hexafluoride are carried out on various fluoride adsorbents of I, II, III...
Dr
Masanobu Nogami
(Kinki University)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
In order to develop resins with selectivity to U(VI) in HNO3 media, we have synthesized several sili-ca-supported polymer beads with the structure of a monoamide as the functional group. The examination on their adsorptivities to various metal ions has clarified that among these resins those consisting of N,N-dimethyl-
acrylamide (Silica-DMAA) and N-methyl-N-vinylbenzylacetamide(Silica-MVBAA)...
Dr
Evgeny Polyakov
(Institute of Solid State Chemistry, UB RAS), Dr
Nina Barysheva
(RFNC-VNIITF)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Equilibrium electrochemical behavior of (U, Pu)N in LiCl–KCl eutectic melts is of great significance for computer modeling of high-temperature electrochemical reprocessing of fast reactors with nitride fuel and lead coolant (BREST) fuel [1]. We have carried out thermodynamic modeling of pyrochemical reprocessing of (U, Pu)N in LiCl-KCl eutectic melt by using software codes and databases HSC...
Mrs
Elena Veselova
(Russia, Moscow, SIU "RADON")
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
At the present moment the age of the most of near-surface waste storages is more than several decades and most of protective barriers have lost their original characteristics and are not able to provide necessary insulation. As a result, atmospheric precipitations penetrate into the storage and redistribution of radionuclides within the storage as well as their removal beyond the storage...
Mr
Vladimir Tkachenko
(Bochvar Institute (VNIINM))
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Nuclear fuel cycle (NFC) closure is significant objective for contemporary energetics. One of the perspective ways at this direction is closed NFC based on fast neutron reactors using nitride fuel.
One of the problems of irradiated nitride fuel (INF) reprocessing is radioactive carbon-14 handling. Unlike oxide fuel nitride fuel will contain nitrogen-14, which partially will transform to...
Mrs
Kateřina Videnská
(ÚJV Řež, a. s.)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The formation and stability of clay colloids from the engineered barrier system of deep geological repository for radioactive waste may have a direct impact on safety in two aspects: firstly, generation of colloids may degrade the engineered barrier and colloid transport of radionuclides may reduce the efficiency of the natural barrier.
The presented work is focused on the study of the...
Ms
Olga Shudegova
(Russian)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Study of carbon dioxide solubility in nitric acid and metal nitrates solutions for estimation of carbon-14 distribution between gas phase and solution during dissolution of spent nuclear fuel
O. Ustinov, A. Shadrin, O. Shmidt, O. Shudegova
JSC «VNIINM», Moscow, 5a Rogova st., Russian Federation
Tel. +7-499-199-8227, Fax. +7-499-196-6451, E-mail:march@bochvar.ru
In the reprocessing...
Mr
Jan Škarohlíd
(Research Centre Rez)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Fluoride Volatility Method is considered to be a prospective advanced reprocessing technology for spent nuclear fuels of FBR systems. The experimental verification of the Fluoride Volatility Method has played an important role in Czech R&D devoted to Partitioning and Transmutation. The goal of the experimental technological line FERDA (Fluoride Experimental Research and Development Assembly),...
Dr
Nicholas Evans
(Loughborough University)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The UK has a relatively high inventory of 99Tc in the wastes to manage. Under the planned cementitious Geological Disposal facility (GDF) conditions of high pH and low Eh most Tc should be immobile as amorphous technetium dioxide. Nevertheless, not much is known about the behaviour of this solid phase. The Loughborough University task within work-package 3 was to investigate the dissolution...
Dr
Alex Аnaniev
(Vladilenovich), Ms
Maya Kalenova
(Yurievna), Dr
Oleg Gromov
(Borisovich)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The concept of radioactive waste management of IAEA and State Corporation "Rosatom" is based on the principle of multilevel environmental protection, according to which the isolation of the waste will be provided by the system of engineering and natural barriers including inert matrix, sealed container, buffer (filler) and geological formation.
The main objective of the first barrier is the...
Prof.
Qingnuan Li
(Shanghai Insititute of Applied Physics, CAS)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
In 2011, Chinese Academy of Sciences (CAS), after discontinuing the research and development activity in nuclear energy for decades, started to implement Strategic Priority Research Program "Future Advanced Fission Nuclear Energy (FANE)". To perform this program, two sub-bases, the north and the south, were deployed in CAS. Shanghai Institute of applied physics (SINAP), as the south sub-base,...
Mrs
Václava Havlová
(ÚJV Řež, a.s.)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
Crystalline rocks are considered as potential host rock for deep geology repository (DGR) of radioactive waste in many countries. In order to define safety functions of host rock and gained performance assessment relevant input data, detailed examination of rock migration parameters, for relevant radionuclides has to be performed. DGR is usually planned to be constructed at the depth 400 – 600...
Dr
Vladimir Kulemin
(Frumkin's Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences)
15/05/2014, 17:30
Chemistry of Nuclear Fuel Cycle / 1st ASGARD International Workshop
Poster
The generation of a great amount of radioactive waste of various radionuclide compositions and activity levels call for the development of various methods of waste reprocessing and storage, as well as the production of new equipment and setups. Vitrification is considered to be one of the main directions for high-level waste disposal. Vitrified waste must be placed in containers meeting...
