Geological factors of disposal site selection for low-and intermediate-level solid radwastes in China

International Nuclear Information System (INIS)

Chen Zhangru

1993-01-01

For disposal of low- and intermediate-level solid radioactive wastes, shallow-ground disposal can provide adequate isolation of waste from human for a fairly long period of time. The objective of disposal site selection is to ensure that the natural properties of the site together with the engineered barrier site shall provide adequate isolation of radionuclides from the human beings and environment, so the whole disposal system can keep the radiological impact within an acceptable level. Since the early 1980's, complying with the national standards and the expert's conception as well as the related IAEA Criteria, geological selection of disposal sites for low-and intermediate-level solid radwastes has been carried out in East China, South China, Northwest China and Southwest China separately. Finally, 5 candidate sites were recommended to the CNNC

Low-level radwaste solidification

International Nuclear Information System (INIS)

Naughton, M.D.; Miller, C.C.; Nelson, R.A.; Tucker, R.F.

1983-01-01

This paper reports on a study of ''Advanced Low-Level Radioactive Waste Treatment Systems'' conducted under an EPRI contract. The object of the study is to identify advanced lowlevel radwaste treatment systems that are commercially available or are expected to be in the near future. The current state-ofthe-art in radwaste solidification technology is presented. Related processing technologies, such as the compaction of dry active waste (DAW), containers available for radwaste disposal, and the regulatory aspects of radwaste transportation and solidification, are described. The chemical and physical properties of the currently acceptable solidification agents, as identified in the Barnwell radwaste burial site license, are examined. The solidification agents investigated are hydraulic cements, thermoplastic polymers, and thermosetting polymers. It is concluded that solidification processes are complex and depend not only on the chemical and physical properties of the binder material and the waste, but also on how these materials are mixed

Industrial Complex for Solid Radwaste Management at Chernobyle Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Ahner, S.; Fomin, V. V.

2002-02-26

In the framework of the preparation for the decommissioning of the Chernobyl Nuclear Power Plant (ChNPP) an Industrial Complex for Solid Radwaste Management (ICSRM) will be built under the EC TACIS Program in the vicinity of ChNPP. The paper will present the proposed concepts and their integration into existing buildings and installations. Further, the paper will consider the safety cases, as well as the integration of Western and Ukrainian Organizations into a cohesive project team and the requirement to guarantee the fulfillment of both Western standards and Ukrainian regulations and licensing requirements. The paper will provide information on the status of the interim design and the effects of value engineering on the output of basic design phase. The paper therefor summarizes the design results of the involved design engineers of the Design and Process Providers BNFL (LOT 1), RWE NUKEM GmbH (LOT 2 and General) and INITEC (LOT 3).

Low-level radwaste engineering economics

International Nuclear Information System (INIS)

Jacobs, M.H.; Miller, C.C.; Young, L.G.

1984-07-01

This topical report on engineering economics for low-level radwaste systems details the methodologies used for economic analyses of radwaste treatment systems and provides examples of radwaste economic evaluations. All of the parameters and cost items used in an evaluation are defined. Examples of the present-value-of-revenue-requirements method, levelized-revenue-requirements method, and the equivalent-capital-investment method are provided. Also, the calculation to determine the maximum justifiable capital expenditure for a radwaste system is illustrated. The report also provides examples of economic evaluations for many current radwaste treatment options. These options include evaporation versus demineralization, dewatering resins versus solidification of resins, and several volume reduction systems. 15 figures, 6 tables

The improvement program of radwaste treatment at Chinshan nuclear power station

International Nuclear Information System (INIS)

Lin, M.M.H.; Huang, C.Y.

1986-01-01

Chinshan-1 and 2, the twin 636-megawatt boiling water reactors with independent radwaste treatment facilities, located at northern Taiwan, started power generation in 1977 and 1978, respectively. Initial years of operation of CSNPS indicated a need for improvement of the radwaste scheme originally provided. The major betterment programs for radwaste system include: (1) addition of auxiliary demineralization system and addition resin storage tank/demineralizer, (2) addition of dry laundry and miscellant drain system, (3) addition of off-gas charcoal delay system, (4) tie connection of the liquid waste system of unit 1 and 2, (5) solid waste system retrofit study, (6) volume reduction study. The administration and water quality controls have also been much improved and the discharge of radioactivity is considerably lower after the improvement has been implemented

Radwaste - Multimedia presentation

International Nuclear Information System (INIS)

2000-01-01

Radioactivity is a part of the Nature since the creation of the Earth. We have learned how to use radioactivity in medicine, power industry, and in other areas of life. Similarly as in other activities, waste is generated. We offer you basic information about radioactivity and radioactive waste (radwaste) in four films: Radioactivity, Source of radwaste, Management of radwaste. In the glossary are video presentations: Container (Castor) for radioactive waste; Deep underground repository; Transport vehicle; WWER type reactor. Encyclopedic part of the program contains detailed theoretical and practical information about use of radioactivity and radioactive waste. You will find the explanation in the part Glossary. (authors)

The generation characteristics of solid radioactive wastes in the KEPCO nuclear power plants

International Nuclear Information System (INIS)

Shon, Soon Hwan; Kang, Duck Won; Kim, Hee Keun

1991-01-01

Solid radwastes generation trend and characteristics were discussed for nuclear power plants in KEPCO. Each plant has a specific tendency of solid radwastes generation due to the plant characteristics. The total volume of solid radwastes generated from nine power plants was accumulated in 23,012 drums by the end of 1989. The average annual volume per unit was about 670 drums. The solid radwaste mostly consisted of solidified concentrates and contaminated trash. The contaminated trash has been the major portion of the solid radwastes since 1982. The volume of the contaminated trash was dependent on the availability factor and period of overhaul. Therefore, the contaminated trash was considered to be a prime target for the solid radwastes minimization plan

Technological process of a multi-purpose radwaste incineration system

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Qiu Mingcai; Yang Liguo; Li Xiaohai; Zhang Xiaobin; Lu Xiaowu; Dong Jingling; Wang Xujin; Li Chuanlian; Yang Baomin

2002-01-01

The author introduces the technological process of a multi-purpose radwaste incineration system. It is composed of three parts: pretreatment, incinerating and clean up of off-gas. The waste that may be treated include combustible solid waste, spent resins and oils. Technological routes of the system is pyrolysis incinerating for solid waste, spray incinerating for spent oils, combination of dry-dust removing and wet adsorption for cleaning up off-gas

Development of core sampling technique for ITER Type B radwaste

Energy Technology Data Exchange (ETDEWEB)

Kim, S. G.; Hong, K. P.; Oh, W. H.; Park, M. C.; Jung, S. H.; Ahn, S. B. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Type B radwaste (intermediate level and long lived radioactive waste) imported from ITER vacuum vessel are to be treated and stored in basement of hot cell building. The Type B radwaste treatment process is composed of buffer storage, cutting, sampling/tritium measurement, tritium removal, characterization, pre-packaging, inspection/decontamination, and storage etc. The cut slices of Type B radwaste components generated from cutting process undergo sampling process before and after tritium removal process. The purpose of sampling is to obtain small pieces of samples in order to investigate the tritium content and concentration of Type B radwaste. Core sampling, which is the candidates of sampling technique to be applied to ITER hot cell, is available for not thick (less than 50 mm) metal without use of coolant. Experimented materials were SS316L and CuCrZr in order to simulate ITER Type B radwaste. In core sampling, substantial secondary wastes from cutting chips will be produced unavoidably. Thus, core sampling machine will have to be equipped with disposal system such as suction equipment. Core sampling is considered an unfavorable method for tool wear compared to conventional drilling.

Development of commercial robots for radwaste handling

International Nuclear Information System (INIS)

Colborn, K.A.

1988-01-01

The cost and dose burden associated with low level radwaste handling activities is a matter of increasing concern to the commercial nuclear power industry. This concern is evidenced by the fact that many utilities have begun to revaluate waste generation, handling, and disposal activities at their plants in an effort to improve their overall radwaste handling operations. This paper reports on the project Robots for Radwaste Handling, to identify the potential of robots to improve radwaste handling operations. The project has focussed on the potential of remote or automated technology to improve well defined, recognizable radwaste operations. The project focussed on repetitive, low skill level radwaste handling and decontamination tasks which involve significant radiation exposure

Radwastes management program of the IEN

International Nuclear Information System (INIS)

Peres, S.S.; Godoy, J.M.O

2000-01-01

Low level radioactive wastes are produced during the operation of the radioactive and nuclear installations of the Nuclear Engineering Institute (Instituto de Engenharia Nuclear, IEN) situated in Rio de Janeiro City, Brazil. These wastes can be generated during the operation and maintenance of the CV-28 Cyclotron, the radioisotopes production, the research activities using natural thorium and uranium in chemical laboratories and, eventually, during the operation Argonauta Reactor. In accordance to the methodology of the radwastes management adopted in the IEN, the wastes are segregated and treated depending on theirs physical, chemical, biological and radiological properties. The wastes with important levels of activity are separate and collected in special containers. Wastes containing short-lived radionuclides are also separated and left away for decaying. Solid wastes are constituted of materials used in laboratories, such as papers, rubber gloves, plastics, over shoes, broken glassware, metal pieces, etc. These wastes are classified as compressible, combustible, non-compressible and non- combustible. The solid wastes are collected in suitable containers placed throughout the working area. Basically, the treatment methods used for these wastes are activity decay, decontamination and compaction. Liquid wastes are generated in small volumes and, generally, containing little quantities of radionuclides. These wastes are classified as aqueous and non-aqueous, acid, alkaline. The diluted aqueous wastes produced in hot laboratories are collected in liquid effluent collection stations for analysis by gamma spectrometry. If the activity concentration is smaller than the established limits in waste management national standards, they are discharge inside of the local sanitary sewer system. Otherwise, these wastes are retained for treatment. The treatment methods used for liquid wastes are activity decay, chemical precipitation, ion exchange and immobilization in inert

Selection of detailed items for periodic safety review on PWR radwaste management system

Energy Technology Data Exchange (ETDEWEB)

Sung, K. B.; Ahn, Y. S.; Park, Y. S.; Kim, S. H.; Kim, J. T. [Korea Hydric and Nuclear Power Company, Taejon (Korea, Republic of)

2003-10-01

Selection of detailed-items for Periodic Safety Review on PWR radwaste management system, the main component could be faithfully clarified according to the purpose of establishment on each system and basic purpose. It is proper to select detailed-items those of radioactivities in the reactor coolant activity levels and the released volume of liquid and gaseous radioactive material on safety performance. It's also proper to select solid radwaste production quantities as detailed-item that it would be predict the next ten years trends after PSR.

Radwaste volume reduction and solidification by General Electric

International Nuclear Information System (INIS)

Green, T.A.; Weech, M.E.; Miller, G.P.; Eberle, J.W.

1982-01-01

Since 1978 General Electric has been actively engaged in developing a volume reduction and solidifcation system or treatment of radwaste generated in commercial nuclear power plants. The studies have been aimed at defining an integrated system that would be directly responsive to the rapid evolving needs of the industry for the volume reduction and solidification of low-level radwaste. The resulting General Electric Volume Reduction System (GEVRS) is an integrated system based on two processes: the first uses azeotropic distillation technology and is called AZTECH, and the second is controlled-air incineration...called INCA. The AZTECH process serves to remove water from concentrated salt solutions, ion exchange resins and filter sludge slurries and then encapsulates the dried solids into a dense plastic product. The INCA unit serves to reduce combustible wastes to ashes suitable for encapsulation into the same plastic product produced by AZTECH

Solid radioactive waste management in Daya Bay Nuclear Power Station

International Nuclear Information System (INIS)

Huang Laixi; He Wenxin; Chen Degan

2004-01-01

This paper introduces the solid radwaste management system, treatment methods and its continuous improvement during the past 9 years in Guangdong Daya Bay Nuclear Power Station (GNPS). GNPS has paid great attention and made a lot of efforts to implement the principle of waste minimization with source control, improvement of treatment process and strict management, so the output of solid radwastes has annually decreased since 1994. In 2002, the output of solid radwastes in GNPS was 63.5 m 3 , only 50% of 1995 (127 m 3 ), reached the advanced level as the same type NPPs in France. During the period 1994-2002, the accumulated production of solid radwaste Packages in GNPS is 1563.51 m 3 only 18% of the design value; all the packages meet the standard and requirement for safe disposal. Besides, this paper analyzes some new technical processes and presents some proposals for further decreasing the solid radwaste production

An incinerator for combustable radwastes

International Nuclear Information System (INIS)

Li Jingquan; Jiang Yun; Zhang Yinsheng; Chen Boling; Zhang Shihang

1989-01-01

An incinerator has been built up in Shanghai. In this paper, the devices of the incinerator, main parameters of the process, and the results of non-radioactive waste and simulated radwaste combustion tests were contributed. That provides reference information for radwaste treatment with incineration process

An analysis on radwaste management in China

International Nuclear Information System (INIS)

Chen Haicheng; Qu zhimin

1999-05-01

Considerable masses of radwastes have been produced in China during past period of four decades. The government has paid great attentions to the management of those radwastes and much progress has been made. The development of nuclear power has led the national radwaste management into a new era, meanwhile has brought about new challenges and issues for the existing management system. The analysis indicates that the existing management system is comprehensive but needs to be further improved: (1) regulations system of radwaste management needs to be perfected; (2) a special operational agency for managing radwastes has to be founded; (3) a financing system for long-term management is expected to be created; (4) information and interaction programs should be carried out and involved in the national management strategy

The experience of liquid radwaste evaporator performance improvement

International Nuclear Information System (INIS)

Kwon, S. H.

1997-01-01

Ulchin NPP has only one monobloc evaporation column which treated all radwaste liquid for two units. Since commercial operation in 1988 the evaporator performance is very poor. I think that the bad condition of evaporator is because of the bad quality of liquid radwaste, the large volume of liquid radwaste to treated, the poor skill of operation and some mistake in equipment design. Because of above conditions the average released activity by liquid radwaste is 35.153mCi/year in last eight years(1988∼1995). So it is necessary that we have to improve the evaporator performance and to reduce the liquid radwaste volume to evaporate

Operational experience on reduction of feedwater iron and liquid radwaste input for Kuosheng Nuclear Power Plant

International Nuclear Information System (INIS)

Wen, T.J.; Huang, Theresa Chen; Liu, Wen Tsung; Liu, T.C.; Shyur, Tzu Sheng; Shen, S.C.

1998-01-01

Other than cobalt alloys, or low cobalt materials, feedwater iron content plays an important role in crud activation and transport causing the growth of out-of-core radiation fields and associated with radwaste generation. Before installing prefilter in the upstream of condensate deep-bed demineralizer, increasing demand for suspended solid removal required new backwash and regeneration technique in Kuosheng Nuclear Power Plant. At steady state full power operation, the average iron concentration in condensate demineralizer influent was 8-15 ppb. Considering both the necessity of backwash and reduction of liquid radwaste input, several actions had been taken to promote the crud removal capabilities without using ultrasonic resin cleaner and controlled feedwater iron content between 0.5 and 2.0 ppb. This modified resin backwash technique would also generate minimum liquid radwaste. Meanwhile, significant efforts have been made to promote the quality of waste water by carefully control input streams as well as backwash modification to reduce liquid radwaste generation. The daily quantity of liquid radwaste has decreased dramatically in the past two years and is effectively controlled under the expected average daily input of design basis. (author)

Analysis on long-term strategy for radwaste management in China

Energy Technology Data Exchange (ETDEWEB)

Chen Haicheng [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-08-01

Radwaste presents a worldwide issue in the management of environmental protection. Most countries carrying out nuclear programs have developed strategies for their radwastes management. China has been executing its strategy, but the development of nuclear power is representing new challenges for the national radwastes management. This paper tries an analysis on the long-term management of radwastes in China. The exiting system of China`s radwastes management is explained. Two important issues on radwastes management i.e. economics and social issues are analyzed. The future issues that will affect China`s radwastes management are discussed. A short summary of the national radwastes management in NEA countries is involved in the paper. The analysis indicates that in China the exiting system of radwastes management is comprehensive but remains to be perfected. Improvements of long-term management need to be made in the aspects of economics and social issue. A financing system for long-term management, as a supplement for the exiting system of radwastes management, is expected to be created. (author)

Analysis on long-term strategy for radwaste management in China

International Nuclear Information System (INIS)

Chen Haicheng

1998-08-01

Radwaste presents a worldwide issue in the management of environmental protection. Most countries carrying out nuclear programs have developed strategies for their radwastes management. China has been executing its strategy, but the development of nuclear power is representing new challenges for the national radwastes management. This paper tries an analysis on the long-term management of radwastes in China. The exiting system of China's radwastes management is explained. Two important issues on radwastes management i.e. economics and social issues are analyzed. The future issues that will affect China's radwastes management are discussed. A short summary of the national radwastes management in NEA countries is involved in the paper. The analysis indicates that in China the exiting system of radwastes management is comprehensive but remains to be perfected. Improvements of long-term management need to be made in the aspects of economics and social issue. A financing system for long-term management, as a supplement for the exiting system of radwastes management, is expected to be created. (author)

Cement radwaste solidification studies third annual report

International Nuclear Information System (INIS)

Brown, D.J.; James, J.M.; Lee, D.J.; Smith, D.L.; Walker, A.T.

1982-03-01

This report summarises cement radwaste studies carried out at AEE Winfrith during 1981 on the encapsulation of medium and low active waste in cement. During the year more emphasis has been placed on the work which is directly related to the solidification of SGHWR active sludge. Information has been obtained on the properties of 220 dm 3 drums of cemented waste. The use of cement grouts for the encapsulation of solid items has also been investigated during 1981. (U.K.)

Advanced liquid radwaste decontamination by using a centrifuge system

International Nuclear Information System (INIS)

Tscheschlok, K.; Szukala, M.

1999-01-01

Waste water streams basically include undissolved suspended solids which contain almost the main part of the activated products. The centrifuge system, called LRS (Liquid Radwaste Treatment System), is able to remove these solids from the liquid content and fills the dewatered product into disposal containers. For this purpose a chemical pre-treatment step is often used for selective precipitation of special radionuclides and flocculents to agglomerate smaller sized particles (colloids) to make them separatable with the LRS. The plant arrangement, the process optimization and the collected operational experiences are described. 2 refs., 1 tab., 8 figs

North Sea focus on radwaste disposal

International Nuclear Information System (INIS)

Cope, D.

1990-01-01

At the recent North Sea Conference in the Netherlands possible future strategies for managing radioactive waste (radwaste) proved to be a contentious issue. Several of its North Sea littoral neighbours sought a categorical assurance that the UK would forego the option of constructing a subterranean radwaste repository which though accessed from land, extends under the coastline, or a sub-seabed facility reached from an offshore structure. It was pointed out that the UK has no present plans for such a radwaste repository. However, sub-seabed designs as a possibility for future repositories were not ruled out. NIREX has decided to concentrate its exploration work at two sites -Sellafield and Dounreay. Both sites are coastal locations and the government is aware that detailed geological exploration may favour extension of a radwaste repository beyond the shoreline, even if initially developed entirely on land. The design of such a radioactive waste repository is outlined. The position of NIREX and the Radioactive Waste Management Advisory Committee is discussed. (author)

Human engineering in mobile radwaste systems

International Nuclear Information System (INIS)

Jones, D.; McMahon, J.; Motl, G.

1988-01-01

To a large degree, mobile radwaste systems are replacing installed plant systems at US nuclear plants due to regulatory obsolescence, high capital and maintenance costs, and increased radiation exposure. Well over half the power plants in the United States now use some sort of mobile system similar to those offered by LN Technologies Corporation. Human engineering is reflected in mobile radwaste system design due to concerns about safety, efficiency, and cost. The radwaste services business is so competitive that vendors must reflect human engineering in several areas of equipment design in order to compete. The paper discusses radiation exposure control, contamination control, compact components, maintainability, operation, and transportability

Radwaste treatment complex. DRAWMACS planned maintenance system

International Nuclear Information System (INIS)

Keel, A.J.

1992-07-01

This document describes the operation of the Planned Maintenance System for the Radwaste Treatment Complex. The Planned Maintenance System forms part of the Decommissioning and Radwaste Management Computer System (DRAWMACS). Further detailed information about the data structure of the system is contained in Database Design for the DRAWMACS Planned Maintenance System (AEA-D and R-0285, 2nd issue, 25th February 1992). Information for other components of DRAWMACS is contained in Basic User Guide for the Radwaste Treatment Plant Computer System (AEA-D and R-0019, July 1990). (author)

Volume reduction equipment for low-level radwastes

International Nuclear Information System (INIS)

Hofmann, J.; Schlich, E.

1982-01-01

Volume reduction of low-level radwaste has been used for years in Germany to reduce the on-site storage capacity which is required until an ultimate disposal site is available. The incineration of trash is a well established cost effective method for dry active waste volume reduction and now liquid radwaste treatment is gaining the operational experience which establishes it as a routine procedure. Resin pyrolysis is a promising new development which when successfully implemented will augment the other systems by safely volume reducing a radwaste which is of increasing concern

Correlation between radwaste processing and hazardous waste treatment processes

International Nuclear Information System (INIS)

Block, O.U.J.; Tulipano, F.J.

1988-01-01

The basic framework under SARA has established that preferred remedies are those which permanently and significantly reduce toxicity, mobility or volume of wastes. In the 1970's radwaste process designs at power plants received pressure to satisfy essentially the same criteria when increased emphasis was placed on limited disposal sites which resulted in rapidly escalating disposal costs. This paper provides a historical perspective of radwaste experience and discusses valuable insight to hazardous waste treatment technologies. The radwaste system experience is discussed in terms of providing a source of proven and reliable technologies. Discussion is presented on specific radwaste processes which are applicable technologies for hazardous waste treatment. The technologies presented include (a) Solidification, (b) Evaporation, and (c) Incineration. Experience is presented which establishes assurance that the treatment technologies will provide a permanent remedy to hazardous waste treatment. This paper describes typical radwaste solidification, evaporation and incineration processes at power plants. The design requirements and implementation of radwaste equipment is correlated to design requirement of hazardous waste equipment. Specific discussion is provided on how the available process equipment can reduce toxicity, mobility, and volume of waste. Discussion is presented on how the standard off the shelf processing equipment needs to be modified for radwaste and hazardous waste applications

Radwaste disposal by incorporation in matrix

International Nuclear Information System (INIS)

Curtiss, D.H.; Heacock, H.W.

1976-01-01

A process of safe disposal, handling, or storae of radwaste associated with nuclear power productin is described. A feature of the invention is to incorporate the radwaste in a hardenable, matrix-forming mass employing a cement-type binding agent to which alkali or alkaline-earth silicate is added, among other things, to increase liquid absorption. 9 claims

Modular radwaste volume reduction and solidification systems

International Nuclear Information System (INIS)

Miller, E.L.

1986-01-01

This paper describes both the modular transportable and the modular mobile liquid radwaste volume reduction and solidification units based on a General Electric Company developed and patented process called AZTECH (a trademark of GE). An AZTECH system removes all water by azeotropic distillation and encapsulates the remaining solids in a polyester compound. The resulting monolith is suitable for either long term above ground storage or shallow land burial. Pilot and demonstration plant testing has confirmed the design parameters. The three processing modules are covered together with data which resulted in Nuclear Regulatory Commission approval on Dec. 30, 1985

Radwastes management in Qinshan Nuclear power plants

International Nuclear Information System (INIS)

Zhou Huan; Ling Kechi; Wang Qingrong; Luo Jingfan

1987-01-01

The source terms input used as the basic data for designing the radwaste treatment systems of Qinshan Nuclear Power Plant [300 MW(e)] is presented. The classification of radioactive liquid wastes, off-gases and solid wastes, and their treatment techniques, as well as on-site storage facilities for solid wastes are described. For liquid waste, the method of filtration-evaporation-ion exchange will be used as the main treatment technique. For off-gas, Holdup-decay treatment will be used. For evaporator concentrates, indrumsolidification method with normal domestic portland cement will be used. The assessment of impact of effluents to environment at normal operation of the NPP is also made. The results show that it will be safe for inhabitants nearby during normal operation and it can meet the requirements of national standard ''Regulation of Radiation Protection''

Radwaste assessment program for nuclear station modifications by design engineering

International Nuclear Information System (INIS)

Eble, R.G.

1988-01-01

Radwaste burial for Duke Power Company's (DPC's) seven nuclear units has become a complicated and costly process. Burial costs are based on overall volume, surcharges for radioactivity content and weight of containers, truck and cask rental, driver fees, and state fees and taxes. Frequently, radwaste costs can be as high as $500 per drum. Additionally, DPC is limited on the total burial space allocated for each plant each year. The thrust of this program is to reduce radwaste volumes needing burial at either Barnwell, South Carolina, or Richland, Washington. A limited number of options are available at our sites: (a) minimization of radwaste volume production, (b) segregation of contamination and noncontaminated trash, (c) decontamination of small hardware, (d) volume reduction of compatible trash, (e) incineration of combustible trash (available at Oconee in near future), and (f) burial of below-regulatory-concern very low level waste on site. Frequently, costs can be reduced by contracting services outside the company, i.e., supercompaction, decontamination, etc. Information about radwaste volumes, activities, and weight, however, must be provided to the nuclear production department (NPD) radwaste group early in the nuclear station modification (NSM) process to determine the most cost-effective method of processing radwaste. In addition, NSM radwaste costs are needed for the NPD NSM project budget. Due to the advanced planning scope of this budget, NSM construction costs must be estimated during the design-phase proposal

Introduction to the outlines of radwaste administration policy of the Republic of China

International Nuclear Information System (INIS)

Huang, C.C.; Tsai, C.M.

1992-01-01

This paper discusses the Radwaste Administration Policy (ORAP) which first drafted by the Radwaste Administration (RWA), a subordinate organization of the Atomic Energy Council (AEC) of the Republic of China, and was approved by the Executive Yuan (Cabinet) on September 16, 1988. ORAP has laid down the guidelines for both radwaste administration by RWA and radwaste management by Taiwan Power Company (TPC or Taipower) and other radwaste producers. ORAP will govern radwaste-related activities in the Republic of China in the foreseeable future. The text of ORAP is shown in the Appendix of this paper

Duke Power's liquid radwaste processing improvement efforts

International Nuclear Information System (INIS)

Baker, R.E. Jr.; Bramblett, J.W.

1995-01-01

The rising cost of processing liquid radwaste and industry efforts to reduce offsite isotopic contributions has drawn greater attention to the liquid radwaste area. Because of economic pressures to reduce cost and simultaneously improve performance, Duke Power has undertaken a wide ranging effort to cost effectively achieve improvements in the liquid radwaste processing area. Duke Power has achieved significant reductions over recent years in the release of curies to the environment from the Liquid Radwaste Treatmentt systems at its Catawba, McGuire, and Oconee stations. System wide site curie reductions of 78% have been achieved in a 3 year period. These curie reductions have been achieved while simultaneously reducing the amount of media used to accomplish treatment. The curie and media usage reductions have been achieved at low capital cost expenditures. A large number of approaches and projects have been used to achieve these curie and media usage reductions. This paper will describe the various projects and the associated results for Duke Power's processing improvement efforts. The subjects/projects which will be described include: (1) Cooperative philosophy between stations (2) Source Control (3) Processing Improvements (4) Technology Testing

Safety analysis report for radwaste foam transport cask

International Nuclear Information System (INIS)

Ku, J. H.; Lee, J. C.; Bang, K. S.; Seo, K. S.; Lee, D. W.; Kim, J. H.; Park, S. W.; Lee, J. W.; Kim, K. H.

1999-08-01

For the tests and examinations of radwaste foam which generated in domestic nuclear power plants a radioactive material transport cask is needed to transport the radwaste foam from the power plants to KAERI. This cask should be easy to handle in the facilities and safe to maintain the shielding safety of operators. According to the regulations, it should be verified that this cask maintains the thermal and structural integrities under prescribed load conditions by the regulations. The basic structural functions and the integrities of the cask under required load conditions were evaluated. Therefore, it was verified that the cask is suitable to transport radwaste foam from nuclear power plants to KAERI. (author). 11 refs., 10 tabs., 25 figs

Peculiarities of the High-Level Concrete-Encased Radwaste Repository Disposition at the Radwaste Disposal Site of the Russian Research Center 'Kurchatov Institute'

International Nuclear Information System (INIS)

Volkov, V.G.; Ponomarev-Stepnoi, N.N.; Gorodetsky, G.G.; Zverkov, Yu.A.; Ivanov, O.P.; Lemus, A.V.; Semenov, S.G.; Stepanov, V.E.; Chesnokov, A.V.; Shisha, A.D.

2006-01-01

The paper presents peculiarities of organization and performance of activities on disposition of the old repository that contained high-level waste and located at the radwaste disposal site of the Russian Research Center 'Kurchatov Institute' in Moscow. The repository was constructed in the late 1950's. A large number of cases with high-level waste were placed in the repository along with low- and intermediate-level waste. When the repository was filled in 1973, the entire radwaste mass was encased in concrete matrix which caused difficulties with the radwaste extraction and made the work on the repository disposition highly hazardous in terms of radiation conditions. Based on results of the preliminary radiation survey of the repository, technologies and equipment to be used in disposition works were selected, and a decision on construction of external radiation shielding around the repository to maintain normal radiation conditions during these works was made. Specific features of the selected radiation shielding design constructed around the repository and of a technology used for the radwaste extraction from the repository are provided. According to the technology, conventional construction machines equipped with a hydraulic hammer or a clamshell were used for destruction of the concrete-encased radwaste mass and extraction of low-level waste. Intermediate- and high-level waste was extracted by remotely controlled robots operating inside the radiation shielding structure. Video cameras and a gamma imager were used for detection of high-level waste or fragments of such radwaste in the mass concrete being destroyed and for guiding remotely controlled robots. Peculiarities of rapid control of changes in radiation conditions in the working areas are presented. This control was performed using a gamma locator with on-line transmission of its data to a PC for their processing. With disposition of this not easily accessible repository, the stage of remediation of old

Establishment and status of the radwaste management standards in China

International Nuclear Information System (INIS)

Zhuo Fengguan

1993-01-01

In the last 30 years and more, with the development of nuclear industry in China, the government, nuclear industry circles and scientists have paid great attention to the safety management of radwastes. Especially in past 10 years, with the implementation of the nuclear power programmes, the safety management of radwastes has been legalized steadily NEPA (National Environment Protection Agency, China), NNSA (National Nuclear Safety Administration) and the competent authorities concerned have engaged in establishing and promulgating policies, regulations, and a series of technical standards on the safety management of radwaste, and efforts are being made to complete and perfect related regulations and standards. The status and programs of radwaste safety management standards in China are briefly introduced, including principles, organizations and procedure for drafting the standards

Fluidized bed volume reduction of diverse radwastes

International Nuclear Information System (INIS)

McFee, J.N.; McConnell, J.W.; Waddoups, D.A.; Gray, M.F.; Harwood, L.E.; Clayton, N.J.; Drown, D.C.

1981-01-01

Method and apparatus for a fluidized bed radwaste volume reduction system are claimed. Low level radioactive wastes, combustible solids, ion exchange resins and filter sludges, and liquids, emanating from a reactor facility are introduced separately through an integrated waste influent system into a common fluidized bed vessel where volume reduction either through incineration or calcination occurs. Addition of a substance to the ion exchange resin before incineration inhibits the formation of low-melting point materials which tend to form clinkers in the bed. Solid particles are scrubbed or otherwise removed from the gaseous effluent of the vessel in an off-gas system, before the cooled and cleaned off-gas is released to the atmosphere. Iodine is chemically or physically removed from the off-gas. Otherwise, the only egress materials from the volume reduction system are containerized dry solids and tramp material. The bed material used during each mode may be circulated, cleaned, stored and exchanged from within the bed vessel by use of a bed material handling system. An instrumentation and control system provides operator information, monitors performance characteristics, implements start up and shut down procedures, and initiates alarms and emergency procedures during abnormal conditions

Development of sampling techniques for ITER Type B radwaste

International Nuclear Information System (INIS)

Hong, Kwon Pyo; Kim, Sung Geun; Jung, Sang Hee; Oh, Wan Ho; Park, Myung Chul; Kim, Hee Moon; Ahn, Sang Bok

2016-01-01

There are several difficulties and limitation in sampling activities. As the Type B radwaste components are mostly metallic(mostly stainless steel) and bulk(∼ 1 m in size and ∼ 100 mm in thickness), it is difficult in taking samples from the surface of Type B radwaste by remote operation. But also, sampling should be performed without use of any liquid coolant to avoid the spread of contamination. And all sampling procedures are carried in the hot cell red zone with remote operation. Three kinds of sampling techniques are being developed. They are core sampling, chip sampling, and wedge sampling, which are the candidates of sampling techniques to be applied to ITER hot cell. Object materials for sampling are stainless steel or Cu alloy block in order to simulate ITER Type B radwaste. The best sampling technique for ITER Type B radwaste among the three sampling techniques will be suggested in several months after finishing the related experiment

Development of sampling techniques for ITER Type B radwaste

Energy Technology Data Exchange (ETDEWEB)

Hong, Kwon Pyo; Kim, Sung Geun; Jung, Sang Hee; Oh, Wan Ho; Park, Myung Chul; Kim, Hee Moon; Ahn, Sang Bok [KAERI, Daejeon (Korea, Republic of)

2016-05-15

There are several difficulties and limitation in sampling activities. As the Type B radwaste components are mostly metallic(mostly stainless steel) and bulk(∼ 1 m in size and ∼ 100 mm in thickness), it is difficult in taking samples from the surface of Type B radwaste by remote operation. But also, sampling should be performed without use of any liquid coolant to avoid the spread of contamination. And all sampling procedures are carried in the hot cell red zone with remote operation. Three kinds of sampling techniques are being developed. They are core sampling, chip sampling, and wedge sampling, which are the candidates of sampling techniques to be applied to ITER hot cell. Object materials for sampling are stainless steel or Cu alloy block in order to simulate ITER Type B radwaste. The best sampling technique for ITER Type B radwaste among the three sampling techniques will be suggested in several months after finishing the related experiment.

A reliability-risk modelling of nuclear rad-waste facilities

International Nuclear Information System (INIS)

Lehmann, P.H.; El-Bassioni, A.A.

1975-01-01

Rad-waste disposal systems of nuclear power sites are designed and operated to collect, delay, contain, and concentrate radioactive wastes from reactor plant processes such that on-site and off-site exposures to radiation are well below permissible limits. To assist the designer in achieving minimum release/exposure goals, a computerized reliability-risk model has been developed to simulate the rad-waste system. The objectives of the model are to furnish a practical tool for quantifying the effects of changes in system configuration, operation, and equipment, and for the identification of weak segments in the system design. Primarily, the model comprises a marriage of system analysis, reliability analysis, and release-risk assessment. Provisions have been included in the model to permit the optimization of the system design subject to constraints on cost and rad-releases. The system analysis phase involves the preparation of a physical and functional description of the rad-waste facility accompanied by the formation of a system tree diagram. The reliability analysis phase embodies the formulation of appropriate reliability models and the collection of model parameters. Release-risk assessment constitutes the analytical basis whereupon further system and reliability analyses may be warranted. Release-risk represents the potential for release of radioactivity and is defined as the product of an element's unreliability at time, t, and the radioactivity available for release in time interval, Δt. A computer code (RARISK) has been written to simulate the tree diagram of the rad-waste system. Reliability and release-risk results have been generated for cases which examined the process flow paths of typical rad-waste systems, the effects of repair and standby, the variations of equipment failure and repair rates, and changes in system configurations. The essential feature of this model is that a complex system like the rad-waste facility can be easily decomposed into its

Novel conditioning methods for radwaste and residues

International Nuclear Information System (INIS)

Rittscher, D.

1993-01-01

Due to the fact that a federal radwaste repository is not yet available and on-site or afr interim storage capacities are limited, new conditioning techniques and strategies for avoiding accruement of radwaste from nuclear power plant operation have been developed, leading to a reduction of annual radwaste amounts from 1800 m 3 (BWR) and 650 m 3 (PWR) in the year 1980 to 160 m 3 (BWR) and 40 m 3 (PWR) in 1990. This very significant reduction of waste amounts was achieved by (1) improvements in on-site waste management, (2) application of volume-reducing, new condititioning techniques (as e.g. dehydration of liquid waste instead of embedding in cement, (3) consequent application of radiologically safe recycling techniques for steel scrap (production of cast steel containers, e.g.), and (4) the use of optimized packaging forms (e.g. containers instead of 200-l waste drums). (orig./DG) [de

Verification test of an engineering-scale multi-purpose radwaste incinerator

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Qiu Mingcai; Yang Liguo; Li Xiaohai; Zhang Xiaobin; Lu Xiaowu; Dong Jingling; Wang Xujin; Li Chuanlian; Yang Baomin

2002-01-01

The verification test of an engineering-scale multi-purpose radwaste incinerator was implemented. The test items include performance determination for the system when solid wastes (include resins) or spent oil were incinerating and off gas was cleaning, tracer test for determining decontamination factor and 72 h continuos running test. 500 h tests verify the reliability and feasibility of designs of technological process, main structure, instrument control and system safety. The incineration system ran smoothly, devices and instruments worked stably. The specifications such as capacity, volume reduction factor, carbon remainder in ash and decontamination factor all meet the design requirements

Integrated data base for spent fuel and radwaste: inventories

International Nuclear Information System (INIS)

Notz, K.J.; Carter, W.L.; Kibbey, A.H.

1982-01-01

The Integrated Data Base (IDB) program provides and maintains current, integrated data on spent reactor fuel and radwaste, including historical data, current inventories, projected inventories, and material characteristics. The IDB program collects, organizes, integrates, and - where necessary - reconciles inventory and projection (I/P) and characteristics information to provide a coherent, self-consistent data base on spent fuel and radwaste

The Morsleben radwaste repository. Preparing for decommissioning

International Nuclear Information System (INIS)

Mehnert, M.; Schmitt, R.

2001-06-01

The publication is intended to illustrate with a brief chronology the history and the present situation of the Morsleben radwaste repository, including specific aspects such as the geology of the site and construction and engineering activities, the particulars of waste form emplacement and log-term storage conditions, topical issues relating to radiological safety during operation and after decommissioning. The brochure is designed for the general audience interested in background information on all aspects of the uses, operation and decommissioning of a radwaste repository in Germany. (orig./CB) [de

Hot Isostatic Press (HIP) vitrification of radwaste concretes

International Nuclear Information System (INIS)

Siemer, D.D.; Scheetz, B.; Gougar, M.L.D.

1995-01-01

Properly formulated and properly ''canned'' radwaste concretes can be readily hot-isostatically-pressed (HIPed) into materials that exhibit performance equivalent to typical radwaste-type glasses. The HIPing conditions (temperature/pressure) required to turn a concrete waste form into a ''vitrified'' waste form are quite mild and therefore consistent with both safety and high productivity. This paper describes the process and its products with reference to its potential application to Idaho Chemical Processing Plant (ICPP) reprocessing wastes

Cost-benefit analysis for environmental impacts and radwaste system for nuclear power plant

International Nuclear Information System (INIS)

Mun, K.N.; Yook, C.C.

1982-01-01

During operation of nuclear power plant, radioactive material is inevitably formed. This radioactive material must be safely processed by radwaste system so that essentially zero activity is released to the environment. However zero released activity is not really practicable and population doses resulted from released activity are proportional to total annual cost for the radwaste system. In this study, cost-benefit analysis for the radwaste system of the Korean Nuclear Units 5 and 6 is performed to evaluate the optimization between the total annual cost for the radwaste system and population doses within 80 km from the plants. From the analysis, the following results are obtained; 1. the total population dose is estimated 4.04 x 10 3 man-rem/year, 2. total annual cost for the radwaste system is required $ 1.74 x 10 6 , 3. cost-benefit ratio is estimated $ 429/man-rem. (Author)

Minimum radwaste system to support commercial operation-what equipment can be deferred

International Nuclear Information System (INIS)

Marshall, R.W.; Tafazzoli, M.M.

1984-01-01

Because of cash flow problems being experienced by utilities as nuclear power stations approach completion, areas of the plant for which the completion of the construction effort could be deferred past commercial operation should be reviewed. The radwaste treatment systems are prime candidates for such a deferral because of the availability, either temporary or permanent, of alternative treatment methods for the waste streams expected to be produced. In order to identify the radwaste equipment, components and associated hardware in the radwaste building which could be deferred past commercial operation, a study was performed by Impell Corporation to evaluate the existing radwaste treatment system and determine the minimum system necessary to support commercial operation of a typical BWR. The study identified the minimum-installed radwaste treatment system which, in combination with portable temporary equipment, would accommodate the waste types and quantities likely to be produced in the first few years of operation. In addition, the minimum-installed system had to be licensable and excessive radiation exposures should not be incurred during the construction of the deferred portions of the system after commercial operation. From this study, it was concluded that a significant quantity of radwaste processing equipment and the associated piping, valves and instrumentation could be deferred. The estimated savings, in construction manhours (excluding field distributables) alone, was over 102,000 M-H

Radwaste reduction experience at Oyster Creek and Three Mile Island Nuclear Power Plants

International Nuclear Information System (INIS)

Ross, M.

1993-01-01

True radwaste minimization at an operating nuclear power plant means straddling the line between ''what is'' and ''what-can-be'' and then regularly moving that line so that dreams become reality. This effort involves keeping track of and maintaining successful programs of the past while searching out and incorporating the best of the upcoming processes, equipment, and contractors. Some of the tactics used for waste minimization have appreciable results and some have small direct results. But even those with small results add to a final total of volume saved. In addition, the approaches with smaller results demonstrate an unmistakable attitude on the part of management that any unnecessary radwaste production is not acceptable. This attitude is understood and assimilated by engineering, operations, and maintenance in such a way that it becomes a matter of pride to reduce radwaste production to quantities below those officially projected. The GPUN plants at Oyster Creek and Three Mile Island Unit-1 limit the quantity of materials allowed onsite under the premise that an item that stays out of contaminated areas cannot become radwaste. For material exiting contaminated zones, the plants have used a combination of preventative avoidance of radwaste generation and careful processing. This includes sorting and screening of materials leaving contaminated areas to reduce the number of items to eventually be treated, preplanning of work efforts to minimize radwaste that must be generated, wood planning, onsite decontamination units, onsite contractor supplied equipment, and offsite radwaste processors in order to minimize the final amount of radwaste to be buried. Sometimes when employing one of these methods, it is necessary to consider not only the waste generated by the process directly but also secondary wastes caused by interactions with other areas of plant operation, such as equipment maintenance

Disposal of solid radioactive waste of nuclear power plant

International Nuclear Information System (INIS)

YU Shichen.

1986-01-01

The contaminations of marine enviroment by the disposal of radwastes should not been expected, then ocean disposal has been stoped in some countries, and land disposal of solid radwastes should been a better method for mankind and environment protection. Ground burial near the surface is currently considered to be feasible. Storage in spent pit or in plant area also should been adapted in several countries

Treatment of LL and ML liquid radwaste. The SGN experience

International Nuclear Information System (INIS)

Tchemitcheff, E.; Roux, P.

1993-01-01

SGN (Societe Generale pour les Techniques Nouvells) with considerable know-how and thirty years of feed-back in industrial management of liquid effluents from the entire French nuclear industry, has accordingly completed many low- and medium-level liquid radwaste treatment, relying on two major industrially proven technologies: evaporation and chemical coprecipitation. The low level and medium level radwaste in France and evaluated

Breaking the paradigm: Revitalizing the liquid radwaste program at River Bend Station

International Nuclear Information System (INIS)

Mallory, C.C. II; Lewis, C.A.

1996-01-01

In December 1995, River Bend Station established the goal of becoming a liquid radwaste open-quotes zero dischargeclose quotes plant by 1998. A new paradigm was required to reduce River Bend Station's annual discharge volume from over 7.5 million gallons in 1995 to open-quotes zeroclose quotes gallons in two years. Changes instituted to date include. (1) Creation of a cross-discipline natural work team (NWT) responsible for radwaste improvements. (2) Enhanced walnut shell filter performance using a polymer filter aid. (3) Activated charcoal to reduce total organic carbon (TOC). (4) Improved operating practices based upon data review and trending. (5) Improved operability of radwaste equipment. Results are encouraging. The volume discharged January through May 1996, including a 39 day refueling outage, is 1.25 million gallons. Only one discharge has occurred since March 2. Historically, discharge volume during a similar five month period has exceeded 3 million gallons. No additional discharges are planned for 1996. Additional improvements are being actively evaluated. These include more effective radwaste train media, UV/O3 decomposition of TOC, adding non-precoated filters to the radwaste stream, reverse osmosis and real-time trending of inleakage volume and TOC and source term reduction

On giving radwaste management some status

International Nuclear Information System (INIS)

Dickson, H.W.; Walker, E.E.; Thiesing, J.W.

1987-01-01

Radwaste management is receiving ever increasing attention in the nuclear industry. The reasons for this include limited allocations for burial, increasing costs of handling and disposal, increased regulatory attention, and ALARA requirements. These issues have lead to an increasing awareness of the disadvantages of running a ''dirty'' plant and a variety of sophisticated systems have been proposed to fix the problem. Instead of these technologically difficult, and sometimes very expensive fixes, this paper focuses on several relatively simple ''low tech,'' and inexpensive solutions. Much can be done with organizational alternatives and assigned responsibilities and authorities to improve the situation. Applying controls on the front end of a radiological task rather than attempting to reduce the magnitude at the back end is the only realistic method for proper radwaste management

Non-power radwaste inventory, characteristics, storage and disposal plan in China

International Nuclear Information System (INIS)

Zhao Yamin; Guo Zede

1997-01-01

Based on the practical experience regarding L/ILW management, national management system and waste management principles have been established in China, and their key points are summarized as follows: The National Environmental Protection Agency (NEPA) is responsible for the centralized management of country's radwastes: unified planning; organizing coordinations; licensing; supervising and inspecting the activities of environment protection. The China national Nuclear Corporation (CNNC) takes the responsibility of research and development of radwaste management; siting, construction, and operating disposal facilities; technical support for making regulations, standards and guidelines. The units using radioactive isotopes and producing radwastes should take charge of temporal storage of their own wastes. L/ILW management principles: controlling waste generation amount as less as possible; collecting wastes according to their categories; reducing volume and immobilizing; reliably packaging; interim storage and disposal. This paper is limited to introduce the waste from nuclear technology application, its inventory, characteristics, interim storage and disposal plan. Information concerning L/ILW management, not limited nuclear technology application radwaste, can be found in references. 4 refs

The history of radwaste at Zion Station - its problems and solutions

International Nuclear Information System (INIS)

Bennett, K.J.

1982-01-01

Zion Station is located adjacent to Lake Michigan about 40 miles north of Chicago. The twin Zion units are four loop PWR's each rated at 1080 MWE with units 1 and 2 beginning commercial operation in 1973 and 1974 respectively. The radwaste system at Zion Station was designed in 1967 when radwaste operations of a nuclear power plant received little consideration. At Zion, the system was to be automated with occasional operator interface to pump down a tank when full or to solidify waste. The solidification equipment purchased was designed for the 40 year life of the station; due to the under estimation of the input to radwaste, this was not the case

Integrated radwaste treatment system lessons learned from 2 1/2 years of operation

International Nuclear Information System (INIS)

Baker, M.N.; Fussner, R.J.

1997-05-01

The Integrated Radwaste Treatment System (IRTS) at the West Valley Demonstration Project (WVDP) is a pretreatment scheme to reduce the amount of salts in the high-level radioactive waste (vitrification) stream. Following removal of cesium-137 (Cs-137) by ion-exchange in the Supernatant Treatment System (STS), the radioactive waste liquid is volume-reduced by evaporation. Trace amounts of Cs-137 in the resulting distillate are removed by ion-exchange, then the distillate is discharged to the existing plant water treatment system. The concentrated product, 37 to 41 percent solids by weight, is encapsulated in cement producing a stable, low-level waste form. The Integrated Radwaste Treatment System (IRTS) operated in this mode from May 1988 through November 1990, decontaminating 450,000 gallons of high-level waste liquid; evaporating and encapsulating the resulting concentrates into 10,393 71-gallon square drums. A number of process changes and variations from the original operating plan were required to increase the system flow rate and minimize waste volumes. This report provides a summary of work performed to operate the IRTS, including system descriptions, process highlights, and lessons learned

The economics of radwaste volume reduction strategies

International Nuclear Information System (INIS)

Giuffre, M.; Ensminger, D.; Nalbandian, J.; Naughton, M.

1984-01-01

A recently concluded EPRI study has generated much of the information needed by utilities when they consider the purchase of volume reduction equipment. This paper presents some of the study's results on volume reduction economics. The paper contains two types of results. The first is a detailed look at the economics of fourteen equipment options at a hypothetical reactor station. Costs were calculated with VRTECH, a radwaste economics computer program developed by TASC. This analysis illustrates the major points of the project conclusions. Second, the effects of the major assumptions used in the hypothetical case are examined. This analysis shows that the radwaste generation rate and the burial cost escalation rate are primary considerations when evaluating the benefit of each option

Waste management tasks of the Radwaste Collecting Centers of the Laender

International Nuclear Information System (INIS)

Dreisvogt, H.

1994-01-01

The paper outlines the manifold activities of the Radwaste Collecting Centers of the Laender. According to section 9 a, sub-sec. 3 of the Atomic Energy Act, the various Laender in Germany are obliged to establish such centers whose purpose among other things is to serve as interim storage site for radwaste accrued at medical, industrial, or research facilities. (HP) [de

The necessity for complex long-term predictions while designing systems for disposal of radwaste and role of those predictions in development of programs for environment protection

International Nuclear Information System (INIS)

Kedrovsky, O.L.; Schishitz, I.Y.

1993-01-01

Development of nuclear power in the future depends on solving two problems: creation of safe reactors; and reliable isolation of radwaste formed during all stages of the nuclear-fuel-cycle. The peculiarity of the second problem consists of the fact that considerable financial expenses are necessary for its decision. The range of the problem is characterized by the predictions of waste accumulation according to which summary activity of those materials (by the year 2000) will come up to 6 x 10 10 mCu. To successfully solve the radwaste isolation problem on the governmental level, it is necessary to formulate the corresponding regulation system. The main task of development of geological aspects of radwaste isolation consists of elimination of dangerous situations, reaching minimum damage effect, and development of a system for hydromonitoring, which includes blocks for search and standard prediction. The paper discusses the activities being carried out in Russia to solve the problems of radwaste disposal

Latest development in project site radwaste treatment facility (SRTF) Sanmen

International Nuclear Information System (INIS)

Mennicken, K.; Lohmann, P.

2015-01-01

Westinghouse Electric Germany GmbH (WEG) was successful in being awarded a contract as to the planning, delivery, installation and commissioning of radwaste treatment systems for the AP1000 units at Sanmen site, PR China. Operational low and intermediate level radioactive waste will be processed in the Site Radwaste Treatment Facility (SRTF). This paper explains the latest developments of the project, especially the experience with customer-hired Chinese planning partners, installation companies and Customer operating personnel. (authors)

Retrofit of radwaste solidification systems in Spain

International Nuclear Information System (INIS)

Rorcillo, R.; Virzi, E.

1983-01-01

In order to meet current Spanish engineering criteria as well as to provide for likely future Spanish Regulatory requirements, utilities committed to a major policy change in the preferred radwaste solidification media. In the early 1970's Spanish utilities, following the United States experience, purchased inexpensive solidification systems which used urea formaldehyde (UF) as the binding matrix. By the late 1970's the Spanish utilities, seeing the deterioration of the UF position and slow progress toward its improvement, unilaterally changed their binding matrix to cement. This paper illustrates the implementation of this change at the ASCO Nuclear Plant. The problems of layout modifications, shortened delivery schedule and criteria unique for Spain are addressed. Also presented is the operating experience acquired during the pre-operational start-up of the ASCO I Radwaste System

Principles and criteria for creation of a concept for national radwaste repository

International Nuclear Information System (INIS)

Milanov, M.; Strezov, A.; Kojuharov, D.

1993-01-01

General principles and criteria based on the international experience and requirements as well as on specific Bulgarian conditions are used in the creation of the Concept for Radwaste Repository Construction as a first stage of the Bulgarian nuclear programme. The Concept contains about 70 projects of common or more specific character. The Bulgarian territory is categorized and several prospective areas are selected as a final result of the analysis performed. A model for development of a National System for Radwaste Management is considered. The formation of a working group appointed by governmental authorities as a solution of the existing highly complex situation connected with the treatment and storage of radwaste in the country is proposed. 1 fig., 14 refs. (author)

Volume reduction and solidification of liquid and solid low-level radioactive waste

International Nuclear Information System (INIS)

May, J.R.

1979-01-01

This paper presents a brief background of the development of a method of radioactive waste volume reduction using a unique fluidized bed calciner/incinerator. The volume reduction system is capable of processing a variety of liquid chemical wastes, spent ion exchange resin beads, filter treatment sludges, contaminated lubricating oils, and miscellaneous combustible solids such as paper, rags, protective clothing, wood, etc. All of these wastes are processed in one chemical reaction vessel. Detailed process data is presented that shows the system is capable of reducing the total volume of disposable radioactive waste generated by light water reactors by a factor of 10. Equally important to reducing the volume of power reactor radwaste is the final form of the stored or disposable radwaste. This paper also presents process data related to a new radwaste solidification system, presently being developed, that is particularly suited for immobilizing the granular solids and ashes resulting from volume reduction by calcination and/or incineration

Stability Analysis of Buffer Storage Large Basket and Temporary Storage Pre-packaging Basket Used in the Type B Radwaste Process Area

International Nuclear Information System (INIS)

Kim, Sung Kyun; Lee, Kune Woo; Moon, Jei Kwon

2011-01-01

The ITER radioactive waste (radwaste) treatment and storage systems are currently being designed to manage Type B, Type A and dust radwastes generated during the ITER machine operation. The Type B management system is to be in the hot cell building basement with temporary storage and the modular type storages outside the hot cell building for the pre-packed Type B radwaste during the ITER operation of 20 years. In order to store Type B radwaste components in onsite storage, the waste treatment chain process for Type B radwastes was developed as follows. First, Type B full components filled in a large basket are imported from Tokamak to the hot cell basement and they are stored in the buffer storage before treatment. Second, they are cut properly with a laser cutting machine or band saw machine and sliced waste parts are filled in a pre-packaging basket. Third, the sampling of Type B components is performed and then the tritium removal treatment is done in an oven to remove tritium from the waste surface and then the sampling is performed again. Forth, the characterization is performed by using a gamma spectrometry. Fifth, the pre-packaging operation is done to ensure the final packaging of the radwaste. Sixth, the pre-packaging baskets are stored in the temporary storage for 6 months and then they are sent to the extension storage and stored until export to host country. One of issues in the waste treatment scheme is to analyze the stacking stability of a stack of large baskets and pre-packaging baskets in the storage system. The baseline plan is to stack the large baskets in two layers in the buffer storage and to stack the pre-packaging baskets in three layers in the temporary storage and extension storage. In this study, the stacking stability analysis for the buffer storage large basket and temporary storage pre-packaging basket was performed for various stack failure modes

Solid radwaste processing and conditioning. The SGN experience

International Nuclear Information System (INIS)

Tucoulat, D.; Tchemitcheff, E.

1993-01-01

Solid wastes are generated in the operation of the installations in France. These solid wastes display different levels of radioactivity. Some of them arising from research centres or reprocessing plants even contain relatively significant quantities of alpha-bearing radionuclides. In order to produce an ultimate waste package that satisfies the requirements set by safety authorities and the organizations in charge of final waste disposal in the concerned countries, solid waste conditioning takes place in a number of successive steps

Proceedings: 2001 ASME/EPRI Radwaste Workshop

International Nuclear Information System (INIS)

2001-01-01

Nuclear utilities continually evaluate methods to improve operations and reduce costs associated with radioactive waste management. The continuing deregulation process has increased the emphasis on this activity. The Annual ASME/EPRI Workshop facilitates this effort by communicating technology and management improvements throughout the industry. This workshop, restricted to utility radwaste professionals, also serves to communicate practical in-plant improvements with the opportunity to discuss them in detail

Deep-well injection of liquid radwaste in Russia - current status and operations

International Nuclear Information System (INIS)

Bradley, D.J.; Foley, M.G.; Rybal'chenko, A.I.

1995-01-01

This paper is submitted as part of a coordinated effort to present the topic of deep-well injection. The companion paper, open-quotes Deep-Well Injection of Liquid Radwaste in Russia - Background and Technical Basis,close quotes focuses on the original decision to inject liquid radwaste, the research behind that decision, and the design and construction of the injection facilities. The emphasis in this paper is on the current status and operation of the well facilities and the control systems used to minimize environmental impact

Proceedings: 2000 ASME/EPRI Radwaste Workshop

International Nuclear Information System (INIS)

2001-01-01

Nuclear utilities are continually evaluating methods to improve operations and reduce costs associated with radioactive waste management. The continuing deregulation process has added increased emphasis to this activity. The Annual ASME/EPRI Workshop facilitates this effort by communicating technological and managerial improvements throughout the industry. This workshop, restricted to utility radwaste professionals, also serves to communicate practical in-plant improvements with the opportunity to discuss them in detail

Bitumen and cement solidifications of LL and ML liquid radwaste. The SGN experience

International Nuclear Information System (INIS)

Tchemitcheff, E.; Roux, P.

1993-01-01

The presentation is focused on the thin-film evaporator technology and the experience gained in the field of the NPPs and research centers on radwaste conditioning. As early as 1970, SGN was licensed by the CEA for the bituminization of LL and ML radwaste. With the support of EDF and COGEMA, SGN has been performing in depth research on cement solidification of borated concentrates and ion exchange resins generated by reactors or reprocessing plant since 1983

Underground storage. Study of radwaste storage in deep geological formations: environmental protection

International Nuclear Information System (INIS)

Hoorelbeke, J.M.

1993-01-01

The purpose of the Agence nationale pour la gestion des dechets radioactifs (Andra) is to monitor the management methods and storage of radioactive waste produced in France. The agency has this undertaken a vast study program for the evaluation of the management conditions of long-life radwaste, which cannot be stored indefinitely in shallow-ground repositories. Underground laboratories are investigating the feasibility of a possible solution which is to store radwaste in a deep geological layer. However, there will be no decision on this type of storage before the year 2006. 7 figs

Why is the NORM Waste Included in to the Croatian RadWaste Strategy

International Nuclear Information System (INIS)

Prlic, I.; Suric Mihic, M.; Hajdinjak, M.

2016-01-01

Croatian RADWASTE Strategy uses modern approach according to EC Directive 2013/59/EURATOM and Croatian Act on Radiological and Nuclear Safety (Official Gazette 141/13, 39/15) linking the entire field of, till modern times non regulated industrial NORM wastes to properly regulated RADWastes. This approach has brought some obscurities to a professional radiation protection community because the fact that NORM will be treated together with the 'heavy' concept of nuclear and radioactive waste was not acceptable due to a historical division of those two fields of radioactivity. As NORM is still regarded as a slightly technologically blended radioactivity which is of no concern to be a risk for the population and RADWASTE is a 'murder' of any population in its vicinity, the need for terminology harmonization and scientifically correct public education was recognized. It is barely known that during the recent past some Croatian professionals did included the NORM sites into the state documents and reports to international regulatory bodies as pure RADWASTE sites. This fact produces immense regulatory difficulties even today. The one and only legal way to solve both, regulatory issues providing real radiation protection procedures during existing NORM waste site sanation and exempting sites to be reused for a legal public purpose (industrial or any other) was to incorporate the existing Croatian NORM sites into the RADWASTE Strategy and to solve all legal radioactivity burden issues during the governmental acceptance process. This approach is a new one in Croatian regulatory acquits and first responses from the stake holders and public involved are promising. The experience from the field and first responses to a concept of harmonizing the reuse approach of existing NORM waste sites from stake holders and partly from general public will be discussed.(author).

Radwaste management and spent fuel management in JAVYS

International Nuclear Information System (INIS)

Bozik, M.; Strazovec, R.

2010-01-01

In this work authors present radwaste management and spent fuel management in JAVYS, a.s. Processing of radioactive wastes (RAW) in the Bohunice Radioactive Waste Processing Center and surface storage of RAW in National RAW Repository as well as Interim Spent fuel storage in Jaslovske Bohunice are presented.

Radwaste Decision Support System

International Nuclear Information System (INIS)

Westrom, G.; Vance, J.N.; Gelhaus, F.E.

1989-01-01

The purpose of the Radwaste Decision Support System (RDSS) is to provide expert advice, analysis results and instructional material relative to the treatment, handling, transport and disposal of low-level radioactive waste produced in nuclear power plants. This functional specification addresses the following topics: Functions of the RDSS, Relationships and interfaces between the function, Development of the decisions and logic tree structures embodied in waste management, Elements of the database and the characteristics required to support the decision-making process, Specific User requirements for the RDSS, Development of the user interface, Basic software architecture, and Concepts for the RDSS usage including updating and maintenance

Low-level radwaste transportation in Taiwan

International Nuclear Information System (INIS)

Lo, L.F.; Huang, C.C.

1993-01-01

In the past ten years, 273 voyages have been made to ship radwaste produced by nuclear power plants and Institute of Nuclear Energy Research (INER). It more or less lowers the problem of insufficient storage space in Taiwan. Although all organizations followed various regulations to operate the transportation, ten events occurred in marine transport. However, they were ordinary incidents and neither released any radiation to contaminate the environment nor caused any casualty. (J.P.N.)

System analysis for radwaste management

International Nuclear Information System (INIS)

Lennemann, W.L.

1987-01-01

The most logical approach to evaluating radioactive waste management processes and their options is to consider radioactive waste management, handling, and disposal as a complete and complex system from the waste arisings to their disposition. The principal elements that should be considered or taken into account when making a decision involving one or more components of a radwaste management system essentially concern radiation doses or detriments- both radiological and industrial safety and both capital investments and operating costs. This paper discusses the system analysis of the low- and medium-level radioactive waste management

Safety Analysis of Spent Nuclear Fuel and Radwaste Facilities

International Nuclear Information System (INIS)

Poskas, P.; Ragaisis, V.

2001-01-01

The overview of the activities in the Laboratory of Heat Transfer in Nuclear Reactors related with the assessment of thermal, neutronic and radiation characteristics in spent nuclear fuel and radwaste facilities are performed. Activities related with decommissioning of Ignalina NPP are also reviewed. (author)

Data acquisition and monitoring of radwaste cementation plants

International Nuclear Information System (INIS)

Cable, A.S.; Lee, D.J.; Samways, J.; Weller, F.C.; Williams, J.R.A.

1988-03-01

This paper summarises the progress made in the two years to June 1987 on the DOE funded programme for Data acquisition and monitoring of Radwaste Cementation Plants. The results of the computer based data logging and processing system fitted to an in-drum mixing station, cement powder plant and sludge handling plant are reported. (author)

Radwaste knowledge management in cooperation with the IAEA

International Nuclear Information System (INIS)

Batyukhnova, O.G.; Dmitriev, S.A.; Ozhovan, M.I.; Drejs, Z.; )

2010-01-01

The authors report on the emerging of the term knowledge management, and the practice of accumulation and preservation of nuclear knowledge. They emphasize that in addition to collecting and keeping scientific knowledge and identification of practical skills, management of nuclear knowledge includes setting the priorities to take into account the expected departure of retiring experts, and creating the mechanisms for attracting and training future employees. Education and training in radwaste management, as in the entire nuclear sector, is of a multi-disciplinary nature. It requires understanding of subjects such as geology, civil construction, mining, hydrogeology, chemistry, geophysics, mechanics, computing, etc. Moreover, this field is plagued with difficulty of reaching scientific, technical and even social consensus. Creation of effective and efficiently-operating systems for maintaining and disseminating knowledge is a complex and labour-consuming task. The role of the IAEA in the field of radwaste knowledge management is underlined. The SUE SIA Radon Moscow' experience and practice in training specialists of various professions and levels (including regulatory personnel) are described [ru

Clay minerals in sandstone uranium deposits: radwaste applications

International Nuclear Information System (INIS)

Brookins, D.G.

1990-01-01

Clay minerals play an important role in the genesis of uranium deposits in sandstones. They incorporate the rate earths (REE), U, Sb, Th, Cs, Rb, Sr, Y, Ba, and even small amounts of chalcophiles. These minerals possess analog elements for many of the radwaste fission products as well as actinides and some actinide daughters. In sandstone uranium deposits, clay minerals are also associated with sulfide minerals, usually pyrite, and organic carbonaceous matter. The primary clay minerals are usually smectites, illites, chlorites and mixed layer varieties. The integrity of these clay minerals is demonstrated by their retention of formational-mineralization ages determined by Rb-Sr geochronologic investigation of the Grants Mineral Belt of the United States. The importance of the clay minerals as analog for parts of the multi-barrier concept in radwaste disposal is their ability to impede water penetration into - and movement of key elements out of uranium rich zones. The clay minerals further sorb and in other ways incorporate into their structures many fission products and actinide analogs from man-made nuclear wastes. 22 refs., 1 fig., 3 tabs

Human engineering considerations in the design of New Virginia Power Radwaste facilities

International Nuclear Information System (INIS)

Bankley, A.V.; Morris, L.L.; Lippard, D.W.

1988-01-01

Human engineering principles were considered by Virginia Power in the recent design of new radwaste facilities (NRFs) for both the Surry and North Anna power stations. Virginia Power recognized that the rigorous application of human engineering principles to the NRF design was essential to the ultimate success or failure of the facilities. Success of the NRF should not only be measured in the volume of radwaste processed but also by other factors such as (a) availability and maintainability of preferred equipment, (b) as-low-as-reasonably-achievable considerations, (c) actual release rates versus achievable release rates, and (d) flexibility to deal with varying circumstances. Each of these success criteria would suffer as the result of operator/human inefficiencies or error. Therefore, human engineering should be applied to the maximum practical extent to minimize such inefficiencies or errors. No method is ever going to ensure a perfectly human-engineered facility design. Virginia Power believes, however, that significant strides have been made in efforts to design and construct a successful radwaste processing facility, a facility where operating success rests with the ability of the human operators to perform their jobs in an efficient and reliable fashion

Modification of an existing radwaste facility to provide onsite low level waste storage

International Nuclear Information System (INIS)

Ault, G.M.; Reiss, J.F.; Commonwealth Edison Co., Chicago, IL)

1985-01-01

The decision of whether or not to install onsite storage capacity for low-level radioactive waste is dictated by individual utility circumstances. Commonwealth Edison has decided to construct facilities to store low-level radwaste onsite at each of their four operating nuclear stations, and they plan to have those facilities in operation by January, 1986. At Dresden, that onsite storage capacity is being provided by modifying an existing radwaste building which already has installed a remotely-operated precision-placement type crane. The purposes of this paper are to describe: (1) how Commonwealth Edison arrived at the decision to construct onsite storage facilities as a hedge against possible disruption of burial site availability in January, 1986; (2) why the desire to minimize the capital investment for this protection led to selection of an uncomplicated design for their ''standard'' facility and to the decision to modify an existing building at Dresden rather than construct a new one; and (3) what is being done to adapt the Dresden 1 Decontamination/Radwaste Building for extended onsite storage

Calibration method for a radwaste assay system

International Nuclear Information System (INIS)

Dulama, C.; Dobrin, R.; Toma, Al.; Paunoiu, C.

2004-01-01

A waste assay system entirely designed and manufactured in the Institute for Nuclear Research is used in radwaste treatment and conditioning stream to ensure compliance with national repository radiological requirements. Usually, waste assay systems are calibrated by using various experimental arrangements including calibration phantoms. The paper presents a comparative study concerning the efficiency calibration performed by shell source method and a semiempirical, computational method based on a Monte Carlo algorithm. (authors)

UK national consensus conference on radwaste management

International Nuclear Information System (INIS)

Craven-Howe, Andrew

2000-01-01

UK CEED organised a consensus conference to debate radwaste disposal. It lasted from 21-24 May 1999. Among the witnesses called to give evidence were UKAEA, BNFL, Nuclear Industries' Inspectorate, Department of the Environment, Transport and the Regions, Friends of the Earth and Greenpeace. The end result was a report produced by the panel of members of the public, recording their views and recommendations. Conclusions are presented. (author)

The costs assessment of the RENEL's programme for radwaste management

International Nuclear Information System (INIS)

Barariu, Gh.; Andreescu, N.

1995-01-01

The paper presents first economical assessment of the Radwaste Management Programme of the Romanian Electricity Authority - Nuclear Power Group (RENEL-GEN) until closing all foreseeable activities in the field of nuclear waste processing and disposal. (Author) 1 Tab., 7 Refs

Safety aspects of the design of a PWR gaseous radwaste treatment system using hydrogen recombiners

International Nuclear Information System (INIS)

Glibert, R.; Nuyt, G.; Herin, S.; Fossion, P.

1978-01-01

PWR Gaseous radwaste treatment system is essential for the reduction of impact on environment of the nuclear power plants. Decay tank system has been used for the retention of the radioactive gaseous fission products generated in the primary coolant. The use of a system combining decay tanks and hydrogen recombiner units is described in this paper. Accent is put on the safety aspects of this gaseous radwaste treatment facilitystudied by BN for a Belgian Power Plant. (author)

Radwaste management in Sweden

International Nuclear Information System (INIS)

Ahlstroem, P.E.; Ungermark, S.

1987-01-01

The waste management system planned for handling the radioactive residues from Sweden's 12 nuclear power units is based on the operation of all the units up to the year 2010 in accordance with Parliament's decision to abolish nuclear power by that time. The main strategy for handling spent nuclear fuel is direct disposal without reprocessing. In the design of the radwaste management system the following fundamental principles have been applied. Short-lived waste will be disposed of as soon as possible after it has been generated. Spent fuel will be intermediately stored for about 40 years before final disposal, thereby reducing heat generation in the repository. Other long-lived waste will be disposed of jointly with the final disposal of spent fuel. 3 figs., 1 tab

Use of robotics in a Radwaste treatment plant

International Nuclear Information System (INIS)

Leeks, C.W.E.

1991-01-01

A 762 Unimate Puma, clean room standard Robot has been installed and commissioned in the Radwaste Treatment Plant at the Winfrith Technology Centre. The robot interacts with a variety of purpose designed tools and proprietary welding equipment. It performs 13 dedicated tasks in the final closure and health physics operations, before the 500 litre waste drum is despatched from the plant. (author)

Performance assessment for Nuclear Power Plant Krsko intermediate and low-level rad-waste repository

International Nuclear Information System (INIS)

Jelavic, V.; Skanata, D.; Plecjas, I.

1990-01-01

Performance safety Assessment for NPP Krsko radwaste repository was performed (LLW/ILW). Shallow land and tunnel type concept were analyzed. Because it was based on two unknown referent sites, one for the shallow land concept and the other for the tunnel type, analysis was generic in nature. Scenario selecting process and consequence analysis were performed by using deterministic approach. Results for both concepts of disposal suggests that proposed NPP Krsko radwaste repository reference site and disposal technology will fully meet radiation limits imposed by the Yugoslav regulations and ICRP guidelines. (author)

Design and operation of the Surry Radwaste Facility

International Nuclear Information System (INIS)

Morris, L.L.; Halverson, W.C.

1993-01-01

In September 1991, Virginia Power started processing radioactive waste with a new Radwaste Facility at the Surry Power Station near Norfolk, Virginia. The Surry Radwaste Facility (SRF) was designed to process and store liquid waste, laundry waste, dry active waste, radioactive filters and spent ion-exchange resin. It also provides on-site decontamination services and a fully equipped hot machine shop. The NRC has recognized that the amount of planning and design, and the attention to detail, that was expended on the SRF Project in order to minimize personnel exposure and ensure efficient operation, is a licensee strength. Through its first year of operation, the facility has proven very successful. Using evaporation and demineralization, over 30 million liters of liquid have been released with no chemical impurities or detectable radioactivity (excluding tritium). Over 623,000 liters of concentrated boric acid waste liquid have been processed with the Bitumen Solidification System yielding 139,880 liters (660 drums) of low level Class A-Stable waste. Additional economic benefits will be realized as the effectiveness of the processing systems continues to improve due to increased operational experience and ergonomics

Review of decommissioning, spent fuel and radwaste management in Slovakia

International Nuclear Information System (INIS)

Jamrich, J.

2000-01-01

Two nuclear power plants with two WWER reactors are currently under operation in Jaslovske Bohunice and NPP A-1 is under decommissioning on the same site. At the second nuclear site in the Slovak Republic in Mochovce third nuclear power plant with two units is in operation. In accordance with the basic Slovak legislation (Act on Peaceful Utilisation of Nuclear Energy) defining the responsibilities, roles and authorities for all organisations involved in the decommissioning of nuclear installations Nuclear Regulatory Authority requires submission of conceptual decommissioning plans by the licensee. The term 'decommissioning' is used to describe the set of actions to be taken at the end of the useful life of a facility, in order to retire the facility from service while, simultaneously, ensuring proper protection of the workers, the general public and the environment. This set of activities is in principle comprised of planning and organisation of decommissioning inclusive strategy development, post-operational activities, implementation of decommissioning (physical and radiological characterisation, decontamination, dismantling and demolition, waste and spent fuel management), radiological, aspects, completion of decommissioning as well as ensuring of funding for these activities. Responsibility for nuclear installations decommissioning, radwaste and spent fuel, management in Slovakia is with a subsidiary of Slovak Electric called Nuclear Installations Decommissioning Radwaste and Spent Fuel Management (acronym SE VYZ), established on January 1, 1996. This paper provides description of an approach to planning of the NPP A-1 and NPPs with WWER reactors decommissioning, realisation of treatment, conditioning and disposal of radwaste, as well as spent fuel management in Slovakia. It takes into account that detail papers on all these issues will follow later during this meeting. (author)

Basic user guide for the radwaste treatment plant computer system

International Nuclear Information System (INIS)

Keel, A.

1990-07-01

This guide has been produced as an aid to using the Radwaste Treatment Plant computer system. It is designed to help new users to use the database menu system. Some of the forms can be used in ways different from those explained and more complex queries can be performed. (UK)

Development of regulatory and legal framework for spent fuel and radwaste management

International Nuclear Information System (INIS)

Bezzubtsev, V.S.

2012-01-01

The Basics of National Policy in Nuclear and Radiation Safety assurance in the Russian Federation define the principles and objectives of nuclear and radiation safety of nuclear facilities during all stages of their life cycle. Russia's National Report at the Fourth Review Meeting of Contracting Parties to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management reflected the organizational as well as legal and regulatory changes that have taken place over past three years. Amendments recently made to the Russian Nuclear Energy Law as well as the Law on Radwaste Management adopted in 2011 are discussed. Federal norms and regulations in the field of spent fuel and radwaste management are also presented. Organizational and legal reforms related to state safety regulation are described [ru

Development of the Computer Code to Determine an Individual Radionuclides in the Rad-wastes Container for Ulchin Units 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Kang, D.W.; Chi, J.H.; Goh, E.O. [Korea Electric Power Research Institute, Taejon (Korea)

2001-07-01

A computer program, RASSAY was developed to evaluate accurately the activities of various nuclides in the rad-waste container for Ulchin units 3 and 4. This is the final report of the project, {sup D}evelopment of the Computer Code to Determine an Individual Radionuclides in the Rad-wastes Container for Ulchin Units 3 and 4 and includes the followings; 1) Structure of the computer code, RASSAY 2) An example of surface dose calculation by computer simulation using MCNP code 3) Methods of sampling and activity measurement of various Rad-wastes. (author). 21 refs., 35 figs., 6 tabs.

A master plan for the radwaste management

International Nuclear Information System (INIS)

Kim, Y.E.; Lee, S.H.; Lee, C.K.; Moon, S.H.; Sung, R.J.; Sung, K.W.

1983-01-01

The accumulated total amount of low-level radioactive wastes to be produced from operating power reactors and nuclear installations up until the year 2007 is estimated to 900,000 drum(approximately 200,000M 3 ). An effective master plan for the safe disposal of the wastes is necessary. Among many different disposal methods available for low-and medium-level radwastes, the engineered trench approach was chosen by an extensive feasibility study as the optimum method for Korea. Site selection, construction and commissioning of such a disposal facility are presumed to take two and a half years, beginning in July 1983. The total cost in opening the site and the unit disposal cost per drum were estimated to be 11 billion won and 40,000 won, respectively. An agency(KORDA) managing the operation of the disposal site is recommended to be established by 1987, assuming that the agency's economic feasibility can be justified by that time. When the disposal site is commissioned, a regulatory guide for ground disposal will be available, and supporting R and D work on the disposal site will be complete. Studies on the technology of radwaste treatment will continue through this period. For the longer term, staff training and future planning have been undertaken to ensure that a master plan, which can be expected to be used as a guideline for disposal of all radioactive waste arising, is fully adequate. (Author)

Radwaste inventories and projections: an overview

International Nuclear Information System (INIS)

Notz, K.J.

1982-07-01

The Integrated Data Base program was set up to provide fully integrated and reconciled inventories, characteristics, and projections for spent nuclear fuel and all categories of radioactive waste. Eight summary papers, six of which were presented at an ANS special session in Los Angeles in June 1982, are included in this report: data base needs and functions: national planning; integrated data base for spent fuel and radwaste: inventories; integrated data base projections; RAWSYM: radioactive waste management system; NWTS program waste projection data needs; low-level waste management data base system; waste sludge composition at the Savannah River Plant; and summary of characteristics of transuranic waste found at DOE sites

Characterization of Carbamazepine-Loaded Solid Lipid ...

African Journals Online (AJOL)

loaded solid lipid nanoparticles by RESS as well as their characterization has been achieved in this study. Keywords: Rapid expansion of supercritical fluid, Stearic acid, Solid lipid nanoparticles, Carbamazepine, Co-precipitation ...

The chemical behaviour of iodine-129 in the process of radwaste conditioning

International Nuclear Information System (INIS)

Schon, T.

1993-11-01

During radwaste reprocessing, elemental I-129 may almost completely be transferred to the dissolver off-gas stream. The AC 6120 adsorbent, consisting of high-heated, amorphous silicic acid impregnated with silver nitrate, proved to be particularly efficient for removing the iodine from the off-gas. In a gas-solid reaction, the elemental iodine is converted into solid silver iodide and silver iodate. The reaction's stoichiometry depends on the loading temperature, with temperatures between 30 and 80 C resulting in a ratio of five between the reaction products of AgI and AgIO 3 , while with temperatures higher than that, up to 150 C, the ratio is three. For assessing the acceptability of the iodine-bearing AC 6120 as a waste product to be emplaced in a salt rock repository, the ratio of the reaction products is one of the main criteria. The products solubility and its complexation reactions with chloride-bearing brines are two other important criteria, especially with a view to the not completely hypothetical accident type of 'water ingress into the salt cavern'. Leaching experiments have shown that in this event, between 30 and over 60% of the waste product's iodine inventory would be leached out within only seven days. Thus AC 6120 is not a candidate adsorbent for immobilization of iodine 129 in a waste product. (orig./HP) [de

Integrated radwaste treatment system. Final report

International Nuclear Information System (INIS)

Baker, M.N.; Houston, H.M.

1997-10-01

In May 1988, the West Valley Demonstration Project (WVDP) began pretreating liquid high-level radioactive waste (HLW). This HLW was produced during spent nuclear fuel reprocessing operations that took place at the Western New York Nuclear Service Center from 1966 to 1972. Original reprocessing operations used plutonium/uranium extraction (PUREX) and thorium extraction (THOREX) processes to recover usable isotopes from spent nuclear fuel. The PUREX process produced a nitric acid-based waste stream, which was neutralized by adding sodium hydroxide to it. About two million liters of alkaline liquid HLW produced from PUREX neutralization were stored in an underground carbon steel tank identified as Tank 8D-2. The THOREX process, which was used to reprocess one core of mixed uranium-thorium fuel, resulted in about 31,000 liters of acidic waste. This acidic HLW was stored in an underground stainless steel tank identified as Tank 8D-4. Pretreatment of the HLW was carried out using the Integrated Radwaste Treatment System (IRTS), from May 1988 until May 1995. This system was designed to decontaminate the liquid HLW, remove salts from it, and encapsulate the resulting waste into a cement waste form that achieved US Nuclear Regulatory Commission (NRC) criteria for low-level waste (LLW) storage and disposal. A thorough discussion of IRTS operations, including all systems, subsystems, and components, is presented in US Department of Energy (DOE) Topical Report (DOE/NE/44139-68), Integrated Radwaste Treatment System Lessons Learned from 2 1/2 Years of Operation. This document also presents a detailed discussion of lessons learned during the first 2 1/2 years of IRTS operation. This report provides a general discussion of all phases of IRTS operation, and presents additional lessons learned during seven years of IRTS operation

Onsite storage facility for low level radwaste

International Nuclear Information System (INIS)

Maxwell, M.G.

1984-01-01

The Tennessee Valley Authority (TVA) has designed and constructed an onsite storage facility for low level radwaste (LLRW) at its Browns Ferry Nuclear Plant in northern Alabama. The paper addresses the function of this facility and provides a complete description of the reinforced concrete storage modules which are the principal structural elements of the facility. The loads and loading combinations for the design of the storage modules are defined to include the foundation design parameters. Other aspects of the modules that are addressed are; the structural roof elements that provide access to the modules, shielding requirements for the LLRW, and tornado missile considerations

How utilities respond to radwaste needs

International Nuclear Information System (INIS)

Strauss, S.D.

1987-01-01

Slow progress is being made toward regionalization of waste disposal, some states working toward regional compacts while others choose to go it alone. More promising is the reduction of radwaste volumes discharged from nuclear stations. More and more utilities are contracting with private companies for LLW processing. While such services are provided predominantly by mobile units at plant sites, one fixed installation already offers processing of dry waste and two others await final regulatory approval. Both developments are detailed. This article also includes an analysis of the design, performances comparison between slagging combustors (SC) and the FBC boiler. Comparisons are also made for SC technology to FBC for 250-MW unit and of utility-unit conversion costs

Radwaste reduction through use of condensate non-precoat filters at Perry Nuclear Power Plant

International Nuclear Information System (INIS)

Hartman, J.L.

1996-01-01

The concept of non-precoat filtration to remove iron oxide without generating traditional resin and fiber precoat material, which is expensive to dispose of as radwaste, is rapidly becoming a trend of the 90's. In 1991, in response to escalating radwaste disposal costs, Perry Nuclear Power Plant was the first BWR to install non-precoat filters (septa) on a full scale basis in a Condensate System. To date, non-precoat septa from three vendors; including Memtec Power Generation have been installed and operated at Perry. It is important that other utilities considering this technology be given as much open-quotes real lifeclose quotes operational data as possible. This paper presents the data from three different companies and provides recommendations for consideration

Characterization of polymer-modified cement as a solidification agent for the radwaste

International Nuclear Information System (INIS)

Ji, Young-Yong; Kwak, Kyung-Kil; Hong, Dae-Seok; Ryu, Woo-Seog

2012-01-01

Highlights: ► Polymer-modified cement (PMC) by modification with water-based resins. ► Determination of the optimized polymer content. ► Evaluation of the improved chemical resistance of the PMC. ► Decrease of the amount of ions released into the demineralized water. ► Highly improved property for the nuclide diffusivity at the Co-60. - Abstract: Polymer-modified cement can be produced by partially replacing cement hydrate binders in ordinary Portland cement with polymeric compounds. It is known that the addition of the polymer to the cement paste leads to improved quality, which would be expected to have a high chemical resistance. In order to investigate the application as a solidification agent for the radwaste, polymer-modified cement specimens, by modification with water-based resins, were prepared according to the polymer content from 0% to 30%. The optimized polymer content in the cement pastes was then determined through the compressive strength and the porosity test. Finally, the improved chemical resistance of the polymer-modified cement with the optimized polymer content was evaluated by the thermal cycling, the immersion, and the leaching tests. From the test results, the amount of ions released into the water showed lower values of about 20% at the polymer-modified cement. Especially, a highly improved nuclide diffusivity of Co-60 was observed in the polymer-modified cement.

Safety assessment for radwaste disposal in Korea: Pt. 1

International Nuclear Information System (INIS)

Suh, I.S.; Park, H.H.; Han, K.W.; Hahn, P.S.

1986-01-01

A simplified safety analysis code has been established in order to provide a basic methodology for the preliminary selection of a disposal method. The disposal type selection is prerequisite to meet the requirements of low and intermediate level radwaste management program in Korea. The code covers resaturation and leaching, migration through fracture-porous media transport such that the rock cavern disposal option can be evaluated compared with that of shallow land burial

Survey and evaluation of handling and disposing of solid low-level nuclear fuel cycle wastes

International Nuclear Information System (INIS)

Mullarkey, T.B.; Jentz, T.L.; Connelly, J.M.; Kane, J.P.

1976-10-01

The report identifies the types and quantities of low-level solid radwaste for each portion of the nuclear fuel cycle, based on operating experiences at existing sites and design information for future installations. These facts are used to evaluate reference 1000 MWe reactor plants in terms of solid radwaste generation. The effect of waste volumes on disposal methods and land usage has also been determined, based on projections of nuclear power growth through the year 2000. The relative advantages of volume reduction alternatives are included. Major conclusions are drawn concerning available land burial space, light water reactors and fuel fabrication and reprocessing facilities. Study was conducted under the direction of an industry task force and the National Environmental Studies Project, a technical program of the Atomic Industrial Forum. Data was obtained from questionnaires sent to 8 fuel fabrication facilities, 39 reactor sites and 6 commercial waste disposal sites. Additional data were gathered from interviews with architect engineering firms, site visits, contacts with regulatory agencies and published literature

Cross flow filtration for radwaste applications reverse osmosis demonstration case studies

International Nuclear Information System (INIS)

Malkmus, D.

1995-01-01

Today's radwaste economic and regulatory scenarios signify the importance in the improvement of operational practices to reduce generator liabilities. This action is largely due to the rising cost dealing with burial sites and the imposed waste volume restriction. To control the economical burdens associated with waste burial and to comply with stricter environmental regulations, NPP's are attempting to modify their radwaste system(s) design and operating philosophy by placing a major emphasis on waste volume reduction and processing techniques. The utilization of reverse osmosis technology as a means for treatment of process and wastewater streams in the nuclear power industry has been investigated for many years. This paper will outline reverse osmosis theory and highlight performance data for process and waste stream purification applications. Case studies performed at 5 nuclear plants have been outlined. The demonstrations were performed on a widely variety of process stream for both a PWR and BWR application. The data provided by the pilot systems, the equipment design, and the economical impact a reverse osmosis unit will have on producing treated (high purity) are as follows

Analytical methods of radwaste characterization

International Nuclear Information System (INIS)

Garcia, C.M.

1994-10-01

In view of the need to carry out more extensive studies on the design of newly proposed methods for the treatment of radioactive wastes collected at PNRI, this study is aimed to provide a guide in the characterization of wastes which is a preparatory step for a well-planned waste processing. (auth.). 8 refs

Sampling of charged liquid radwaste stored in large tanks

International Nuclear Information System (INIS)

Tchemitcheff, E.; Domage, M.; Bernard-Bruls, X.

1995-01-01

The final safe disposal of radwaste, in France and elsewhere, entails, for liquid effluents, their conversion to a stable solid form, hence implying their conditioning. The production of conditioned waste with the requisite quality, traceability of the characteristics of the packages produced, and safe operation of the conditioning processes, implies at least the accurate knowledge of the chemical and radiochemical properties of the effluents concerned. The problem in sampling the normally charged effluents is aggravated for effluents that have been stored for several years in very large tanks, without stirring and retrieval systems. In 1992, SGN was asked by Cogema to study the retrieval and conditioning of LL/ML chemical sludge and spent ion-exchange resins produced in the operation of the UP2 400 plant at La Hague, and stored temporarily in rectangular silos and tanks. The sampling aspect was crucial for validating the inventories, identifying the problems liable to arise in the aging of the effluents, dimensioning the retrieval systems and checking the transferability and compatibility with the downstream conditioning process. Two innovative self-contained systems were developed and built for sampling operations, positioned above the tanks concerned. Both systems have been operated in active conditions and have proved totally satisfactory for taking representative samples. Today SGN can propose industrially proven overall solutions, adaptable to the various constraints of many spent fuel cycle operators

The remote methods for radwaste and SNF control

International Nuclear Information System (INIS)

Ivanov, O; Stepanov, V; Danilovich, A; Potapov, V

2017-01-01

With the examples of developments carried out in the Kurchatov Institute and by the world leaders in the field the presentation considers the devices and methods to obtain remotely information on the distribution of radioactivity in radwaste and SNF. It describes the different types of light portable gamma cameras. The application of scanning spectrometric systems is considers also. The methods of recording UV radiation for detection of alpha contamination with the luminescence of air are presented. We discuss the scope and tasks that can be solved using remote and non-destructive methods. (paper)

Maximized liquid radwaste volume reduction through a total integrated process: A new technology success story

International Nuclear Information System (INIS)

Rae, G.A.

1996-01-01

A fundamental nuclear industry goal is the minimization of the generation of radioactive waste. This goal has been dramatically reinforced over the past few years due to the spiraling increased costs of both commercial and DOE disposal. To assist in meeting these goals and reducing the industry's costs, NUKEM initiated a new technology program to maximize the reduction of liquid radwaste through the use of a systematic approach or TIPS (Total Integrated Process System). This concept evaluates the total life cycle of various technologies in a combination that results in the final waste form being minimized to the pure solids content of the waste stream. Additionally, it allows for a final waste form that maximizes the utilization of the waste package and is conditioned to be readily acceptable to additional processing to meet new waste form requirements at future disposal sites, should interim storage of the waste be required. The TIPS, although first introduced at commercial facilities, has broad applications for DOE's liquid waste streams

New perspectives for visual characterization of pharmaceutical solids

DEFF Research Database (Denmark)

Laitinen, Niklas; Antikainen, Osmo; Rantanen, Jukka

2004-01-01

The utilization of descriptive image information in pharmaceutical powder technology is rather limited. Consequently, the development of this discipline is a challenge within physical characterization of pharmaceutical solids. The aim of this study was to develop and evaluate an inventive visual...... in particle size analysis also enabling the evaluation of the further product quality in the end of the granulation process. The idea of characterization of bulk surface images opens new perspectives for characterization of pharmaceutical solids....

Impact of LWR decontamination on radwaste systems

International Nuclear Information System (INIS)

Perrigo, L.D.; Divine, J.R.

1979-01-01

Increased radiation levels around certain reactors in the United States and accompanying increases in personnel exposures are causing a reexamination of options available to utilities to continue operation. One of the options is decontamination of the primary system to reduce radiation levels. The Battelle-Northwest study of decontamination and its impact on radwaste systems has been directed towards existing reactors and allied systems as they are employed during their operational lifetimes. Decommissioning and cleanup during such work are not within the scope of this project although certain processes and waste systems might be similar. Rupture debris cleanup represents a special situation that requires different design features and concepts and it is not a part of this study

The strategy of radwaste management in Slovenia

International Nuclear Information System (INIS)

Loose, A.; Babsek, B.; Jeran, M.

1994-01-01

This paper's intention is to show the present situation and future activities of the Agency for radwaste management. It was established by the slovene government to provide the strategy for a safe management of radioactive waste. The safety is the main concern of the Agency, since the situation in Slovenia is quite complex as it is a small country with a limited number of suitable locations and a strong public opposition towards anything connected with nuclear power generation or radioactivity in general. The emphasis of the Agency's activities at the moment is siting and technology selection for low level waste and intermediate level waste repository as well as solutions on interim storage of high level waste

The application of polyelectrolytes to improve liquid radwaste treatment system radionuclide removal efficiency

International Nuclear Information System (INIS)

Homyk, W.A.; Spall, M.J.; Vance, J.N.

1990-01-01

At nuclear plants, miscellaneous waste water treated in the liquid radwaste processing system contains a significant fraction of suspended particulate materials ranging in size from a few microns down to the submicron region. The fewer particles that typically exist as colloids are generally negatively charged by virtue of inorganic and organic anions absorbed onto the particle surfaces. Because many of the radionuclides exist as colloids and resist agglomeration and settling they are not easily removed by mechanical filtration or ion exchange processes. The colloidal materials will easily pass through most filters with conventional pore size ratings and through most ion exchange media. This leads to poor decontamination Factors (dFs) and higher radionuclide releases to the environment. A laboratory-scale testing program was conducted at Indian Point Unit No. 2 to determine the effectiveness of the use of organic polyelectrolytes to destabilize colloidal suspensions in liquid radwaste. Destabilizing colloidal suspensions will improve the removal efficiencies of the suspended material by typical filtration and ion exchange processes. The increased removal efficiencies will provide increased dFs in the liquid radwaste treatment system. The testing focused on identifying the specific organic polyelectrolytes and the associated dosages which would be effective in destabilizing the colloidal suspensions on actual waste water samples. The testing also examined the filtration characteristics of the water source to determine filter parameters such as: body feed material, body feed dosages, specific flow rates, etc., which would provide the basis for the design of filtration systems for these applications. The testing effort and the major conclusions from this investigation are given. 4 refs., 8 figs., 2 tabs

Solid electrolytes general principles, characterization, materials, applications

CERN Document Server

Hagenmuller, Paul

1978-01-01

Solid Electrolytes: General Principles, Characterization, Materials, Applications presents specific theories and experimental methods in the field of superionic conductors. It discusses that high ionic conductivity in solids requires specific structural and energetic conditions. It addresses the problems involved in the study and use of solid electrolytes. Some of the topics covered in the book are the introduction to the theory of solid electrolytes; macroscopic evidence for liquid nature; structural models; kinetic models; crystal structures and fast ionic conduction; interstitial motion in

Characterization of carbonaceous solids by oxygen chemisorption

Energy Technology Data Exchange (ETDEWEB)

Furimsky, E.; Palmer, A.; Duguay, D.G.; McConnell, D.G.; Henson, D.E.

1988-06-01

Oxygen chemisorption of high and low carbon carbonaceous solids was measured in an electro-microbalance at 200 degrees C in air. A linear correlation between the amount of chemisorbed oxygen and H/C ratio as well as aromaticity was established for the high carbon solids. For the low carbon solids a linear correlation was established between the amount of chemisorbed oxygen and the content of organic matter. Experimental observations are discussed in terms of structural aspects of the solids. Oxygen chemisorption is a suitable technique for a rapid characterization of carbonaceous solids including coal. 15 refs., 7 figs., 3 tabs.

Evaluation of the processes used for the treatment of the hospitable radwastes containing Cs-137

International Nuclear Information System (INIS)

Peres, S.S.; Silva, J.J.G.

1988-01-01

This work presents a resume of results obtained in the treatment of radwastes containing Cs-137 from HNMD (Hospital Naval Marcilio Dias) and IRD (Instituto de Radioprotecao e Dosimetria), due to the radiological accident of Goiania. (author) [pt

Characterization of urban solid waste in Chihuahua, Mexico

International Nuclear Information System (INIS)

Gomez, Guadalupe; Meneses, Montserrat; Ballinas, Lourdes; Castells, Francesc

2008-01-01

The characterization of urban solid waste generation is fundamental for adequate decision making in the management strategy of urban solid waste in a city. The objective of this study is to characterize the waste generated in the households of Chihuahua city, and to compare the results obtained in areas of the city with three different socioeconomic levels. In order to identify the different socioeconomic trends in waste generation and characterization, 560 samples of solid waste were collected during 1 week from 80 households in Chihuahua and were hand sorted and classified into 15 weighted fractions. The average waste generation in Chihuahua calculated in this study was 0.676 kg per capita per day in April 2006. The main fractions were: organic (48%), paper (16%) and plastic (12%). Results show an increased waste generation associated with the socioeconomic level. The characterization in amount and composition of urban waste is the first step needed for the successful implementation of an integral waste management system

Characterization of urban solid waste in Chihuahua, Mexico.

Science.gov (United States)

Gomez, Guadalupe; Meneses, Montserrat; Ballinas, Lourdes; Castells, Francesc

2008-12-01

The characterization of urban solid waste generation is fundamental for adequate decision making in the management strategy of urban solid waste in a city. The objective of this study is to characterize the waste generated in the households of Chihuahua city, and to compare the results obtained in areas of the city with three different socioeconomic levels. In order to identify the different socioeconomic trends in waste generation and characterization, 560 samples of solid waste were collected during 1 week from 80 households in Chihuahua and were hand sorted and classified into 15 weighted fractions. The average waste generation in Chihuahua calculated in this study was 0.676 kg per capita per day in April 2006. The main fractions were: organic (48%), paper (16%) and plastic (12%). Results show an increased waste generation associated with the socioeconomic level. The characterization in amount and composition of urban waste is the first step needed for the successful implementation of an integral waste management system.

Preliminary site investigation for LL and IL radwaste disposal for Qinshan NPP

International Nuclear Information System (INIS)

Huang Yawen; Chen Zhangru

1993-01-01

With the purpose of selecting a disposal site for the low- and intermediate-level radwastes arising from Qinshan NPP, site investigations were carried out in several districts of Zhejiang Province. Investigation objectives included the circumstances of geology, hydrogeology, environmental ecology, and social economy. On the basis of collected data, five possible sites were recommended for policy-making reference and further investigation

Evaluation and standardisation of fast analytical techniques for destructive radwaste control

International Nuclear Information System (INIS)

De Simone, A.; Troiani, F.

2001-01-01

The document describes the work programme carried out by the Laboratorio Nazionale per la 'Caratterizzazione dei Refit Radioattivi', in the frame of the European research project Destructive Radwaste Control. The main tasks of the research work were the evaluation of fast sample pre-treatment procedures and the development of chromatographic methods coupled to fast nuclide detection by Liquid Scintillation Counting. In order to test the High Performance Ion Chromatograph (HPIC) coupled to the Liquid Scintillation Counter (LSC) on high salt content solutions, synthetic cement solutions have been prepared and spiked with several β-emitters hard to be measured with non-destructive analyses, along with other radionuclides important for the determination of the radiological inventory in radwastes. As the validation tests for the new analytical methods involved the manipulation of radioactive solutions, a remote area for HPIC-LSC apparatus has been designed and performed, in order to operate in safe conditions. According to the research programme, fast analytical methods for the chemical separation and radionuclide detection of the radioactive elements of interest, have been developed and qualified. From the results of the work, some protocols of analysis have been defined: they contain all information about operative conditions for HPIC-LSC apparatus, field of applicability, chemical and radioactive detection limits [it

Strategy for the disposal of low- and intermediate-level radwastes in Canada

International Nuclear Information System (INIS)

Dixon, D.F.

The intent of the strategy described is to optimize both safety and cost of disposal by classifying waste segments according to hazardous lifetime and to match these to two or more selected disposl concepts graded according to containment and isolation capabilities. The bulk of low- and intermediate-level radwastes arising in Canada are a relatively short-lived hazard requiring isolation for no more than a few hundred years. Burial of this segment at tens-of-metres in quatenary deposits has been proposed as a concept worth evaluating. It is expected that part of the low- and intermediate-level radwastes will be potentially hazardous for geological time periods. Once methods of isolation for long-lived fuel wastes have been identified, these could be utilized for wastes requiring isolation for longer than a few hundred years. Disposal of a hard-rock vault is being evaluated as a reference concept and costs are presented. It is proposed that waste classification may consider more than two categories to further reduce costs and to better accommodate the radiological character of wastes. The overall disposal strategy should be flexible enough to account for present waste management practices and anticipated future needs

Simulation of Thermal, Neutronic and Radiation Characteristics in Spent Nuclear Fuel and Radwaste Facilities

International Nuclear Information System (INIS)

Poskas, P.; Bartkus, G.

1999-01-01

The overview of the activities in the Division of Thermo hydro-mechanics related with the assessment of thermal, neutronic and radiation characteristics in spent nuclear fuel and radwaste facilities are performed. Also some new data about radiation characteristics of the RBMK-1500 spent nuclear fuel are presented. (author)

Melting decontamination and free release of metal waste at Studsvik RadWaste Co. in Sweden

International Nuclear Information System (INIS)

Kawatsuma, Shinji; Ishikawa, Keiji; Matsubara, Tatsuo; Donomae, Yasushi; Imagawa, Yasuhiro

2006-01-01

The Studsvik RadWaste Co. in Sweden was visited on August 29, 2005 by members of radioactive waste and decommissioning subgroup of central safety task force in old Japan Nuclear Cycle Development Institute as 'Overseas investigation'. The visit afforded us the chance to survey melting and decontaminating of metallic waste in this company and the status of free release. Domestic and foreign radioactive metallic waste is accepted in this company after 1987, and the majority of the decontaminated waste have been released freely. In the background of the big effort of this company and the strong leadership of the regulator (SSI: Swedish radiation protection Authority), prosperous operation was able to have been achieved. This survey was done based on 'Free release of radioactive metallic waste in Europe: the free release experience for 17 years at Studsvik RadWaste Co. in Sweden' by Dr. J. Lorenzen. (author)

Immobilization and leaching mechanisms of radwaste in cement-based matrices

International Nuclear Information System (INIS)

Glasser, F.P.; Rahman, A.A.; Crawford, R.W.; McCullough, C.E.; Angus, M.J.

1983-01-01

The effect of potential sorbers including silicas, titania, calcined kaolin, zirconium phosphate and two crystalline calcium silicates, tobermorite and xonotlite, have been used to improve the Cs-retention capacity of cement-based systems. The analysis of the pore fluid compositions of equilibrated cement-radwaste composites provides evidence concerning the leach mechanisms whereby Cs is removed. The reactions occurring between cement and clinoptilolite are elucidated and results of kinetic studies presented. Simulate Magnox waste is shown to react with cement, leading to a carbonate exchange. (author)

Volume reduction, a safer and cheaper way of radwaste management

International Nuclear Information System (INIS)

Mergan, L.M.; Cordier, J.P.; Storrer, J.A.

1979-01-01

Development of 'Volume Reduction' has demonstrated that it is a safer and cheaper radwaste management method. Safer, because of several advantages: decrease of solidified product volume, satisfactory product properties, absence of free water, better control of process parameters, increased encapsulation efficiency ... The corresponding impact on the waste management costs, results in important savings on different factors, as well as regards the operational costs as the investment expenses. Economy in the range of BF 35.000 per m 3 of incoming waste is achievable. The main volume reduction techniques readily available are briefly reviewed

Strategic review on management and disposal of low- and intermediate-level solid radwastes

International Nuclear Information System (INIS)

Li Xuequn

1993-01-01

An overview on the actual status of solid low- and intermediate-level wastes (L/ILW) management in China is described. Some of the main problems at present are analysed. The strategies on management and disposal of the wastes are discussed in light of systematology. A large amount of solid L/ILW and distilled residual solution to be solidified have been accumulated during the past 30 years development of nuclear industry in China. These wastes, containing fission products, activated products, and uranium and transuranium elements respectively, mainly come from nuclear reactors, spent fuel reprocessing plants, and nuclear fuel fabrication plants. In the century, solid L/ILW and solidified wastes are produced mainly by nuclear industry; but in the next century, solid wastes will be steadily produced mainly from nuclear power plants

Experimental investigation of factors affecting the control of redox conditions within a radwaste repository

International Nuclear Information System (INIS)

Guppy, R.M.; Atkinson, A.

1991-04-01

The maximum aqueous concentration of multivalent radioelements in a radwaste repository can be estimated from the expected Eh (the oxidising or reducing tendency of the solution) and pH of the aqueous phase in the repository so long as equilibrium between all oxidising and reducing species can be guaranteed. The objective of the work reported here was to ascertain whether any significant departures from redox equilibrium are likely to arise. Technetium (VII) species were exposed under anaerobic conditions to concentrations of ferrous, hydrogen sulphide and thiosulphate species likely to be present in a repository environment to establish which species are capable of reducing aqueous Tc(VII) to a less soluble Tc(IV) solid compound. Potential catalytic solid phases and phases capable of electron exchange were also exposed to Tc(VII) species under anaerobic, aerobic and hydrogen atmospheres. We have not been able to demonstrate conclusively that mutual equilibrium was attained between technetium and iron redox couples, nor that the apparent solubility of technetium was that expected from the resulting Eh and pH of the solution, although some technetium was removed from solution. Hydrogen did not reduce Tc(VII) within the timescale of the experiments and no catalytic effects by haematite or a cementitious backfill grout for reductions involving hydrogen were observable. Magnetite removed some technetium from solution, apparently by surface reaction, under inert (argon) and reducing (hydrogen) atmospheres. Sulphides, and to a lesser extent thiosulphates, will reduce the solubility of technetium to a very low level. (author)

A special issue on preparation and characterization of solids

Czech Academy of Sciences Publication Activity Database

Luňáček, J.; Nitsch, Karel; Kožíšek, Zdeněk

2013-01-01

Roč. 5, č. 6 (2013), s. 507-508 ISSN 2164-6627 Institutional support: RVO:68378271 Keywords : characterization of solids Subject RIV: BM - Solid Matter Physics ; Magnetism http://www.aspbs.com/asem.html#v5n6

Radwaste '86: proceedings volume

International Nuclear Information System (INIS)

Ainslie, L.C.

1986-12-01

The volume contains all the papers presented at the above Conference, which was held in Cape Town, South Africa from 7 to 12 September 1986. A total of 55 contributions cover the full spectrum of the theme of the Conference, which was subdivided into four sessions. Conditioning, treatment and management of radioactive waste: 12 papers reporting on experiences in various countries, as well as specialist topics such as the extraction of radioactive contaminants from reactor pool water. Containment, safe handling and long-term integrity of ILLW packages: 2 papers dealing with cask design. Transport and storage of radwaste and spent fuel: 7 papers ranging from broad overviews to specific operations in different parts of the world. Radioactive waste disposal and environmental impact: 32 papers covering topics from site selection, design and operation, to modelling and monitoring studies. South Africa's Vaalputs radioactive waste disposal facility is comprehensively described. The volume is a useful reference for anyone interested in the disposal of radioactive waste, especially in arid environments, as well as its treatment and management prior to disposal, and will appeal to a wide range of disciplines including engineers, geologists, geophysicists, life scientists and environmentalists. Of particular interest would be the intensive studies undertaken in South Africa prior to the establishment of a radioactive waste repository in that country

Preparation and characterization of a novel polymeric based solid-solid phase change heat storage material

International Nuclear Information System (INIS)

Xi Peng; Gu Xiaohua; Cheng Bowen; Wang Yufei

2009-01-01

Here we reported a two-step procedure for preparing a novel polymeric based solid-solid phase change heat storage material. Firstly, a copolymer monomer containing a polyethylene glycol monomethyl ether (MPEG) phase change unit and a vinyl unit was synthesized via the modification of hydrogen group of MPEG. Secondly, by copolymerization of the copolymer monomer and phenyl ethylene, a novel polymeric based solid-solid phase change heat storage material was prepared. The composition, structure and properties of the novel polymeric based solid-solid phase change material were characterized by IR, 1 H NMR, DSC, WAXD, and POM, respectively. The results show that the novel polymeric based solid-solid phase change material possesses of excellent crystal properties and high phase change enthalpy.

300 GPM Solids Removal System A True Replacement for Back Flushable Powdered Filter Systems - 13607

Energy Technology Data Exchange (ETDEWEB)

Ping, Mark R.; Lewis, Mark [EnergySolutions, Suite 100, Center Point II, 100 Center Point Circle, Columbia, SC 29210 (United States)

2013-07-01

The EnergySolutions Solids Removal System (SRS) utilizes stainless steel cross-flow ultra-filtration (XUF) technology which allows it to reliably remove suspended solids greater than one (1) micron from liquid radwaste streams. The SRS is designed as a pre-treatment step for solids separation prior to processing through other technologies such as Ion Exchange Resin (IER) and/or Reverse Osmosis (RO), etc. Utilizing this pre-treatment approach ensures successful production of reactor grade water while 1) decreasing the amount of radioactive water being discharged to the environment; and 2) decreasing the amount of radioactive waste that must ultimately be disposed of due to the elimination of spent powdered filter media. (authors)

300 GPM Solids Removal System A True Replacement for Back Flushable Powdered Filter Systems - 13607

International Nuclear Information System (INIS)

Ping, Mark R.; Lewis, Mark

2013-01-01

The EnergySolutions Solids Removal System (SRS) utilizes stainless steel cross-flow ultra-filtration (XUF) technology which allows it to reliably remove suspended solids greater than one (1) micron from liquid radwaste streams. The SRS is designed as a pre-treatment step for solids separation prior to processing through other technologies such as Ion Exchange Resin (IER) and/or Reverse Osmosis (RO), etc. Utilizing this pre-treatment approach ensures successful production of reactor grade water while 1) decreasing the amount of radioactive water being discharged to the environment; and 2) decreasing the amount of radioactive waste that must ultimately be disposed of due to the elimination of spent powdered filter media. (authors)

The concept of partitioning/transmutation in radwaste management

International Nuclear Information System (INIS)

Guillaumont, R.

1993-01-01

It is trite to say that radwaste is more difficult to handle than conventional industrial waste because of its radioactivity. If many toxic chemical compounds can be destroyed by simple thermal incineration, non-radioactive substances whose radioactivity is linked to the presence of toxic elements give rise, because they undergo ''infinite decay'', to the same problems as long-lived radwaste. Radioactivity, because it involves the self-destruction of radionuclides, is more an advantage, as long as it does not result in stable toxic daughter elements, and as long as radioactive decay remains compatible with their reliable confinement. Disposal of A waste (low level waste), for which the radioactive decay period of the beta and/or gamma emitting radionuclides is of human-scale time periods, has become an industrial practice and there is no conceptual problem for this waste. However, management of B and C waste (alpha and high level waste) and, their storage, remain to day in the design stage. It is because they contain sizeable quantities of alpha, beta and gamma emitting radionuclides with radioactive decay periods much greater than human-scale time periods and because C waste generates heat, that the final stage of their management poses problems. These problems are of a complex nature for reasons of 1) science, 2) ethics 3) economics 4) sociology. The idea of modifying alpha and beta radioactivity in C waste to the point where it could disappear is not in itself a new idea. Over the past twenty years, in response to studies on the disposal of vitrified nuclear waste, this option has been raised on several occasions. It has suddenly resurfaced in the light as the topic of Partitioning Transmutation Concept (PTC). Japan and more recently France announced for the first time consistent research programmes. The idea of reduction of alpha radioactivity of the actual B waste is no more a new idea. It has recently come in light as a complementary idea, possibly

Sorption data base for performance assessment of radwaste repository

International Nuclear Information System (INIS)

Cho, Y.H.; Jung, J.; Lee, J.K.; Hahn, P.S.

2001-01-01

Sorption data base (SDB) provides readily available data for the performance assessment of radwaste repository when site-specific data are not available and/or more reference data are needed. The software developed in the Korea Atomic Energy Research Institute (KAERI), SDB-21C, is a graphic user interface (GUI) program that provides efficient and user friendly tools for evaluating the large amount of sorption data. The data base of distribution coefficients compiled in the program contains about 11,000 Nuclear Energy Agency (NEA) data and 2,000 KAERI data up to now while the addition of new data is under progress. Furthermore, the parametric model and its compiled data sets are also included in SDB-21C. (author)

Municipal Solid Waste Characterization according to Different Income Levels: A Case Study

Directory of Open Access Journals (Sweden)

Huseyin Kurtulus Ozcan

2016-10-01

Full Text Available Solid waste generation and characterization are some of the most important parameters which affect environmental sustainability. Municipal solid waste (MSW characterization depends on social structure and income levels. This study aims to determine the variations in waste components within MSW mass by income levels and seasonal conditions following the analysis conducted on the characterization of solid wastes produced in the Kartal district of the province of Istanbul, which is the research area of this study. To this end, 1.9 tons of solid waste samples were collected to represent four different lifestyles (high, medium, and low income levels, and downtown in the winter and summer periods, and characterization was made on these samples. In order to support waste characterization, humidity content and calorific value analyses were also conducted and various suggestions were brought towards waste management in line with the obtained findings. According to the results obtained in the study, organic waste had the highest rate of waste mass by 57.69%. Additionally, significant differences were found in municipal solid waste components (MSWC based on income level. Average moisture content (MC of solid waste samples was 71.1% in moisture analyses. The average of calorific (heating value (HHV was calculated as 2518.5 kcal·kg−1.

The evolution of hot-stage microscopy to aid solid-state characterizations of pharmaceutical solids

International Nuclear Information System (INIS)

Vitez, I.M.; Davidovich, M.; Newman, A.W.; Kiesnowski, C.

1998-01-01

A variety of techniques can be used to characterize the physical properties of pharmaceutical solids, including thermal analysis, hot-stage microscopy, X-ray powder diffraction, spectroscopic and micromeritic analysis. Comprehensive characterizations of the physical properties of pharmaceutical solids require a multi-disciplinary approach, since no single technique is capable of characterizing the materials completely.The combination of traditional hot-stage microscopy with new technologies such as high-resolution micrography, image capture, storage manipulation, and presentation, have permitted more comprehensive physical property characterizations to be conducted. As a result of these technological advances, it is possible to present the results of these microscopic analyses, as they were initially collected by the microscopist, outside of the laboratory.An evolutionary trail detailing the use of hot-stage microscopy in the Materials Science Group, from a simple melting point apparatus to the current hot-stage DSC microscopy instrument, will be presented. Examples of materials characterized using the hot-stage microscopy system will also be presented. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

Mathematical simulation of gas pressure in fibre-reinforced concrete container at radiation and biological decomposition of cellulose, bituminized and concrete radwastes

International Nuclear Information System (INIS)

Kuruc, J.; Kvito, P.

2005-01-01

Fibre-reinforced concrete container (FRCC) are used for long-time repository of radioactive wastes. Low- and middle-active radwastes from operation of the NPPs V-1, V-2 Jaslovske Bohunice, Mochovce NPP and from decommissioned NPP A-1 (Jaslovske Bohunice) are treated in the plant SE-VYZ in Jaslovske Bohunice and after immobilisation are deposited in National Radwaste Repository Mochovce (RU RAO). After filling of the RU RAO, FRCC will be stored during 300 years. During this time the integrity of the FRCC must be guaranteed. By the influence of autoradiolysis of the cellulose and bituminized radwastes as well as in cement grout the gases are formed, mainly the hydrogen, methane and carbon dioxide. In the case of presence of available water (a w ≥ 0.63) and in presence of microbes and moulds at appropriate conditions the biological decomposition of cellulose materials may proceed with formation of H 2 , CH 4 a CO 2 . With increasing of developed gases may increase pressure in FRCC, that may initiate the loss of integrity of the FRCC with following endangering of radiation safety of the RU RAO, respectively of the territory over the repository.Authors developed the new mathematical model of pressure of gases in FRCC and in deposited barrels with cellulose and bituminized radwastes. The mathematical model is based on biological decomposition of cellulose materials as well as on radiation decomposition of cellulose, bitumen and concrete. In this mathematical model the diffusion through the walls of FRCC is the main process responsible for decreasing of the pressure. This model was developed in two basic variants: (1) Mathematical model of gas pressure in FRCC as function of dose; (2) Mathematical model of gas pressure in FRCC as function of mass of cellulose

Radiochemical Separation and Quantification of Tritium in Metallic Radwastes Generated from CANDU Type NPP - 13279

Energy Technology Data Exchange (ETDEWEB)

Ahn, H.J.; Choi, K.C.; Choi, K.S.; Park, T.H.; Park, Y.J.; Song, K. [Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-330 (Korea, Republic of)

2013-07-01

As a destructive quantification method of {sup 3}H in low and intermediate level radwastes, bomb oxidation, sample oxidation, and wet oxidation methods have been introduced. These methods have some merits and demerits in the radiochemical separation of {sup 3}H radionuclides. That is, since the bomb oxidation and sample oxidation methods are techniques using heating at high temperature, the separation methods of the radionuclides are relatively simple. However, since {sup 3}H radionuclide has a property of being diffused deeply into the inside of metals, {sup 3}H which is distributed on the surface of the metals can only be extracted if the methods are applied. As an another separation method, the wet oxidation method makes {sup 3}H oxidized with an acidic solution, and extracted completely to an oxidized HTO compound. However, incomplete oxidized {sup 3}H compounds, which are produced by reactions of acidic solutions and metallic radwastes, can be released into the air. Thus, in this study, a wet oxidation method to extract and quantify the {sup 3}H radionuclide from metallic radwastes was established. In particular, a complete extraction method and complete oxidation method of incomplete chemical compounds of {sup 3}H using a Pt catalyst were studied. The radioactivity of {sup 3}H in metallic radwastes is extracted and measured using a wet oxidation method and liquid scintillation counter. Considering the surface dose rate of the sample, the appropriate size of the sample was determined and weighed, and a mixture of oxidants was added to a 200 ml round flask with 3 tubes. The flask was quickly connected to the distilling apparatus. 20 mL of 16 wt% H{sub 2}SO{sub 4} was given into the 200-ml round flask through a dropping funnel while under stirring and refluxing. After dropping, the temperature of the mixture was raised to 96 deg. C and the sample was leached and oxidized by refluxing for 3 hours. At that time, the incomplete oxidized {sup 3}H compounds were

Optical techniques for solid-state materials characterization

CERN Document Server

Prasankumar, Rohit P

2016-01-01

This book has comprehensively covered the essential optical approaches needed for solid-state materials characterization. Written by experts in the field, this will be a great reference for students, engineers, and scientists.-Professor Yoke Khin Yap, Michigan Technical University.

The no-cost radwaste resource: Utilizing the system engineer to help achieve optimum radwaste system performance

International Nuclear Information System (INIS)

Green, R.; Michalski, M.

1995-01-01

All of us in the nuclear power business today know and often use words like - de-regulation, downsize, manpower reduction, cost savings, budget cuts, cost per kilowatt and probably 25 other terms, all relating to you doing a better job with less money and fewer resources. Maybe I have a suggestion that will help you find a resource that can help you - a no-cost resource that you may already have and may not be using. I don't know what you believe, but I believe that a nuclear power station can only be as good as the people who work there, and I believe that system performance and reliability can be improved on virtually any system by merely directing focus and attention to that system. In other words, systems are like children, if you neglect them, they go bad... And they go bad when you're not expecting it. This paper looks at what a system engineer can do for you toward a goal of optimum Radwaste system performance and reviews some of the tools we are using at Grand Gulf to reach our goals

Liquid radwaste processing, operational experience utilizing Duratek Mobile Process System (MPS)

International Nuclear Information System (INIS)

Hunkele, W.; Jensen, C.E.; Duratek Corp., Beltsville, MD)

1985-01-01

The use of Duratek's Mobile Process System (MPS) employing sluiceable pressure vessels and improved operational techniques generates operational efficiencies including volume reduction (VR), reduced personnel labor and exposure and higher flowrates for cleanup of liquid radwaste streams in an operating nuclear power plant (Salem Generating Station). Significant additional VR is achievable based on laboratory and on-site experience utilizing Durasil 70. Under high conductivity, actual waste stream conditions, this proprietary media has demonstrated through-puts of a magnitude 15 times higher than organic cation resin. A long-term problem, cobalt species removal, is mitigated by this media

On selection of geological medium for disposal of high-level radwaste

International Nuclear Information System (INIS)

Min Maozhong

1991-01-01

The present paper briefly reviews the suitability of some rocks as geological disposal repositories of high-level radwaste (HLW). The suitable rocks for geological ogi disposal of HLW are rock salt (salt diapir, bedded salt), granite, argillaceous rocks, tuff, basalt, gabbro, diabase, anhydrite, marine sedimentary rocks etc., especially, rock salt, granite, and argillaceous rocks. The data of principal hydraulic properties, mechanical-physical properties for various rocks in typical environment which might be considered for disposal purposes are also given in this paper. These data give a reference to China's geological disposal of HLW in the future

Preparation of Radwaste Disposal Site in Jawa Island and Its Surrounding Areas

International Nuclear Information System (INIS)

Budi Setiawan; Teddy Sumantry; Heru Sriwahyuni; Hendra A Pratama; Nurul Efri E; Achmad Sjarmufni; Pratomo Budiman; Dadang Suganda; Soegeng Waluyo; Ari Pudyo; Dewi Susilowati; Marwoto

2008-01-01

The task continuation and national needs indicate the important of starting for radioactive waste disposal preparation. As the IAEA procedures for the first step are to accomplished the conceptual and planning stage of radwaste disposal siting in Jawa island. Within the plan, the Milestone, the site important factors, the potential host rock, the possible areas, the aims and the investigation programs have been defined. From the procedures which are followed hopefully in the end of the activities, suitable site(s) to be able selected for radioactive waste disposal facility in near future. (author)

Characterization of solidified radioactive wastes produced at Montalto di Castro BWR plant with reference to the site storage

International Nuclear Information System (INIS)

Donato, A.; Ricci, G.; Pace, A.

1985-01-01

The cement solidification of the Montalto di Castro BWR plant radwastes has been studied both from the point of view of the mixtures of formulation and of the product characterization. Five radwaste types and mixtures of them have been taken into consideration, determining the best chemical formulations starting from the compressive strenght as leading parameter. The solidified products have been characterized from the point of view of the freeze and thawing resistance, the water immersion resistance, the leachability, the dimensional changes and the free standing water. All the tests have been performed taking into account the real site conditions, so the leaching tests and the water immersion tests have been carried out using sea water and table water as leachant

Evaluation of radwaste minimization program of dry and wet active waste in the Laguna Verde Nuclear Power Plant

International Nuclear Information System (INIS)

Luna-Garza, Hector

2001-01-01

A growing rate of radwaste volume production combined with an increase of both, costs and associated dose involved in its treatment and disposition processes have created a serious problem to the Laguna Verde Nuclear Power Plant (BWR, two Units, 682 Mwe each) in Mexico. Due the lack of a Final Repository in the country, the solution in the short or long terms relies on the success of a continuous and aggressive minimization program mainly based on modifications and upgrades applied to these processes. Technical and administrative strategies adopted by LVNPP for the reduction of Liquid Effluents and Dry and Wet Active Waste in the next three years are described. Based on the results of the LVNPP current radwaste process systems, an estimated accumulation of 11,502 m 3 by the year 2035 will exceed the actual on-site storage capacity. If the strategies succeed, this production would fall to an expected manageable volume of 4067 m 3 . (author)

Operation of Temporary Radioactive waste stoprage facility

Energy Technology Data Exchange (ETDEWEB)

Kinseem, A A; Abulfaraj, W H; Sohsah, M A; Kamal, S M; Mamoon, A M [Nuclear Engineering Department, Faculty of Engineering, King Abdelazizi University jeddah-21413, Saudi Arabia (Saudi Arabia)

1997-12-31

Radionuclides of various half lives have been in use for several years years at different Departments of king Abdulaziz university, the university hospital, and research center. The use of unsealed radionuclides in many laboratories, resulted in considerable amounts of solid and liquid radwaste, mainly radiopharmaceuticals. To avoid accumulation of radwastes in working areas, a temporary radioactive waste storage facility was built. Segregation of radwastes according to type was carried out, followed by collection into appropriate containers and transfer to the storage facility. Average radiation dose rate inside the store was maintained at about 75 {mu} h{sup -1} through use of appropriate shielding. The dose rates at points one meter outside the store walls were maintained at about 15-20 {mu}Sv h{sup -1}. Utilization of radioisotopes during the period of 1991-1995 resulted in a volume of about 1.8 m{sup 3} of solid radwaste and about 200 L of liquid radwaste. Records of the store inventory are maintained in a computer database, listing dates, types, activities and packaging data pertinent to the radwastes delivered to the store. Quality assurance procedures are implemented during the different stages of the radwaste collection, transportation, and storage. Construction and operation of the storage facility comply with radiation safety requirements for the workers handling the radwastes, the public and the environment. The capacity of the storage facility is such that it will accommodate storage of generated radwastes of long half life up to year 2016. Permanent disposal of such radwastes may be indicated afterwards. 2 figs., 3 tabs.

Solid State Characterization of Commercial Crystalline and Amorphous Atorvastatin Calcium Samples

OpenAIRE

Shete, Ganesh; Puri, Vibha; Kumar, Lokesh; Bansal, Arvind K.

2010-01-01

Atorvastatin calcium (ATC), an anti-lipid BCS class II drug, is marketed in crystalline and amorphous solid forms. The objective of this study was to perform solid state characterization of commercial crystalline and amorphous ATC drug samples available in the Indian market. Six samples each of crystalline and amorphous ATC were characterized using X-ray powder diffractometry (XRPD), differential scanning calorimetry (DSC), thermogravimetric analysis, Karl Fisher titrimetry, microscopy (hot s...

Characterization and morphology of solids suspended in rain water

International Nuclear Information System (INIS)

Iturbe G, J.L.; Lopez M, B.E.; Torre O, J. De la

2000-01-01

This work presents the results obtained from the analysis of rain water in Mexico. The study treats over the characterization and morphology of the solids suspended in form of particles in the atmosphere. The solids suspended were obtained of the pluvial precipitations after these have been centrifuged. Subsequently of the separation, the particulate matter was analysed by Sem and X-ray dispersive energy

Kola peninsula radwaste management in the framework of THE Italian-Russian cooperation agreement for global partnership - 59392

International Nuclear Information System (INIS)

Nobile, Massimiliano; Izmailov, Dmitry; Spadoni, Antonino; Uryvskiy, Oleg

2012-01-01

In 2003 a Cooperation Agreement, envisaging a grant of 360 Meuro in 10 years, was signed between Italy and Russia in the framework of the 'so-called' Global Partnership Program. So far, in five years of concrete work, a total of 146 Meuro have been engaged through 33 contracts and 121 Meuro have been already paid. Together with other significant lines of activities the management of waste, presently located at Andreeva Bay site, is surely the most important one, not only for the amount of allocated funds (about the half of available ones) but also for the urgency to solve serious environmental problems linked to the actual unsafe conditions of these waste, both as regards possible incidents or malicious attacks from outside. Volume of Low Level and Intermediate Level (LL/IL) waste at Andreeva Bay site are 17000 tons and 3000 tons, respectively for solid and liquid; moreover is expected, during the next 15 years, the production of additional 33000 tons of liquid and 8000 tons of solid, due to the need of demolishing existing facilities and final closing of the site. As regards radwaste management facilities, the solution defined in OBIN (justification of investment) has been analyzed and critically reviewed. After the completion of a conceptual study, the construction of three facilities (solid and liquid treatment ones and a protective structure for storing on site temporarily conditioned waste) was decided and a contract was assigned in 2010 to Ansaldo Nucleare/AtomStroyExport for the detailed design of the above mentioned facilities, which is expected to be completed in 2012. Some important modifications to the initial time schedule have been taken into account and now the operation of the facilities is expected by 2015, two years before the previous estimate. (authors)

Optical characterization of thin solid films

CERN Document Server

Ohlídal, Miloslav

2018-01-01

This book is an up-to-date survey of the major optical characterization techniques for thin solid films. Emphasis is placed on practicability of the various approaches. Relevant fundamentals are briefly reviewed before demonstrating the application of these techniques to practically relevant research and development topics. The book is written by international top experts, all of whom are involved in industrial research and development projects.

Assessment of tritiated activities in the radwaste generated from ITER Chinese helium cooled ceramic breeding test blanket module system

Energy Technology Data Exchange (ETDEWEB)

Chen, Chang An, E-mail: chenchangan@caep.cn; Liu, Lingbo; Wang, Bo; Xiang, Xin; Yao, Yong; Song, Jiangfeng

2016-11-15

Highlights: • Approaches were developed for calculation/evaluation of tritium activities in the materials and components of a TBM system, with tritium permeation being considered for the first time. • Almost all tritiated materials and components were considered in CNHCCB TBM system including the TBM set, connection pipes, and the ancillary tritium handling systems. • Tritium activity data in HCCB TBM system were updated. Some of which in directly tritium contacted components are to be 2 or 4 magnitudes higher than the original neutron transmutation calculations. • The radwaste amount from both operation and decommission of HCCB TBM system was evaluated. - Abstract: Chinese Helium Cooled Ceramic Breeding Test blanket Module (CNHCCB TBM) will be tested in the ITER machine for the feasibility of in pile tritium production for a future magnetic confinement fusion reactor. The tritium inventories/retentions in the material/components were evaluated and updated mainly based on the tritium diffusion/permeation theory and the analysis of some reported data. Tritiated activities rank from less than 10 Bq g{sup −1} to 10{sup 9} Bq g{sup −1} for the different materials or components, which are generally higher than those from the previous neutron transmutation calculation. The amounts of tritiated radwaste were also estimated according to the operation, decommission, maintenance and replacement strategies, which vary from several tens of kilograms to tons in the different operation phases. The data can be used both for the tritium radiological safety evaluation and radwaste management of CNHCCB TBM set and its ancillary systems.

Introduction to seminar on organics in radwaste held at Harwell on 22nd September 1987

International Nuclear Information System (INIS)

Bradbury, D.

1988-01-01

The introduction to the Seminar on Organics in Radwaste stresses the necessity for the efficiency of natural and engineered barriers designed for the management of radioactive wastes to satisfy public scrutiny. The preparation of wastes prior to encapsulation is discussed. The negative effects of introduced organic material in waste sites on safety and the mechanism of organic degradation prior to the removal of organics from wastes is discussed. (U.K.)

Of creation of up-to-date system for liquid radwaste management at Ukraine's NPPs. Problem statement

International Nuclear Information System (INIS)

Andronov, O.B.

2015-01-01

The main aspects are addressed of problems in the field of liquid radwaste (LRW) management for Ukrainian NPPs; approaches for its decision, and offers of NNEGC Energoatom SE STC specialists concerning the above issue. Conceptual principle of creation of up-to-date hi-tech complex for LRW management is considered

Dissolution of britholites and monazite / brabantite solid solutions doped with actinides

International Nuclear Information System (INIS)

Du Fou De Kerdaniel, E.

2007-12-01

In the field of the radwaste storage in underground repository, several matrices were considered as promising ceramics for the specific immobilization of actinides. Two of them, britholites and monazite/ brabantite solid solution, have been considered during this work. In order to examine the dissolution mechanisms occurring at the solid liquid interface, several leaching experiments have been conducted on (Ln III PO 4 ), brabantite (Ca II An IV (PO 4 ) 2 : An = Th, U) and britholites (Ca 9 Nd 0.5 An 0.5 IV (PO 4 ) 4.5 (SiO 4 ) 1.5 F 2 : An = Th, U). Some steady experiments, performed in under saturation conditions for various pH and temperature conditions allowed to evaluate the long term behaviour of such matrices through their chemical durability. On the contrary, the thermodynamic equilibria were examined through the leaching experiments performed near the saturation conditions. By the way, various secondary phases, precipitated onto the surface of altered samples have been identified and characterized. Among them, the (Nd, Ca, Th) - rhabdophane, novelly prepared in over- saturation experiments for a thorium weight loading lower than 11 % appeared to be metastable. Indeed, it turns into TPHPH (Th 2 (PO 4 ) 2 HPO 4 .H 2 O) and Nd - rhabdophane (NdPO 4 .1/2H 2 O) when increasing leaching time. (author)

Immobilization and leaching mechanisms of radwaste in cement-based matrices

International Nuclear Information System (INIS)

Glasser, F.P.; Rahman, A.A.; Crawford, R.W.; McCullough, C.E.; Angus, M.J.

1982-03-01

The components of anhydrous cement clinkers and their adsorptive properties for Cs has been determined. The efficiency of different analytical methods are compared, and it is shown that only radiochemical methods afford a true picture of the quantitative extent of adsorption. Hydrothermal studies have been undertaken to assess the interactions between the Ca(OH) 2 component of cement and radioactive waste constituents. In most cases, chemical reaction occurs due to the strongly alkaline nature of the medium: the potential of hydrothermal methods for predicting the behaviour and performance of cement-radwaste systems is assessed and the relevant solution chemistry described. Cement-zeolite interactions have been studied: these interactions are revealed by a variety of physical techniques, and begin to afford some insight into the reaction mechanism. (author)

Performance assessment for Nuclear Power Plant Krsko intermediate and low-level rad-waste repository; Provjera sigurnosnih performansi odlagalishta radioaktivnog otpada niske i srednje aktivnosti nuklearne elektrane Krsko

Energy Technology Data Exchange (ETDEWEB)

Jelavic, V [Inst. za Elektroprivredu, Zagreb. (Yugoslavia).; Tankosic, Dj [Bechtel Inc., San Francisco (United States); Skanata, D [Nuklearna elektrana Krshko, Krshko (Yugoslavia); Plecjas, I [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

1990-07-01

Performance safety Assessment for NPP Krsko radwaste repository was performed (LLW/ILW). Shallow land and tunnel type concept were analyzed. Because it was based on two unknown referent sites, one for the shallow land concept and the other for the tunnel type, analysis was generic in nature. Scenario selecting process and consequence analysis were performed by using deterministic approach. Results for both concepts of disposal suggests that proposed NPP Krsko radwaste repository reference site and disposal technology will fully meet radiation limits imposed by the Yugoslav regulations and ICRP guidelines. (author)

Solid State Characterizations of Long-Term Leached Cast Stone Monoliths

Energy Technology Data Exchange (ETDEWEB)

Asmussen, Robert M.; Pearce, Carolyn I.; Parker, Kent E.; Miller, Brian W.; Lee, Brady D.; Buck, Edgar C.; Washton, Nancy M.; Bowden, Mark E.; Lawter, Amanda R.; McElroy, Erin M.; Serne, R Jeffrey

2016-09-30

This report describes the results from the solid phase characterization of six Cast Stone monoliths from the extended leach tests recently reported on (Serne et al. 2016),that were selected for characterization using multiple state-of-the-art approaches. The Cast Stone samples investigated were leached for > 590 d in the EPA Method 1315 test then archived for > 390 d in their final leachate. After reporting the long term leach behavior of the monoliths (containing radioactive ⁹⁹Tc and stable ¹²⁷I spikes and for original Westsik et al. 2013 fabricated monoliths, ²³⁸U), it was suggested that physical changes to the waste forms and a depleting inventory of contaminants of potential concern may mean that effective diffusivity calculations past 63 d should not be used to accurately represent long-term waste form behavior. These novel investigations, in both length of leaching time and application of solid state techniques, provide an initial arsenal of techniques which can be utilized to perform such Cast Stone solid phase characterization work, which in turn can support upcoming performance assessment maintenance. The work was performed at Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions (WRPS) to characterize several properties of the long- term leached Cast Stone monolith samples.

Robotic cleaning of radwaste tank nozzles

International Nuclear Information System (INIS)

Boughman, G.; Jones, S.L.

1992-01-01

The Susquehanna radwaste processing system includes two reactor water cleanup phase separator tanks and one waste sludge phase separator tank. A system of educator nozzles and associated piping is used to provide mixing in the tanks. The mixture pumped through the nozzles is a dense resin-and-water slurry, and the nozzles tend to plug up during processing. The previous method for clearing the nozzles had been for a worker to enter the tanks and manually insert a hydrolaser into each nozzle, one at a time. The significant radiation exposure and concern for worker safety in the tank led the utility to investigate alternate means for completing this task. The typical tank configuration is shown in a figure. The initial approach investigated was to insert a manipulator arm in the tank. This arm would be installed by workers and then teleoperated from a remote control station. This approach was abandoned because of several considerations including educator location and orientation, excessive installation time, and cost. The next approach was to use a mobile platform that would operate on the tank floor. This approach was selected as being the most feasible solution. After a competitive selection process, REMOTEC was selected to provide the mobile platform. Their proposal was based on the commercial ANDROS Mark 5 platform

Characterization on incineration residue of radioactive solid wastes

International Nuclear Information System (INIS)

Katoh, Kiyoshi; Hirayama, Katsuyoshi; Kato, Akira.

1989-01-01

Characterization was carried out on incineration residue discharged from the radioactive solid waste incineration unit (capacity, 100 kg/h) in use at the Tokai Research Establishment of Japan Atomic Energy Research Institute (JAERI) to obtain basic data for investigating solidification methods of the residue. The characterized residue was taken from furnace and a primary ceramic filter of the incineration unit which incinerates combustible solid wastes generated at JAERI and the outside organizations. Items of characterization involve a particle size distribution, misplaced materials content, ignition loss, chemical composition and radioactivity of nuclides in the ash. As the results, the size of ash sampled from the furnace distributed a wide range, with about 35∼60 % of ash smaller than 5 mm and about 10∼25 % of massive one larger than 30 mm (max. size: ∼130 mm). The ignition loss was 2∼3 %. The chemical compositions of the ash were mainly SiO 2 , Fe 2 O 3 , CaO and Al 2 O 3 . The specific activities of the ash were about 0.4∼4 x 10 3 Bq/g, and principal contaminants were 60 Co and 137 Cs. (author)

Evaluation of brazilian bentonites as additive in the radwaste cementation

International Nuclear Information System (INIS)

Tello, C.C.O. de.

1988-01-01

The behavior of some Brazilian bentonites has been evaluated, concerning to their use as additive in the radwaste cementation. The purpose of the bentonite is to retain the radioelements in the final product in leaching process. Experiments to determine properties such as compressive strenght, viscosity, set time leaching and cesium sorption have been carried out to this evaluation. After one-year test, the results show that the bentonites greatly reduce the cesium release. A literature survey about cementation process and plants and about the cement product characteristics has been made in order to obtain a reliable final product, able to be transported and storaged. Some leaching test methods and mathematical models, that could be applied in the evaluation of cement products with bentonite have been evaluated. (author) [pt

The development of radwaste policy and the Nirex programme

International Nuclear Information System (INIS)

Folger, M.

1993-01-01

Radwaste policy has had a chequered past in this country and although some of the blame has occasionally been laid at our door, three things sound be borne in mind, the context within which Nirex has worked and must continue to work, many of the ''myths'' about Nirex, and assurance that there is a well structured programme for stepwise investigation, and potential development, at Sellafield. Through that solution the waste producers will be paying real money to meet the requirement in the present generation. I aim to demonstrate that the United Kingdom (UK) programme for deep disposal is on track and compares well with the programmes which other nuclear nations have in place. Whatever the future investment decisions on nuclear power, government strategy does properly require safe disposal of the wastes we already have and the wastes which will come forward from the present nuclear programme. (Author)

Planning of optimal work path for minimizing exposure dose during radiation work in radwaste storage

International Nuclear Information System (INIS)

Kim, Yoon Hyuk; Park, Won Man; Kim, Kyung Soo; Whang, Joo Ho

2005-01-01

Since the safety of nuclear power plant has been becoming a big social issue, the exposure dose of radiation for workers has been one of the important factors concerning the safety problem. The existing calculation methods of radiation dose used in the planning of radiation work assume that dose rate dose not depend on the location within a work space, thus the variation of exposure dose by different work path is not considered. In this study, a modified numerical method was presented to estimate the exposure dose during radiation work in radwaste storage considering the effects of the distance between a worker and sources. And a new numerical algorithm was suggested to search the optimal work path minimizing the exposure dose in pre-defined work space with given radiation sources. Finally, a virtual work simulation program was developed to visualize the exposure dose of radiation during radiation works in radwaste storage and provide the capability of simulation for work planning. As a numerical example, a test radiation work was simulated under given space and two radiation sources, and the suggested optimal work path was compared with three predefined work paths. The optimal work path obtained in the study could reduce the exposure dose for the given test work. Based on the results, the developed numerical method and simulation program could be useful tools in the planning of radiation work

Improvement of Radwaste Management System at Bilibinskaya NPP in the Far North Conditions - 13456

Energy Technology Data Exchange (ETDEWEB)

Fedorov, Denis; Adamovich, Dmitry; Savkin, Alexander [SUE SIA Radon, 2/14, 7th Rostovsky lane, Moscow, 119121 (Russian Federation)

2013-07-01

Since 2009 Bilibinskaya NPP is getting started to prepare to the decommissioning in the Far North conditions. Bilibinskaya NPP is located in the Far North of Russian Federation in Chukotka region. Since 1974 it operates 4 units EGP-6 with the capacity of 48 MW each. According to the contract, SIA Radon has performed the following works: - LLRW disposal safety analysis, - The technology of spent ion-exchanger and salt residue solidification is proposed, - Expected radwaste (till 2027) management economical analysis, - Technical proposals for LLRW and IRW management. (authors)

Development and Physicochemical Characterization of Sirolimus Solid Dispersions Prepared by Solvent Evaporation Method

Directory of Open Access Journals (Sweden)

Shahram Emami

2014-12-01

Full Text Available Purpose: The aim of the present investigation was preparation and characterization of sirolimus solid dispersions by solvent evaporation technique to improve its dissolution properties. Methods: Polyvinylpyrrolidone (PVP, Poloxamer 188 and Cremophore RH40 were used to prepare the solid dispersions of sirolimus. In vitro dissolution study using USP type I apparatus, were performed in distilled water (containing SLS 0.4% for pure sirolimus, physical mixtures, Rapamune and prepared solid dispersions. The characterization of solid dispersions was performed using Fourier Transform Infrared (FTIR Spectroscopy and Differential Scanning Calorimetry (DSC. Results: More than 75% of sirolimus was released within 30 minutes from all prepared solid dispersions. The dissolution rate of all prepared solid dispersion powders were more than physical mixtures. The absence of sirolimus peak in the DSC spectrum of solid dispersions indicated the conversion of crystalline form of sirolimus into amorphous form. The results from FT-IR spectroscopy showed that there was no significant change in the FT-IR spectrum of solid dispersions indicating absence of well-defined interaction between drug and carriers. Conclusion: It was concluded that solid dispersion method, using PVP, Poloxamer 188 and Cremophore RH40 can improve dissolution rate of sirolimus.

Operation of radiation monitoring system in radwaste form test facility

International Nuclear Information System (INIS)

Ryu, Young Gerl; Kim, Ki Hong; Lee, Jae Won; Kwac, Koung Kil

1998-08-01

RWFTF (RadWaste Form Test Facility) must have a secure radiation monitoring system (RMS) because of having a hot-cell capable of handling high radioactive materials. And then in controlled radiation zone, which is hot-cell and its maintenance and operation / control room, area dose rate, radioactivities in air-bone particulates and stack, and surface contamination are monitored continuously. For the effective management such as higher utilization, maintenance and repair, the status of this radiation monitoring system, the operation and characteristics of all kinds of detectors and other parts of composing this system, and signal treatment and its evaluation were described in this technical report. And to obtain the accuracy detection results and its higher confidence level, the procedure such as maintenance, functional check and system calibration were established and appended to help the operation of RMS. (author). 6 tabs., 30 figs

Configuration system development of site and environmental information for radwaste disposal facility

International Nuclear Information System (INIS)

Park, Se-Moon; Yoon, Bong-Yo; Kim, Chang-Lak

2005-01-01

License for the nuclear facilities such as radioactive waste repository demands documents of site characterization, environmental assessment and safety assessment. This performance will produce bulk of the relevant data. For the safe management of radioactive waste repository, data of the site and environment have to be collected and managed systematically. Particularly for the radwaste repository, which has to be institutionally controlled for a long period after closure, the data will be collected and maintained through the monitoring programme. To meet this requirement, a new programme called 'Site Information and Total Environmental data management System (SITES)' has been developed. The scope and function of the SITES is issued in data DB, safety assessment and monitoring system. In this respect, SITES is designed with two modules of the SITES Database Module (SDM) and the Monitoring and Assesment (M and A). The SDM module is composed of three sub-modules. One is the Site Information Management System (SIMS), which manages data of site characterization such as topography, geology, hydrogeology, engineering geology, etc. The other is the ENVironmental Information management System (ENVIS) and Radioactive ENVironmental Information management System (RENVIS), which manage environmental data required for environmental assessment performance. ENVIS and RENVIS covered almost whole items of environmental assessment report required by Korean government. The SDM was constructed based on Entity Relationship Diagram produced from each item. Also using ArcGIS with the spatial characteristics of the data, it enables groundwater and water property monitoring networks, etc. To be analyzed in respect of every theme. The sub-modules of M and A called the Site and Environment Monitoring System (SEMS) and the Safety Assessment System (SAS) were developed. SEMS was designed to manage the inspection records of the individual measuring instruments and facilities, and the on

Approach for Assessing Human Intrusion into a Radwaste Repository

International Nuclear Information System (INIS)

Cho, Dong Keun; Kim, Jung Woo; Jeong, Jong Tae; Baik, Min Hoon

2016-01-01

An approach to assess human intrusion into radwaste repository resulting from future human actions was proposed based on the common principals, requirements, and recommendations from IAEA, ICRP, and OECD/NEA, with the assumption that the intrusion occurs after loss of knowledge of the hazardous nature of the disposal facility. At first, the essential boundary conditions were derived on the basis of international recommendations, followed by overall approach to deal with inadvertent human intrusion. The essential premises were derived on the basis of international recommendations, followed by overall approach to deal with inadvertent human intrusion. The procedure to derive protective measures was also explained with four steps regarding how to derive safety framework, general measures, potential measures, and eventual protective measures on the basis of stylized scenarios. It is expected that the approach proposed in this study will be effectively used to reduce the potential for and/or consequence of human intrusion during entire processes of realization of disposal facility.

Liquid radwaste processing history at Fort Calhoun Nuclear Station

International Nuclear Information System (INIS)

Bilau, A.; Rutar, F.

1989-01-01

This report presents a historical perspective of liquid radwaste processing at the Fort Calhoun Unit 1 Nuclear Power Station, located in east central Nebraska. Of particular interest is the textual and graphical comparison of the operational implications of the various waste processing methods employed in the last ten years at the Fort Calhoun Station. Fort Calhoun's waste collection and processing systems are described in detail. These process systems include evaporation and solidification employing an in-plant drum solidification system. This solidification system was later replaced with vendor solidification services which solidified wastes in large liners. Ultimately, the plant converted its processing operation to ion exchange cleanup using ion selective media. The operational and economic impact of each of these process systems is discussed including overall costs, personnel exposure, capital expenditure requirements, burial volumes generated, maintenance and reliability assessments. Operational goals and performance criteria employed in the decision-making process for selection of the optimal technology are discussed, including the impact of various influent and effluent requirements

Dissolution of britholites and monazite / brabantite solid solutions doped with actinides; Etude de la dissolution de britholites et de solutions solides monazite / brabantite dopees avec des actinides

Energy Technology Data Exchange (ETDEWEB)

Du Fou De Kerdaniel, E

2007-12-15

In the field of the radwaste storage in underground repository, several matrices were considered as promising ceramics for the specific immobilization of actinides. Two of them, britholites and monazite/ brabantite solid solution, have been considered during this work. In order to examine the dissolution mechanisms occurring at the solid liquid interface, several leaching experiments have been conducted on (Ln{sup III}PO{sub 4} ), brabantite (Ca{sup II}An{sup IV}(PO{sub 4}){sub 2}: An = Th, U) and britholites (Ca{sub 9}Nd{sub 0.5}An{sub 0.5}{sup IV} (PO{sub 4}){sub 4.5}(SiO{sub 4}){sub 1.5}F{sub 2}: An = Th, U). Some steady experiments, performed in under saturation conditions for various pH and temperature conditions allowed to evaluate the long term behaviour of such matrices through their chemical durability. On the contrary, the thermodynamic equilibria were examined through the leaching experiments performed near the saturation conditions. By the way, various secondary phases, precipitated onto the surface of altered samples have been identified and characterized. Among them, the (Nd, Ca, Th) - rhabdophane, novelly prepared in over- saturation experiments for a thorium weight loading lower than 11 % appeared to be metastable. Indeed, it turns into TPHPH (Th{sub 2}(PO{sub 4}){sub 2}HPO{sub 4}.H{sub 2}O) and Nd - rhabdophane (NdPO{sub 4}.1/2H{sub 2}O) when increasing leaching time. (author)

Treatment of solid radioactive waste: Volume reduction of non-combustible waste

International Nuclear Information System (INIS)

Boehme, G.

1982-01-01

Press compaction is very common as for volume reduction of low level radioactive solid waste. In most cases a sorting step and if necessary a fragmenting step are desirable prior to the compaction process. Besides contamination-free loading and unloading techniques are important. Typical technical solutions for mixed solid waste handling and compacting equipment are shown and discussed by means of the lay-out drawings for a medium size radwaste compaction facility. A special technique can be applied if one has to compact active exhaust air filters in a hot cell. KfK has developed a remotely operated mobile equipment for this purpose. As for the nuclear fuel cycle considerable interest is existing in compacting spent fuel halls after fuel dissolution. In various European countries mechanical compaction and high temperature processes are therefore under development. These processes are described and the related equipment is discussed. (orig./RW)

Preliminary safety assessment and preliminary safety report for the treated radwaste store, Winfrith

International Nuclear Information System (INIS)

Staples, A.T.

1992-06-01

It is the purpose of this assessment to define the categorisation of the Treated Radwaste Store, TRS, B55 at the Winfrith Technology Centre. Its further purpose is to cover all relevant sections required for a Preliminary Safety Report (PSR) encompassing the TRS and the integral Quality Assessment Unit (QUA). The TRS is designed for the interim storage of intermediate level radioactive wastes. All waste material stored in the TRS will be contained within 500 litre stainless steel drums acceptable to NIREX. It is proposed that the TRS will receive 500 litre stainless steel NIREX drums containing either irradiated DRAGON fuel or encapsulated sludge waste. (author)

X-Ray Characterization of Non-Equilibrium Solid Solutions

International Nuclear Information System (INIS)

Brown, A.; Rosdahl, Oe.

1975-01-01

The Rudman approach to composition line broadening in X-ray diffraction patterns, originally designed for the study of diffusion in alloys, is seen to provide a basis for characterizing inhomogeneous solid solutions. Limitations, imposed on this treatment when the cell dimensions of the primary components differ by less than 0.1 A, are attributable to experimental effects such as instrument broadening. These limitations can be overcome by a rigorous numerical treatment of the measured data. Thus, separate elimination of the Kα 2 radiation component followed by iterative deconvolution are advocated for the recovery of the intrinsic broadening. This course of action is made possible chiefly through the availability of large, fast memory computers and primary data recorded in the form of a step scan on punched paper tape. The characteristics of inhomogeneous solid solutions made available by the above treatment are the identity of closely similar, solid solution phases, the frequency distribution curve for a chosen component, and the degree of homogeneity of the X-ray sample

10CFR61 waste form conformance program for asphalted radwaste

International Nuclear Information System (INIS)

Kobran, M.J.; Guarini, W.J.

1987-01-01

With the enactment of Title 10, Code of Federal Regulation, Part 61, ''Licensing Requirements for Land Disposal of Radioactive Waste'' came the imposition of new requirements on licensees who dispose of radioactive waste via shallow land burial. Specifically, 10CFR61 both imposed a waste classification system requiring segregation of waste according to hazard and established waste performance characteristics required to enhance stability of the burial site. In order to provide licensees with guidance regarding implementation of applicable requirements of 10CFR61, the NRC low level Waste Licensing Branch issued two Technical Positions. To demonstrate compliance of asphalted radwaste produced with oxidized asphalt with 10CFR61 criteria and the NRC's Technical Position, five utilities combined resources. The five utilities sponsoring the program were Public Service Electric and Gas Company, Niagara Mohawk Power Company, Detroit Edison Company, New Hampshire Yankee, and Consumers Power Comany

Discussion of the question whether a local authority can claim to be affected in its planning competence by a permit issued for construction of a radwaste processing plant. High Administrative Court Lueneburg, judgement of 21.1.1993 - 7 K 5/90

International Nuclear Information System (INIS)

Czajka, D.

1993-01-01

A local authority has taken legal action against the first partial permit for the construction of a radwaste conditioning pilot plant at Gorleben, claiming to be affected in its planning competence by the fact that transport of spent fuel elements between the spent fuel storage facility and the pilot plant 2 km away would have to proceed on the rural district road. The action has been discussed. Appealable head notes: A local authority is not affected in its planning competence by a permit issued for construction of a facility for radwaste processing, although the operation of said facility may result in radwaste being transported by a road crossing the local authority's territory. (orig.) [de

Liquid radwaste treatment by microfiltration, ultrafiltration and reverse osmosis

International Nuclear Information System (INIS)

Dulama, M.; Deneanu, N.; Popescu, I.V.

2001-01-01

Radioactive liquid waste processing is an integral part of any facility involved in nuclear power generation, radioisotope production, research and development, decontamination or other aspects of nuclear energy. The aqueous liquid radwastes from the decontamination center are currently treated by the membrane plant. Generally, the liquid waste streams are effectively volume-reduced by a combination of continuous crossflow microfiltration (MF), spiral wound reverse osmosis (SWRO) and tubular reverse osmosis membrane technologies. Backwash chemical cleaning wastes from the membrane plant are further volume-reduced by evaporation. The concentrate from the membrane plant is ultimately immobilized with bitumen. We performed experiments using two simulated waste solution; secondary waste from the decontamination process with POD (Permanganate Oxidation Decontamination) solution and secondary waste from decontamination with CAN-DECON solution. The experimental tests have been done with cellulose acetate (CA) membrane and polysulfonate (PSF) membrane manufactured at Research Center for Macromolecular Materials and Membranes Bucharest and with Millipore membrane type VS 0.025 μm. A schematic of the laboratory-scale test facility is presented

Chapter No.6. Radioactive waste (RAW)

International Nuclear Information System (INIS)

2002-01-01

UJD SR supervises all phases of radioactive waste management at nuclear installations and final phases of institutional radioactive waste management. Total concentrates generation and minimisation trends during recent period (for NPP V1, NPP V2 Bohunice and NPP Mochovce) as well as increasing of their conditioning are presented. So nearly 8000 m3 of concentrates were stored at the end of year 2001, representing 75.5% of storage capacity at Bohunice site. Total amount of solid waste stored at VVER NPPs reached 3500 m3 at December 2001. The solid waste storage capacity of NPP V1 Bohunice is spent. NPP A1 Bohunice with a heterogeneous reactor using natural uranium, moderated by heavy water and cooled by CO 2 had been in operation for 4 years. It was finally shut down in February 1977 after an accident (INES level 4). Main activities in 2001 were focused on an increasing of radwaste management safety by the waste solidification or storage improvement, especially in the case of inorganic spent fuel coolant. The total solid radwaste inventory in 2001 (including filters) represents cca 700 m3 of soft and pre-pressed not sorted waste, 700 m3 of sorted waste, more then 1 000 t of scrap and next 260 m3 of scrap in drums. The total volume of contaminated soils and concrete is more than 7200 m3. The volume of solid radwaste depends on the extent of dismantling works and following treatment, conditioning and disposal. The total volume is also increased by products of bituminization and cementation facilities in drums stored before conditioning at NPP A1 Bohunice site. The facilities focused only on treatment of radwaste from NPP A1 decommissioning are operated by the same operator as a part of this decommissioned nuclear installation. Experimental and research treatment plants are operated by VUJE. A facility for the treatment and conditioning of operational liquid radwaste from NPP Mochovce is under preparation and a start of construction is foreseen in 2004. The nuclear

Design and construction of engineering test device of a multi-purpose radwaste incineration system

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Qiu Mingcai; Yang Liguo; Li Xiaohai; Zhang Xiaobin; Lu Xiaowu; Dong Jingling; Wang Xujin; Li Chuanlian; Yang Baomin

2002-01-01

The author describes designs of main un-standard devices, monitoring system and safety system, as well as construction of the engineering system devices for a multi-purpose radwaste incineration system. Un-standard devices include waste crusher, pyrolysis furnace, incinerator furnace, cool stream dilution device and bag filter, etc. The monitoring system mainly includes industrial controlled computer, supported by conventional electrical equipment and instruments. Designs of system safety takes account of containment of radioactive materials fire-prevention, explosion prevention, anti-corrosion, redundance and reservation, emergency system, controlling and electric safety system, etc. Results show that main technological system remains good airtight with leakage ratio at 0.67%

X-Ray Characterization of Non-Equilibrium Solid Solutions

Energy Technology Data Exchange (ETDEWEB)

Brown, A; Rosdahl, Oe

1975-07-01

The Rudman approach to composition line broadening in X-ray diffraction patterns, originally designed for the study of diffusion in alloys, is seen to provide a basis for characterizing inhomogeneous solid solutions. Limitations, imposed on this treatment when the cell dimensions of the primary components differ by less than 0.1 A, are attributable to experimental effects such as instrument broadening. These limitations can be overcome by a rigorous numerical treatment of the measured data. Thus, separate elimination of the Kalpha{sub 2} radiation component followed by iterative deconvolution are advocated for the recovery of the intrinsic broadening. This course of action is made possible chiefly through the availability of large, fast memory computers and primary data recorded in the form of a step scan on punched paper tape. The characteristics of inhomogeneous solid solutions made available by the above treatment are the identity of closely similar, solid solution phases, the frequency distribution curve for a chosen component, and the degree of homogeneity of the X-ray sample

WasteChem Corporation's Volume Reduction and Solidification (VRS) system for low-level radwaste treatment: Final report

International Nuclear Information System (INIS)

1988-01-01

Since 1965, low and medium level radwastes from nuclear power stations, reprocessing plants and nuclear research centers have been stabilized using the Volume Reduction and Solidification (VRS) system. The VRS system uses an extruder/evaporator to evaporate the liquids from waste influents, while simultaneously incorporating the remaining radioactive solids in an asphalt binder. In the period 1965 to 1986 a minimum of 700,000 cubic feet of wastes have been processed with the VRS system. This report provides current operating data from various systems including the volume reduction factors achieved, and the progress of start-ups in the US. The report also provides previously unpublished experience with mixed wastes including uranium raffinate and nitrate-bearing sludges from surface impoundments. VRS systems in the US are currently operating at the Palisades and Hope Creek nuclear stations. These systems produce a variety of waste types including boric acid, bead resin, sodium sulfate and powdered resins. There are three start-ups of VRS systems scheduled in the US in 1987. These systems are at Fermi 2, Seabrook, and Nine Mile Point 2. Overseas, the startup of new systems continues with three VRS process lines coming on-line at the LaHague Reprocessing Center in France in 1986 and a start-up scheduled for 1987 at the Laguna Verde plant in Mexico. The US systems are operating continuously and with little required maintenance. Data on maintenance and the operator exposure are provided in this report. 6 refs., 11 figs., 13 tabs

Combustion/absorption process for the separation of {sup 14}C and {sup 3}H in radwastes released from nuclear power plants and their analysis

Energy Technology Data Exchange (ETDEWEB)

Ko, Young Gun, E-mail: ygko@kaeri.re.kr; Kim, Chang-Jong; Cho, Young Hyun; Chung, Kun Ho; Kang, Mun Ja

2017-06-05

Highlights: • {sup 14}CO{sub 2} and THO were produced by the combustion of radwaste samples. • The radioactivity of {sup 14}CO{sub 2} and THO absorbed sorbents were measured by LSC. • The CO{sub 2} absorption in the {sup 14}C sorbent was analyzed using by FT-IR and a rheometer. • The temperature and viscosity of the CO{sub 2} absorbed {sup 14}C sorbent was investigated. - Abstract: Radioactivities of {sup 3}H and {sup 14}C in spent radioactive ion exchange resins and spent radioactive lubricant oils released from nuclear power plants, has been determined using a combustion and sorption method (combustion method). The liquid scintillation counting (LSC) spectra showed that the interference of other radionuclides has not significantly affected the determination of radioactivities of {sup 3}H and {sup 14}C in the radwaste samples. The chemical structure of {sup 14}CO{sub 2}, which originated from the combustion of radwastes, trapped {sup 14}C sorbent has been investigated using Fourier transform infrared spectroscopy (FT-IR). FT-IR study showed interesting results that peaks for uncoupled CO{sub 2} and carbonic amide appeared at FT-IR spectra of CO{sub 2} high-absorbed {sup 14}C sorbents, while the peak for carbamate was only observed at the spectra of CO{sub 2} low-absorbed sorbents. During the CO{sub 2} sorption in {sup 14}C sorbent, temperature and viscosity of the sorbent increased owing to decrease of enthalpy and increase of apparent molecular weight of the sorbent caused by the bonding formation between sorbent molecules.

Vandellos 1 NPP. Dismantling at the level 1

International Nuclear Information System (INIS)

Pla, E.; Perez Pallares, J.

1998-01-01

Because of the fire in a main turbogenerator in October 1989, the Spanish Ministry of Industry ordered the definitive shutdown of Vandellos 1 NPP. The tasks allowed to the owner in the Ministerial Order were: the reactor defueling, the operation radwaste conditioning. The size of the reactor core needed to prepare an adequate defueling plan in order to prevent the potential reactivity oscillations and ensure the refrigeration of the nuclear fuel remaining in the core. The operation radwastes were divided in four types, according to the conditioning method: the low level solid radwaste, the irradiated metallic materials, the resins and zeolites used for decontaminating the liquid effluents, the radwaste stored in three graphite silos. The low level solid radwastes were stored during operation in drums of 220 litres. Recently they were compacted at a pressure of 40 tones before to be shipped to en ENRESA disposal. The irradiated metallic materials are, essentially, some parts of the refuelling machine. For deactivating the liquid effluents, Vandellos 1 used both organic resins and zeolites. The presence of zeolites helps the cementation, but its rough surface makes difficult to flow in the pipes of the cementation plant. 35 m 3 of this mixture have been conditioned into 670 drums of 220 liters. Vandellos 1 has three silos designed to store the graphite sleeves (reactor fuel support). In the silo number 1 some other radwastes were stored, as low level solid radwastes and two fuel elements. An international request for tenders was made in order to undertake the extraction and conditioning all these radwastes. The project was awarded to the Spanish/French Consortium EQUIPOS NUCLEARES-FRAMATOME. The achievement of the graphite silos project needed to design specific devices for separating irradiated wires from graphite, and searching and extracting two fuel elements jumbled up with the graphite sleeves. The spent fuel ponds have been emptied and its internals confined

PLGA and PHBV Microsphere Formulations and Solid-State Characterization

DEFF Research Database (Denmark)

Yang, Chiming; Plackett, David; Needham, David

2009-01-01

To develop and characterize the solid-state properties of poly(DL-lactic-co-glycolic acid) (PLGA) and poly(3-hydroxybutyric acid-co-3-hydroxyvaleric acid) (PHBV) microspheres for the localized and controlled release of fusidic acid (FA). The effects of FA loading and polymer composition on the me...... of a DCM-FA-rich phase in the forming microsphere....

X-ray characterization of solid small molecule organic materials

Science.gov (United States)

Billinge, Simon; Shankland, Kenneth; Shankland, Norman; Florence, Alastair

2014-06-10

The present invention provides, inter alia, methods of characterizing a small molecule organic material, e.g., a drug or a drug product. This method includes subjecting the solid small molecule organic material to x-ray total scattering analysis at a short wavelength, collecting data generated thereby, and mathematically transforming the data to provide a refined set of data.

Localized corrosion of metallic materials and γ radiation effects in passive layers under simulated radwaste repository conditions. Final report

International Nuclear Information System (INIS)

Schultze, J.W.; Kudelka, S.; Michaelis, A.; Schweinsberg, M.; Thies, A.

1996-02-01

The task of the project was to simulate the conditions in a radwaste repository and to perform local analyses in order to detect the critical conditions and material susceptibilities leading to localized corrosion of materials. The information thus obtained was to yield more precise data on the long-term stability of materials for the intended purpose, in order to be able to appropriately select or optimize the materials (Ti, TiO.2Pd, Hastelloy C4, fine-grained structural steel). A major aspect to be examined was natural inhomogeneities of the electrode surfaces, as determined by the grain structure of the selected materials. Thus a laterally inhomogeneous composition in the welded zone induces an inhomogeneous current distribution, and hence strong susceptibility to localized corrosion. This effect was to be quantified, and the localized corrosion processes had to be identified by means of novel, electrochemical methods with a resolution power of μm. The investigations were to be made under conditions as near to practice as possible, for instance by simulating radwaste repository conditions and performing measurements at elevated temperatures (170 C) in an autoclave. Another task was to examine the radiation effects of γ radiation on passive layers, and describe the possible modifications induced by recrystallisation, photocorrosion, or oxide formation. (orig./MM) [de

Solid Phase Characterization of Tank 241-C-105 Grab Samples

International Nuclear Information System (INIS)

Ely, T. M.; LaMothe, M. E.; Lachut, J. S.

2016-01-01

The solid phase characterization (SPC) of three grab samples from single-shell Tank 241-C-105 (C-105) that were received at the laboratory the week of October 26, 2015, has been completed. The three samples were received and broken down in the 11A hot cells.

Characterization and analysis of medical solid waste in Osun State ...

African Journals Online (AJOL)

This paper reports the study of quantum and characterization of medica solid wastes generated by healthcare facilities in Osun State. The work involved administration of a questionnaire and detailed studies conducted on facilities selected on the basis of a combination of purposive and random sampling methods.

High-Resolution Solid-State NMR Spectroscopy: Characterization of Polymorphism in Cimetidine, a Pharmaceutical Compound

Science.gov (United States)

Pacilio, Julia E.; Tokarski, John T.; Quiñones, Rosalynn; Iuliucci, Robbie J.

2014-01-01

High-resolution solid-state NMR (SSNMR) spectroscopy has many advantages as a tool to characterize solid-phase material that finds applications in polymer chemistry, nanotechnology, materials science, biomolecular structure determination, and others, including the pharmaceutical industry. The technology associated with achieving high resolution…

Preparation and characterization of etoricoxib solid dispersions using lipid carriers by spray drying technique

OpenAIRE

Chauhan, Bhaskar; Shimpi, Shyam; Paradkar, Anant

2005-01-01

The basic objectives of this study were to prepare and characterize solid dispersions of poorly water-soluble drug etoricoxib using lipid carriers by spray drying technique. The properties of solid dispersions were studied by diffuse reflectance infrared Fourier transform spectroscopy (DRIFTS), differential scanning calorimetry (DSC), hotstage microscopy (HSM), radiograph powder diffraction (XRPD), and dissolution studies. The absence of etoricoxib peaks in XRPD profiles of solid dispersions ...

High power solid state retrofit lamp thermal characterization and modeling

NARCIS (Netherlands)

Jakovenko, J.; Formánek, J.; Vladimír, J.; Husák, M.; Werkhoven, R.J.

2012-01-01

Thermal and thermo-mechanical modeling and characterization of solid state lightening (SSL) retrofit LED Lamp are presented in this paper. Paramount Importance is to design SSL lamps for reliability, in which thermal and thermo-mechanical aspects are key points. The main goal is to get a precise 3D

Contact expert group for international radwaste projects. Fourth meeting

International Nuclear Information System (INIS)

1997-06-01

The Contact Expert Group for International Radwaste Projects is the result of an IAEA seminar on ''International Co-operation on Nuclear Waste Management in the Russian Federation'', 15-17 May 1995, that was requested and sponsored by the Nordic countries. In two working groups at the Seminar, participants from the Russian Federation and 17 countries and international organizations co-operating with the Russian Federation in waste management projects recognized the need for setting up a contact group of experts to assist in co-ordinating their efforts. Such co-ordination would help avoid redundancy and duplication of effort, assure that priority needs were made known to the international community, and provide points of contact to facilitate co-operation. This report is a compilation of the 4. CEG meeting materials, both prepared by the CEG Secretariat and presented by meeting's participants. The materials discussed by the CEG and subsequently modified are presented in the finally approved version. As in the case of previous similar reports, the documentation presented was just compiled without any editing and thus should be considered only as ''working proceedings'' of the meeting

Low level radwaste packaging: why not cement

International Nuclear Information System (INIS)

Wilson, R.B.

1978-01-01

Over the past several years many words have been expended in a quest to define a variety of competing radioactive waste immobilization technologies. With the more recent recognition of the technical pitfalls of urea-formaldehyde (UF) a liquid chemical binder considered as optimum less than two years ago, utilities, architect-engineers and systems vendors find themselves in a technology void, awaiting the inevitable breakthrough which will identify the perfect immobilization agent. The culmination of these pressures has brought about the introduction of new immobilization technologies including: one which offers both volume reduction and immobilization in yet another new binder agent; the costly development of highly sophisticated volume reduction systems, the highly-concentrated products from which may pose as-yet unknown immobilization problems; and, the marketing of several new more expensive liquid chemical binders which are reputed to have eliminated the kinds of problems associated with urea-formaldehyde. This paper addresses these issues by coming full circle and arriving back at the initial approach employed for low level radwaste immobilization, the use of cement. Based on an evaluation of the three principal competing immobilization approaches, liquid chemical, bitumen and cement, the merits and drawbacks of each is examined. As will be described, an objective assessment of these competing technologies has resulted in a somewhat surprising conclusion that, while none of the approaches is without disadvantages, cement can be shown to offer the most reliable, versatile long-term solution to today's needs

Radiochemical approaches to the migration of elements from a radwaste repository

International Nuclear Information System (INIS)

Guillaumont, R.

1993-01-01

Underground high-level or intermediary-level alpha radwaste repositories will contain tons to hundreds of tons of anthropogenic elements. It is predicted that the release of the elements into the far field will be mainly dependent upon the 'solubilities', sums of the concentrations of soluble species and colloidal/pseudo colloidal forms, of expected near field compounds. On the other hand, safety assessments, based on computation models of migration, show that elements in the discharged water into the biosphere will be at tracer level, or at least, at trace levels. Kinetic and thermodynamic aspects of the processes in which elements will be involved during their migration are discussed together with the change in their concentrations, over several orders of magnitude. It is shown that special attention must be given to predict the behaviour of the elements in the far field from what we know from classical chemistry, and that more experimental data must be obtained to improve the models. (author). 31 refs., 5 figs., 4 tabs

Solid state characterization of commercial crystalline and amorphous atorvastatin calcium samples.

Science.gov (United States)

Shete, Ganesh; Puri, Vibha; Kumar, Lokesh; Bansal, Arvind K

2010-06-01

Atorvastatin calcium (ATC), an anti-lipid BCS class II drug, is marketed in crystalline and amorphous solid forms. The objective of this study was to perform solid state characterization of commercial crystalline and amorphous ATC drug samples available in the Indian market. Six samples each of crystalline and amorphous ATC were characterized using X-ray powder diffractometry (XRPD), differential scanning calorimetry (DSC), thermogravimetric analysis, Karl Fisher titrimetry, microscopy (hot stage microscopy, scanning electron microscopy), contact angle, and intrinsic dissolution rate (IDR). All crystalline ATC samples were found to be stable form I, however one sample possessed polymorphic impurity, evidenced in XRPD and DSC analysis. Amongst the amorphous ATC samples, XRPD demonstrated five samples to be amorphous 'form 27', while, one matched amorphous 'form 23'. Thermal behavior of amorphous ATC samples was compared to amorphous ATC generated by melt quenching in DSC. ATC was found to be an excellent glass former with T(g)/T(m) of 0.95. Residual crystallinity was detected in two of the amorphous samples by complementary use of conventional and modulated DSC techniques. The wettability and IDR of all amorphous samples was found to be higher than the crystalline samples. In conclusion, commercial ATC samples exhibited diverse solid state behavior that can impact the performance and stability of the dosage forms.

Experimental characterization of solid particle transport by slug flow using Particle Image Velocimetry

International Nuclear Information System (INIS)

Goharzadeh, A; Rodgers, P

2009-01-01

This paper presents an experimental study of gas-liquid slug flow on solid particle transport inside a horizontal pipe with two types of experiments conducted. The influence of slug length on solid particle transportation is characterized using high speed photography. Using combined Particle Image Velocimetry (PIV) with Refractive Index Matching (RIM) and fluorescent tracers (two-phase oil-air loop) the velocity distribution inside the slug body is measured. Combining these experimental analyses, an insight is provided into the physical mechanism of solid particle transportation due to slug flow. It was observed that the slug body significantly influences solid particle mobility. The physical mechanism of solid particle transportation was found to be discontinuous. The inactive region (in terms of solid particle transport) upstream of the slug nose was quantified as a function of gas-liquid composition and solid particle size. Measured velocity distributions showed a significant drop in velocity magnitude immediately upstream of the slug nose and therefore the critical velocity for solid particle lifting is reached further upstream.

Characterization of rhamnolipids by liquid chromatography/mass spectrometry after solid-phase extraction.

Science.gov (United States)

Behrens, Beate; Engelen, Jeannine; Tiso, Till; Blank, Lars Mathias; Hayen, Heiko

2016-04-01

Rhamnolipids are surface-active agents with a broad application potential that are produced in complex mixtures by bacteria of the genus Pseudomonas. Analysis from fermentation broth is often characterized by laborious sample preparation and requires hyphenated analytical techniques like liquid chromatography coupled to mass spectrometry (LC-MS) to obtain detailed information about sample composition. In this study, an analytical procedure based on chromatographic method development and characterization of rhamnolipid sample material by LC-MS as well as a comparison of two sample preparation methods, i.e., liquid-liquid extraction and solid-phase extraction, is presented. Efficient separation was achieved under reversed-phase conditions using a mixed propylphenyl and octadecylsilyl-modified silica gel stationary phase. LC-MS/MS analysis of a supernatant from Pseudomonas putida strain KT2440 pVLT33_rhlABC grown on glucose as sole carbon source and purified by solid-phase extraction revealed a total of 20 congeners of di-rhamnolipids, mono-rhamnolipids, and their biosynthetic precursors 3-(3-hydroxyalkanoyloxy)alkanoic acids (HAAs) with different carbon chain lengths from C8 to C14, including three rhamnolipids with uncommon C9 and C11 fatty acid residues. LC-MS and the orcinol assay were used to evaluate the developed solid-phase extraction method in comparison with the established liquid-liquid extraction. Solid-phase extraction exhibited higher yields and reproducibility as well as lower experimental effort.

Characterization of solid wastes from kraft pulp industry for ceramic materials development purposes

International Nuclear Information System (INIS)

Rodrigues, L.R.; Francisco, M.A.C.O.; Sagrillo, V.P.D.; Louzada, D.M.; Entringer, J.M.S.

2016-01-01

The Kraft pulp industry generates a large amount of solid wastes. Due this large quantity, the target of this study is characterize inorganic solid wastes, dregs, grits and lime mud, from the step of reagents recovery of Kraft process, aiming evaluate the potentiality of their use as alternative raw material on development of ceramic materials. Initially, the wastes were dried and ground, then they were subjected to the following characterization techniques: pH analysis, particle size analysis, X ray fluorescence, X ray diffraction, differential thermal analysis and thermogravimetric analysis and scanning electron microscopy. According to the results, it may be concluded that these wastes could be used as raw material in production of red ceramic and luting materials. (author)

Characterization of solid-solution interface by potentiometric titration and electrophoretic mobility

International Nuclear Information System (INIS)

Lindecker, C.; Drot, R.; Fourest, B.; Simoni, E.

1999-01-01

The study of nuclear waste storage in deep geological sites involves the understanding of processes which could produce a possible dispersion or retention of radioelements. The dispersion of solid particles in aqueous solution is consequently important to be characterized. In this bi-phased system it is necessary to determine the characteristics of the solid-solution interface. The method used of this study is the techniques of potentiometric titration applied to heterogeneous systems. The material studied were phosphate matrices which were synthesized in the laboratory. The dependence of their surface change upon the nature of the electrolytes was investigated

Radwaste management aspects of the test blanket systems in ITER

Energy Technology Data Exchange (ETDEWEB)

Laan, J.G. van der, E-mail: JaapG.vanderLaan@iter.org [ITER Organization, Route de Vinon sur Verdon, F-13067 Saint Paul Lez Durance (France); Canas, D. [CEA, DEN/DADN, centre de Saclay, F-91191 Gif-sur-Yvette cedex (France); Chaudhari, V. [Institute for Plasma Research, Bhat, Gandhinagar 382428 (India); Iseli, M. [ITER Organization, Route de Vinon sur Verdon, F-13067 Saint Paul Lez Durance (France); Kawamura, Y. [Japan Atomic Energy Agency, Naka-shi, Ibaraki-ken 311-0193 (Japan); Lee, D.W. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Petit, P. [European Commission, DG ENER, Brussels (Belgium); Pitcher, C.S.; Torcy, D. [ITER Organization, Route de Vinon sur Verdon, F-13067 Saint Paul Lez Durance (France); Ugolini, D. [Fusion for Energy, Barcelona (Spain); Zhang, H. [China Nuclear Energy Industry Corporation, Beijing 100032 (China)

2016-11-01

Highlights: • Test Blanket Systems are operated in ITER to test tritium breeding technologies. • The in-vessel parts of TBS become radio-active during the ITER nuclear phase. • For each TBM campaign the TBM, its shield and the Pipe Forests are removed. • High tritium contents and novel materials are specific TBS radwaste features. • A preliminary assessment confirmed RW routing, provided its proper conditioning. - Abstract: Test Blanket Systems (TBS) will be operated in ITER in order to prepare the next steps towards fusion power generation. After the initial operation in H/He plasmas, the introduction of D and T in ITER will mark the transition to nuclear operation. The significant fusion neutron production will give rise to nuclear heating and tritium breeding in the in-vessel part of the TBS. The management of the activated and tritiated structures of the TBS from operation in ITER is described. The TBS specific features like tritium breeding and power conversion at elevated temperatures, and the use of novel materials require a dedicated approach, which could be different to that needed for the other ITER equipment.

A study of reverse osmosis applicability to light water reactor radwaste processing. Technical report

International Nuclear Information System (INIS)

Markind, J.; Van Tran, T.

1979-04-01

The use of membrane technology has demonstrated significant process potential in nuclear radioactive waste applications. Reverse osmosis and ultrafiltration can provide filtration capability without the need of filter aids, minimize the requirements of chemical regeneration and/or disposal of expensive resins and can preconcentrate wastes without requiring major process equipment with large auxiliary heat supplies. Because of these capabilities, a study was undertaken to review, evaluate and document the existing experience, both nuclear and appropriate non-nuclear, of the membrane industry as it applies to the processing of reactor radwaste by membrane technology and, in particular, reverse osmosis and ultrafiltration. Relevant information was collected from both the literature and extensive communications with users and suppliers of membrane equipment. The systems reviewed ranged from experimental laboratory units to full scale process units

Characterization of actinide targets by low solid-angle alpha particle counting

CERN Document Server

Denecke, B; Pauwels, J; Robouch, P; Gilliam, D M; Hodge, P; Hutchinson, J M R; Nico, J S

1999-01-01

Actinide samples were characterized in an interlaboratory comparison between IRMM and NIST, including alpha-particle counting at defined low solid angle and counting in a 2 pi proportional gas counter. For this comparison, nine sup 2 sup 3 sup 3 UF sub 4 samples with high uniformity in the layer thickness were prepared at IRMM by deposition under vacuum. Polished silicon wafers were used as source substrates, and these were rotated during the deposition using a planetary rotation system. The estimated uncertainties for the defined low solid-angle methods were about 0.1% at both NIST and IRMM. The agreement of reported alpha-particle emission rates in the energy range 2.5-5.09 MeV was better than or equal to 0.02% for the defined solid-angle methods. When comparing total alpha-particle emission rates over the larger energy range 0-9 MeV (which includes all emissions from the daughter nuclides and the impurities), the agreement of the defined solid-angle methods was better than or equal to 0.05%. The 2 pi propo...

Non-intrusive measurement and hydrodynamics characterization of gas–solid fluidized beds: a review

OpenAIRE

Sun, Jingyuan; Yan, Yong

2016-01-01

Gas-solid fluidization is a well-established technique to suspend or transport particles and has been applied in a variety of industrial processes. Nevertheless, our knowledge of fluidization hydrodynamics is still limited for the design, scale-up and operation optimization of fluidized bed reactors. It is therefore essential to characterize the two-phase flow behaviours in gas-solid fluidized beds and monitor the fluidization processes for control and optimization. A range of non-intrusive t...

Non-intrusive measurement and hydrodynamics characterization of gas-solid fluidized beds: a review

Science.gov (United States)

Sun, Jingyuan; Yan, Yong

2016-11-01

Gas-solid fluidization is a well-established technique to suspend or transport particles and has been applied in a variety of industrial processes. Nevertheless, our knowledge of fluidization hydrodynamics is still limited for the design, scale-up and operation optimization of fluidized bed reactors. It is, therefore, essential to characterize the two-phase flow behaviours in gas-solid fluidized beds and monitor the fluidization processes for control and optimization. A range of non-intrusive techniques have been developed or proposed for measuring the fluidization dynamic parameters and monitoring the flow status without disturbing or distorting the flow fields. This paper presents a comprehensive review of the non-intrusive measurement techniques and the current state of knowledge and experience in the characterization and monitoring of gas-solid fluidized beds. These techniques are classified into six main categories as per sensing principles, electrostatic, acoustic emission and vibration, visualization, particle tracking, laser Doppler anemometry and phase Doppler anemometry as well as pressure-fluctuation methods. Trends and future developments in this field are also discussed.

Non-intrusive measurement and hydrodynamics characterization of gas–solid fluidized beds: a review

International Nuclear Information System (INIS)

Sun, Jingyuan; Yan, Yong

2016-01-01

Gas–solid fluidization is a well-established technique to suspend or transport particles and has been applied in a variety of industrial processes. Nevertheless, our knowledge of fluidization hydrodynamics is still limited for the design, scale-up and operation optimization of fluidized bed reactors. It is, therefore, essential to characterize the two-phase flow behaviours in gas–solid fluidized beds and monitor the fluidization processes for control and optimization. A range of non-intrusive techniques have been developed or proposed for measuring the fluidization dynamic parameters and monitoring the flow status without disturbing or distorting the flow fields. This paper presents a comprehensive review of the non-intrusive measurement techniques and the current state of knowledge and experience in the characterization and monitoring of gas–solid fluidized beds. These techniques are classified into six main categories as per sensing principles, electrostatic, acoustic emission and vibration, visualization, particle tracking, laser Doppler anemometry and phase Doppler anemometry as well as pressure-fluctuation methods. Trends and future developments in this field are also discussed. (topical review)

The development of radwaste in cineration technology (1)

International Nuclear Information System (INIS)

Park, Hun Hwee; Kim, Joon Hyung; Seo, Yong Chil; Kim, In Tae; Ahn, Byung Gil; Yang, Hee Chul; Won, Dong Yeon; Lee, Jae Chun; Kim, Chan Joong

1988-04-01

In order to establish a schedule to develope the incineration technology with feasibility, we summarized the recently published reports of the state of the arts and feasibility studies on it. After comparison study between incineration and compaction, we suggested that the combustible wastes should be incinerated and the incombustible wastes should be compacted by a supercompactor. The status of utilization of incineration for industrial and municipal wastes in Korea was surveyed and the applicability of these techniques to incineration of radwastes were evaluated and resulted to be good. Finally, a long-term plan to utilize the incineration technology up to the commercialization was established on the basis of the above data and feasibility. An experimental incineration process with a capacity of 5 kg plastic wastes per hour was designed by the research team and constructed by several machinery industries of the country to study the incineration characteristics and test the performance of each filter unit in the off-gas system. This process consists of waste pretreatment system, incinerator, off-gas treatment system, and measurement and control system. This process was constructed and performed test-operation with feeding some shredded wastes. The actual experiments will be done in 1988. Under the final goal of developing a SiC filter tube which could be used in the incineration process, a SiC sample with a proper binder was fabricated. The attempts to fabricate a bigger tube and to find out the best fabricating condition will be continued. (Author)

Learn interactively about radwaste management

International Nuclear Information System (INIS)

Stritar, Andrej; Gortnar, Oton; Mele, Irena; Zeleznik, Nadja

2001-01-01

The main purpose of this multimedia, developed by Nuclear Training Centre for the Agency for Radwaste Management is to present the topic to general public, especially schoolchildren. This is a short report about our first experience with the development of multimedia presentations. The whole process was relatively long, almost two years, but the main reason for that was availability of funds. The basic messages, the CD is supposed to deliver to the user, are: Radioactive waste is produced as a by-product of several beneficial human activities. Radioactive waste is dangerous, but we can safely handle and store it. Target audience is younger population that is very familiar with that type of multimedia technology. Therefore the design must be simple, attractive and easily understandable. The way how our messages are delivered must be close to the emotional level of the user, while at the same time factual data must be accurate and up to date. We have decided to use a combination of graphical animations, spoken messages, music, pictures and video clips. Main areas covered are the following: 1. Civilisation and waste 2. About radioactivity 3. What is radioactive waste and where is it produced? 4. What do we do with radioactive waste? 5. Radioactive waste in Slovenia 6. Transport of radioactive waste. Each area is at the top of a single branch of the scenario. In the second step for every display of each branch we have carefully prepared the written and spoken text, selected pictures, eventual video clips and designed animations. During the last development phase the feedback from the target audience was analysed. About 40 students and teacher of elementary school were involved. Their feedback was quite positive. Following figures try to give the impression about the final implementation of the CD ROM. Everything is in Slovenian language, however, translation to any other language is possible. CD-ROM is freely distributed to young visitors of the Nuclear Information

Evaluation and standardisation of fast analytical techniques for destructive radwaste control

Energy Technology Data Exchange (ETDEWEB)

De Simone, A.; Troiani, F. [ENEA, Unita' Rifiuti Radioattivi e Disattivazione Impianti, Centro Ricerche Saluggia, Vercelli (Italy)

2001-07-01

The document describes the work programme carried out by the Laboratorio Nazionale per la 'Caratterizzazione dei Rifiuti Radioattivi', in the frame of the European research project Destructive Radwaste Control. The main tasks of the research work were the evaluation of fast sample pre-treatment procedures and the development of chromatographic methods coupled to fast nuclide detection by Liquid Scintillation Counting. In order to test the High Performance Ion Chromatograph (HPIC) coupled to the Liquid Scintillation Counter (LSC) on high salt content solutions, synthetic cement solutions have been prepared and spiked with several {beta}-emitters hard to be measured with non-destructive analyses, along with other radionuclides important for the determination of the radiological inventory in radwastes. As the validation tests for the new analytical methods involved the manipulation of radioactive solutions, a remote area for HPIC-LSC apparatus has been designed and performed, in order to operate in safe conditions. According to the research programme, fast analytical methods for the chemical separation and radionuclide detection of the radioactive elements of interest, have been developed and qualified. From the results of the work, some protocols of analysis have been defined: they contain all information about operative conditions for HPIC-LSC apparatus, field of applicability, chemical and radioactive detection limits. [Italian] Questo documento riporta il lavoro realizzato dal Laboratorio Nazionale per la Caratterizzazione dei Rifiuti Radioattivi, nell'ambito del progetto di ricerca Europeo sulle tecniche di misura distruttive per rifiuti radioattivi. Il lavoro era finalizzato sia alla valutazione di nuove procedure veloci per la preparazione dei campioni da analizzare sia allo sviluppo di metodi Cromatografici accoppiati alla rivelazione di radionuclidi mediante Conteggio a Scintillazione Liquida. La sperimentazione della Cromatografia Ionica ad

Preparation and characterization of solid lipid nanoparticles-a review.

Science.gov (United States)

Parhi, Rabinarayan; Suresh, Padilama

2012-03-01

In the present scenario, most of the developed and new discovered drugs are posing real challenge to the formulation scientists due to their poor aqueous solubility which in turn is responsible for poor bioavailability. One of the approach to overcome above problem is the packaging of the drug in to particulate carrier system. Among various carriers, lipid emerged as very attractive candidate because of its unique property of enhancing the bioavailability of poorly water soluble drugs. Solid lipid, one of the physical forms of lipid, is used to formulate nanoparticles, popularly known as Solid lipid nanoparticles (SLNs), as an alternative carrier system to emulsions, liposomes and polymeric micro- and nano-particles. SLNs combine advantages of the traditional systems but avoid some of their major disadvantages. This paper reviews numerous production techniques for SLNs along with their advantages and disadvantages. Special attention is paid to the characterization of the SLNs by using various analytical tools. It also emphasizes on physical state of lipid (supercooled melts, different lipid modifications).

Characterization of Protein-Excipient Microheterogeneity in Biopharmaceutical Solid-State Formulations by Confocal Fluorescence Microscopy.

Science.gov (United States)

Koshari, Stijn H S; Ross, Jean L; Nayak, Purnendu K; Zarraga, Isidro E; Rajagopal, Karthikan; Wagner, Norman J; Lenhoff, Abraham M

2017-02-06

Protein-stabilizer microheterogeneity is believed to influence long-term protein stability in solid-state biopharmaceutical formulations and its characterization is therefore essential for the rational design of stable formulations. However, the spatial distribution of the protein and the stabilizer in a solid-state formulation is, in general, difficult to characterize because of the lack of a functional, simple, and reliable characterization technique. We demonstrate the use of confocal fluorescence microscopy with fluorescently labeled monoclonal antibodies (mAbs) and antibody fragments (Fabs) to directly visualize three-dimensional particle morphologies and protein distributions in dried biopharmaceutical formulations, without restrictions on processing conditions or the need for extensive data analysis. While industrially relevant lyophilization procedures of a model IgG1 mAb generally lead to uniform protein-excipient distribution, the method shows that specific spray-drying conditions lead to distinct protein-excipient segregation. Therefore, this method can enable more definitive optimization of formulation conditions than has previously been possible.

Characterization and hydrogeological modelling of a site for disposal of medium- and low-level radioactive waste

International Nuclear Information System (INIS)

Lavie, J.; Peaudecerf, P.

1993-01-01

Characterization studies of the French low-and intermediate-level radwaste site in the Aube Department includes a significant hydrogeological appraisal element. These studies are based upon geological, hydrogeological, and hydrodynamic measurements. The data are compiled into a model of the ground water- body. Data collection is continuous. The hydrodynamic model and the transport model is regularly validated for ANDRA (French National Radioactive Waste Disposal Agency) with a reliable and up-dated tool

A strategic approach to the conceptual design of complex radwaste facilities

International Nuclear Information System (INIS)

Mackay, Stewart; Scott Dam, A.; Holmes, Robert G.G.

1992-01-01

The design of radwaste treatment facilities is often complicated by the variety of waste types being treated. Further uncertainties over their composition and final waste form specifications can make the normal conceptual design phase difficult and unreliable. This paper describes the strategic planning necessary to define the facility functions and the process to prepare a Functional Design Criteria. The paper shows clearly, that for complex waste management problems, it is vital to consider and resolve uncertainties by means of a strategic plan before embarking on conceptual design. The paper shows an approach to preparation of design criteria using functional analysis. The paper provides examples where these methods were and are being used, both in the U.K. and the U.S. Strategic plans and functional criteria can be used as a basis for conceptual design which then provides a more meaningful basis for detailed technology selection during the detailed design process. The paper discusses experiences and lessons learned in the planning process. This process is widely applicable to a number of complex waste treatment facilities being planned and developed to process wastes generated at government facilities. (author)

The estimation and prediction of the inventories for the liquid and gaseous radwaste systems using the linear regression analysis

International Nuclear Information System (INIS)

Kim, J. Y.; Shin, C. H.; Kim, J. K.; Lee, J. K.; Park, Y. J.

2003-01-01

The variation transitions of the inventories for the liquid radwaste system and the radioactive gas have being released in containment, and their predictive values according to the operation histories of Yonggwang(YGN) 3 and 4 were analyzed by linear regression analysis methodology. The results show that the variation transitions of the inventories for those systems are linearly increasing according to the operation histories but the inventories released to the environment are considerably lower than the recommended values based on the FSAR suggestions. It is considered that some conservation were presented in the estimation methodology in preparing stage of FSAR

Results of Characterization and Retrieval Testing on Tank 241-C-109 Heel Solids

Energy Technology Data Exchange (ETDEWEB)

Callaway, William S.

2013-09-26

Eight samples of heel solids from tank 241-C-109 were delivered to the 222-S Laboratory for characterization and dissolution testing. After being drained thoroughly, one-half to two-thirds of the solids were off-white to tan solids that, visually, were fairly evenly graded in size from coarse silt (30-60 μm) to medium pebbles (8-16 mm). The remaining solids were mostly strongly cemented aggregates ranging from coarse pebbles (16-32 mm) to fine cobbles (6-15 cm) in size. Solid phase characterization and chemical analysis indicated that the air-dry heel solids contained ≈58 wt% gibbsite [Al(OH){sub 3}] and ≈37 wt% natrophosphate [Na{sub 7}F(PO{sub 4}){sub 2}·19H{sub 2}O]. The strongly cemented aggregates were mostly fine-grained gibbsite cemented with additional gibbsite. Dissolution testing was performed on two test samples. One set of tests was performed on large pieces of aggregate solids removed from the heel solids samples. The other set of dissolution tests was performed on a composite sample prepared from well-drained, air-dry heel solids that were crushed to pass a 1/4-in. sieve. The bulk density of the composite sample was 2.04 g/mL. The dissolution tests included water dissolution followed by caustic dissolution testing. In each step of the three-step water dissolution tests, a volume of water approximately equal to 3 times the initial volume of the test solids was added. In each step, the test samples were gently but thoroughly mixed for approximately 2 days at an average ambient temperature of 25 °C. The caustic dissolution tests began with the addition of sufficient 49.6 wt% NaOH to the water dissolution residues to provide ≈3.1 moles of OH for each mole of Al estimated to have been present in the starting composite sample and ≈2.6 moles of OH for each mole of Al potentially present in the starting aggregate sample. Metathesis of gibbsite to sodium aluminate was then allowed to proceed over 10 days of gentle mixing of the

Characterization of municipal solid waste incineration fly ash before and after electrodialytic treatment

DEFF Research Database (Denmark)

Pedersen, Anne Juul; Gardner, Kevin H.

2003-01-01

Municipal solid waste incineration (MSWI) fly ash, which has been treated electrodialytically for the removal of heavy metals, may have changed characteristics compared to untreated fly ash. In this study, MSWI fly ash was characterized with respect to leaching properties (pH static leaching...

Solving radwaste problems

International Nuclear Information System (INIS)

Oyen, L.C.

1976-01-01

The combination of regulatory changes and increased waste volume has resulted in design changes in waste processing systems. Problems resulting from waste segregation as a basis for design philosophy are considered, and solutions to the problems are suggested. The importance of operator training, maintenance procedures, good housekeeping, water management, and offsite shipment of solids is discussed. Flowsheets for radioactive waste processing systems for boiling water reactors and pressurized water reactors are included

Characterization Plan for L/ILW Repository Candidate Sites in Croatia

International Nuclear Information System (INIS)

Schaller, A.; Lokner, V.; Kucar-Dragicevic, S.; Subasic, D.

1998-01-01

There have been four preferred sites for L/ILW repository selected in the siting program in Croatia so far. According to the accepted and verified site selection procedure, these sites are suitable for a more detailed characterization, including also site specific field investigations. The aim of these investigations is to measure and calculate all needed site specific parameters important for performance of safety assessment, aiming eventually with selection of the final disposal site. Both Croatian and IAEA regulations referring to radwaste repository siting procedure have been briefly discussed. Detailed site investigations foreseen to be done in order to perform a successful site characterization, refer to the following main topics: geomorphology, lithostratigraphy, tectonics, seismicity, rock mechanics, surface-water hydrology, aquifer features and groundwater hydrology, rock and groundwater chemistry, and radionuclide transport modeling. All these issues are listed in suggested site characterization format. (author)

National report of the Slovak Republic compiled in terms of the Join on the safety of spent fuel management and on the safety of radwaste management

International Nuclear Information System (INIS)

Jurina, V.; Viktory, D.; Petrik, T.; Sovcik, J.; Suess, J.; Tomek, J.; Lukacovic, J.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Vaclav, J.; Bystricka, S.; Barbaric, M.; Horvath, J.; Betak, J.; Mihaly, B.; Adamovsky, V.; Baloghova, A.; Orihel, M.; Vasina, D.; Balaz, J.; Misovicova, D.; Vrtoch, M.; Mlcuch, J.; Granak, P.; Meleg, J.; Bardy, M.; Gogoliak, J.

2011-08-01

The National safety report of the Slovak Republic on the safety of spent fuel management and on the safety of radwaste management in 2011 is presented. These activities in the safety of spent fuel management and radioactive waste management in the Slovak Republic are reported under the headings: (A) Introduction; B) Concept for spent nuclear fuel management (SNF) and radwaste management (RAW); (C) Scope of application of the convention; (D) Spent fuel management and radioactive waste (RAW) management facilities; (E) Legislation and regulation; (F) General safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste (RAW) management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Disused sealed sources; (K) Planned measures to improve safety; (L) Communication with the public; (M) Annexes. Annexes consists of following parts: I. List of nuclear facilities for spent fuel and RAW management. II. Limits of radioactive material discharges into atmosphere and hydrosphere. III. List of nuclear installations in decommissioning. IV. Inventory of stored spent nuclear fuel. V. Inventory of stored RAW. VI. List of national laws, decrees and guidelines. VII. List of international expert reports (including safety reports). VIII. List of authors.

Characterization of Uranium Solids Precipitated with Aluminosilicates

International Nuclear Information System (INIS)

DUFF, MC

2004-01-01

At the Savannah River Site (SRS), the High-Level Waste (HLW) Tank Farms store and process high-level liquid radioactive wastes from the Canyons and recycle water from the Defense Waste Processing Facility. The waste is concentrated using evaporators to minimize the volume of space required for HLW storage. Recently, the 2H Evaporator was shutdown due to the crystallization of sodium aluminosilicate (NAS) solids (such as cancrinite and sodalite) that contained close to 10 weight percent of elementally-enriched uranium (U). Prior to extensive cleaning,the evaporator deposits resided on the evaporator walls and other exposed internal surfaces within the evaporator pot. Our goal is to support the basis for the continued safe operation of SRS evaporators and to gain more information that could be used to help mitigate U accumulation during evaporator operation. To learn more about the interaction between U(VI) and NAS in HLW salt solutions, we performed several fundamental studies to examine the mechanisms of U accumulation with NAS in highly caustic solutions. This larger group of studies focused on the following processes: co-precipitation/structural incorporation, sorption, and precipitation (with or without NAS), which will be reviewed in this presentation. We will present and discuss local atomic structural characterization data about U that has been co-precipitated with NAS solids (such as amorphous zeolite precursor material and sodalite) using X-ray absorption fine-structure (XAFS) spectroscopic techniques

SOLID RADIOACTIVE WASTE STORAGE TECHNOLOGIES: PERFORMANCE OF A POLYMER SEALANT COATING IN AN ARCTIC MARINE ENVIRONMENT

International Nuclear Information System (INIS)

COWGILL, M.G.; MOSKOWITZ, P.D.; CHERNAENKO, L.M.; NAZARIAN, A.; GRIFFITH, A.; DIASHEV, A.; ENGOY, T.

2000-01-01

This first project, under the auspices of the Arctic Military Environmental Cooperation (AMEC) forum, Project 1.4-1 Solid Radioactive Waste Storage Technologies, successfully demonstrated the feasibility of using a polymer-based coating to seal concrete and steel surfaces from permanent radioactive contamination in an Arctic marine environment. A mobile, self-sufficient spraying device, was developed to specifications provided by the Russian Ministry of Defence Northern Navy and was deployed at the RTP Atomflot site, Murmansk, Russia. Demonstration coatings of Polibrid 705 were applied to concrete surfaces exposed to conditions ranging from indoor pedestrian usage to heavy vehicle passage and container handling in a loading bay. A large steel container was also coated with the polymer, filled with solid radwaste, sealed, and left out of doors and exposed to the full 12 month Arctic weather cycle. The field tests were accompanied by a series of laboratory qualification tests carried out at the research laboratory of ICC Nuclide in St. Petersburg. During the 12-month field tests, the sealant coating showed little sign of degradation except for a few chips and gouge marks on the loading bay surface that were readily repaired. Contamination resulting from radwaste handling was easily removed and the surface was not degraded by contact with the decontamination agents. In the laboratory testing, Polibrid 705 met all the Russian qualification requirements with the exception of flammability. In this last instance, it was decided to restrict application of the coating to land-based facilities. The Russian technical experts from the Ministry of Defence quickly familiarized themselves with the equipment and were able to identify several areas of potential improvement as deployment of the equipment progressed. The prime among these was the desirability of extending the range of the equipment through enlarged gasoline tanks (to permit extended operational times) and longer

SOLID RADIOACTIVE WASTE STORAGE TECHNOLOGIES: PERFORMANCE OF A POLYMER SEALANT COATING IN AN ARCTIC MARINE ENVIRONMENT

Energy Technology Data Exchange (ETDEWEB)

COWGILL,M.G.; MOSKOWITZ,P.D.; CHERNAENKO,L.M.; NAZARIAN,A.; GRIFFITH,A.; DIASHEV,A.; ENGOY,T.

2000-06-14

This first project, under the auspices of the Arctic Military Environmental Cooperation (AMEC) forum, Project 1.4-1 Solid Radioactive Waste Storage Technologies, successfully demonstrated the feasibility of using a polymer-based coating to seal concrete and steel surfaces from permanent radioactive contamination in an Arctic marine environment. A mobile, self-sufficient spraying device, was developed to specifications provided by the Russian Ministry of Defence Northern Navy and was deployed at the RTP Atomflot site, Murmansk, Russia. Demonstration coatings of Polibrid 705 were applied to concrete surfaces exposed to conditions ranging from indoor pedestrian usage to heavy vehicle passage and container handling in a loading bay. A large steel container was also coated with the polymer, filled with solid radwaste, sealed, and left out of doors and exposed to the full 12 month Arctic weather cycle. The field tests were accompanied by a series of laboratory qualification tests carried out at the research laboratory of ICC Nuclide in St. Petersburg. During the 12-month field tests, the sealant coating showed little sign of degradation except for a few chips and gouge marks on the loading bay surface that were readily repaired. Contamination resulting from radwaste handling was easily removed and the surface was not degraded by contact with the decontamination agents. In the laboratory testing, Polibrid 705 met all the Russian qualification requirements with the exception of flammability. In this last instance, it was decided to restrict application of the coating to land-based facilities. The Russian technical experts from the Ministry of Defence quickly familiarized themselves with the equipment and were able to identify several areas of potential improvement as deployment of the equipment progressed. The prime among these was the desirability of extending the range of the equipment through enlarged gasoline tanks (to permit extended operational times) and longer

Evaluation of disposal, recycling and clearance scenarios for managing ARIES radwaste after plant decommissioning

International Nuclear Information System (INIS)

El-Guebaly, L.

2007-01-01

The wealth of experience accumulated over the past 30-40 years of fusion power plant studies must be forged into a new strategy to reshape all aspects of handling the continual stream of radioactive materials during operation and after power plant decommissioning. With tighter environmental controls and the political difficulty of building new repositories worldwide, the disposal option could be replaced with more environmentally attractive scenarios, such as recycling and clearance. We applied the three scenarios to the most recent ARIES compact stellarator power plant. All ARIES-CS components qualify as Class A or C low-level waste, according to the US guidelines, and can potentially be recycled using conventional and advanced remote handling equipment. Approximately 80% of the total waste can be cleared for reuse within the nuclear industry or, preferably, released to the commercial market. This paper documents the recent developments in radwaste management of nuclear facilities and highlights the benefits and challenges of disposal, recycling and clearance

Solid waste generation and characterization in the University of Lagos for a sustainable waste management.

Science.gov (United States)

Adeniran, A E; Nubi, A T; Adelopo, A O

2017-09-01

Waste characterization is the first step to any successful waste management policy. In this paper, the characterization and the trend of solid waste generated in University of Lagos, Nigeria was carried out using ASTM D5231-92 and Resource Conservation Reservation Authority RCRA Waste Sampling Draft Technical Guidance methods. The recyclable potential of the waste is very high constituting about 75% of the total waste generated. The estimated average daily solid waste generation in Unilag Akoka campus was estimated to be 32.2tons. The solid waste characterization was found to be: polythene bags 24% (7.73tons/day), paper 15% (4.83tons/day), organic matters 15%, (4.83tons/day), plastic 9% (2.90tons/day), inert materials 8% (2.58tons/day), sanitary 7% (2.25tons/day), textile 7% (2.25tons/day), others 6% (1.93tons/day), leather 4% (1.29tons/day) metals 3% (0.97tons/day), glass 2% (0.64tons/day) and e-waste 0% (0.0tons/day). The volume and distribution of polythene bags generated on campus had a positive significant statistical correlation with the distribution of commercial and academic structures on campus. Waste management options to optimize reuse, recycling and reduce waste generation were discussed. Copyright © 2017 Elsevier Ltd. All rights reserved.

Influence of the segregation of the granulate from the radwaste-mortar mixture from on the {sup 137}Cs leach-rate; Uticaj segregacije granulata iz sastava betonske - RAO forme na izluzivanje Cs{sup 137}

Energy Technology Data Exchange (ETDEWEB)

Peric, A; Plecas, I; Pavlovic, R; Pavlovic, S [Institute of Nuclear Sciences VINCA, Belgrade (Yugoslavia)

1994-07-01

In this paper. influence of the segregation of the granulate, presented in the radwaste-mortar matrix formulation, on the {sup 137}Cs, immobilized in the waste form, leach-rate is presented. {sup 137}Cs leach-rates of the two inspected groups of the radwaste-mortar mixture samples were compared, where the first group of the orthocylinder shaped samples was treated due to the Standard Hespe's method and the second group was treated using modified Hespe's method. In the prolonged experimental time, both groups have obtained leach-rate values that are nearly the same, striving to the saturation leach-rate values. This fact indicates that the leaching of the radionuclide as a consequence of the granulate segregation process is in same way rebuilt, as a result of the completed hydratation of the mortar matrix, and 'self healing' of the new open pores and cavities (author)

National report of the Slovak Republic compiled in terms of the join convention on the safety of spent fuel management and on the safety of radwaste management

International Nuclear Information System (INIS)

Jurina, V.; Viktory, D.; Petrik, T.; Sovcik, J.; Suess, J.; Tomek, J.; Lukacovic, J.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Vaclav, J.; Bystricka, S.; Barbaric, M.; Horvath, J.; Betak, J.; Mihaly, B.; Adamovsky, V.; Baloghova, A.; Orihel, M.; Vasina, D.; Balaz, J.; Misovicova, D.; Vrtoch, M.; Mlcuch, J.; Granak, P.; Meleg, J.; Bardy, M.; Gogoliak, J.

2011-08-01

The National safety report of the Slovak Republic on the safety of spent fuel management and on the safety of radwaste management in 2011 is presented. These activities in the safety of spent fuel management and radioactive waste management in the Slovak Republic are reported under the headings: (A) Introduction; B) Concept for spent nuclear fuel management (SNF) and radwaste management (RAW); (C) Scope of application of the convention; (D) Spent fuel management and radioactive waste (RAW) management facilities; (E) Legislation and regulation; (F) General safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste (RAW) management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Disused sealed sources; (K) Planned measures to improve safety; (L) Communication with the public; (M) Annexes. Annexes consists of following parts: I. List of nuclear facilities for spent fuel and RAW management. II. Limits of radioactive material discharges into atmosphere and hydrosphere. III. List of nuclear installations in decommissioning. IV. Inventory of stored spent nuclear fuel. V. Inventory of stored RAW. VI. List of national laws, decrees and guidelines. VII. List of international expert reports (including safety reports). VIII. List of authors.

Development and characterization of solid dispersion of piroxicam for improvement of dissolution rate using hydrophilic carriers

Directory of Open Access Journals (Sweden)

Mohammad Barzegar-jalali

2014-09-01

Full Text Available Introduction: The main objective of this study was preparation and characterization of solid dispersion of piroxicam to enhance its dissolution rate. Methods: Solid dispersion formulations with different carriers including crospovidone, microcrystalline cellulose and Elaeagnus angustifolia fruit powder and with different drug: carrier ratios were prepared employing cogrinding method. Dissolution study of the piroxicam powders, physical mixtures and solid dispersions was performed in simulated gastric fluid and simulated intestinal fluid using USP Apparatus type II. The physical characterization of formulations were analyzed using powder X ray diffraction (PXRD, particle size analyzer and differential scanning calorimetry (DSC. Interactions between the drug and carriers were evaluated by Fourier transform infrared (FT-IR spectroscopic method. Results: It was revealed that all of three carriers increase the dissolution rate of piroxicam from physical mixtures and especially in solid dispersions compared to piroxicam pure and treated powders. PXRD and DSC results were confirmed the reduction of crystalline form of piroxicam. FT-IR analysis did not show any physicochemical interaction between drug and carriers in the solid dispersion formulations. Conclusion: Dissolution rate was dependent on the type and ratio of drug: carrier as well as pH of dissolution medium. Dissolution data of formulations were fitted well in to the linear Weibull as well as non-linear logistic and a suggested models.

Solid waste characterization in Ketao, a rural town in Togo, West Africa.

Science.gov (United States)

Edjabou, Maklawe Essonanawe; Møller, Jacob; Christensen, Thomas H

2012-07-01

In Africa the majority of solid waste data is for big cities. Small and rural towns are generally neglected and waste data from these areas are often unavailable, which makes planning a proper solid waste management difficult. This paper presents the results from two waste characterization projects conducted in Kétao, a rural town in Togo during the rainy season and the dry season in 2010. The seasonal variation has a significant impact on the waste stream. The household waste generation rate was estimated at 0.22 kg person(-1) day(-1) in the dry season and 0.42 in the rainy season. Likewise, the waste moisture content was 4% in the dry season while it was 33-63% in the rainy season. The waste consisted mainly of soil and dirt characterized as 'other' (41%), vegetables and putrescibles (38%) and plastic (11%). In addition to these fractions, considerable amounts of material are either recycled or reused locally and do not enter the waste stream. The study suggests that additional recycling is not feasible, but further examination of the degradability of the organic fraction is needed in order to assess whether the residual waste should be composed or landfilled.

Natural analogue for storage of radwaste in crystalline rocks

International Nuclear Information System (INIS)

Brookins, D.G.; Abashian, M.S.; Cohen, L.H.; Wollenberg, H.A. Jr.

1982-01-01

The Bryan-Eldora stock (Colorado) intruded the Precambrian Idaho Springs Formation metamorphic rocks 58 million years ago. Geochronologic-geochemical work by Hart et al. [S.R. Hart et al., in Radiometric Dating for Geologists, E.I. Hamilton, R.S. Farquhar, eds. (Wiley-Interscience, New York, 1968) pp. 73-110] has demonstrated that the heat from the cooling intrusive rocks was sufficient to affect mineral isotopic systematics up to 2000 m from the contact, and the nature of these isotopic perturbations can be explained by a simple diffusion model in turn based on various heat flow models. Our new studies are focused on elemental exchange between stock and intruded rock as a function of distance from the contact; the assumption is made that the stock is a very large, high heat source analogous to a waste form emplaced in the metamorphic rocks without benefit of canister or engineered backfill. Data for U, Th and the REE indicate actinide and lanthanide immobility except perhaps in the 0 to 2m contact zone where some infiltration of the country rocks by stock-derived fluids occurred. Beyond 4m no stock-derived U, Th, REE or *Pb are noted. Further, whole rock Rb-Sr and stable O isotopic data indicate conductive cooling as opposed to convective, water-induced cooling. The intruded rocks possess low porosity and permeability; this helped prevent elemental migration during the 10 5 to 10 6 years of stock crystallization. The petrographic and geochemical studies show that the Idaho Springs (or equivalent) metamorphic rocks are well suited for radwaste storage. 1 figure, 1 table

Decontamination and decommissioning technology tree and the current status of the technologies

Energy Technology Data Exchange (ETDEWEB)

Oh, Won Zin; Won, H.J.; Kim, G.N.; Lee, K.W.; Chol, W.K.; Jung, C.H.; Kim, C.J.; Kim, S.H.; Kwon, S.O.; Chung, C.M

2001-03-01

A technology tree diagram was developed on the basis of the necessary technologies applicable to the decontamination and decommissioning of nuclear facilities. The technology tree diagram is consist of 6 main areas such as characterization, decontamination, decommissioning and remote technology, radwaste management, site restoration, and decommissioning plan and engineering. Characterization is divided into 4 regions such as sampling and data collection, general characterization, chemical analysis and radiological analysis. Decontamination is also divided into 4 regions such as chemical decontamination, mechanical decontamination, the other decontamination technologies and new decontamination technologies. Decommissioning and remote technology area is divided into 4 regions such as cutting techniques, decommissioning technologies, new developing technologies and remote technologies. Radwaste management area is divided into 5 regions such as solid waste treatment, sludge treatment, liquid waste treatment, gas waste treatment and thermal treatment. Site restoration area is divided into 3 regions such as the evaluation of site contamination, soil decontamination and ground water decontamination. Finally, permission, decommissioning process, cost evaluation, quality assurance and the estimation of radionuclide inventory were mentioned in the decommissioning plan and engineering area. The estimated items for each technology are applicable domestic D and D facilities, D and D problem area and contamination/requirement, classification of D and D technology, similar technology, principle and overview of technology, status, science technology needs, implementation needs, reference and contact point.

Decontamination and decommissioning technology tree and the current status of the technologies

International Nuclear Information System (INIS)

Oh, Won Zin; Won, H. J.; Kim, G. N.; Lee, K. W.; Chol, W. K.; Jung, C. H.; Kim, C. J.; Kim, S. H.; Kwon, S. O.; Chung, C. M.

2001-03-01

A technology tree diagram was developed on the basis of the necessary technologies applicable to the decontamination and decommissioning of nuclear facilities. The technology tree diagram is consist of 6 main areas such as characterization, decontamination, decommissioning and remote technology, radwaste management, site restoration, and decommissioning plan and engineering. Characterization is divided into 4 regions such as sampling and data collection, general characterization, chemical analysis and radiological analysis. Decontamination is also divided into 4 regions such as chemical decontamination, mechanical decontamination, the other decontamination technologies and new decontamination technologies. Decommissioning and remote technology area is divided into 4 regions such as cutting techniques, decommissioning technologies, new developing technologies and remote technologies. Radwaste management area is divided into 5 regions such as solid waste treatment, sludge treatment, liquid waste treatment, gas waste treatment and thermal treatment. Site restoration area is divided into 3 regions such as the evaluation of site contamination, soil decontamination and ground water decontamination. Finally, permission, decommissioning process, cost evaluation, quality assurance and the estimation of radionuclide inventory were mentioned in the decommissioning plan and engineering area. The estimated items for each technology are applicable domestic D and D facilities, D and D problem area and contamination/requirement, classification of D and D technology, similar technology, principle and overview of technology, status, science technology needs, implementation needs, reference and contact point

Radwaste requirements at a biomedical research facility

International Nuclear Information System (INIS)

Brannegan, D.P.; Wolter, W.; Merenda, J.M.; Figdor, S.K.

1993-01-01

The low-level radioactive waste (LLRW) federal legislation that was passed during the 1980s was intended to provide an orderly system of LLRW disposal as the country's three waste sites proceeded toward excluding out-of-state generators. The system was based on a regional interstate compact system. As originally envisioned, several contiguous states were to form an association (compact) with one state receiving radwaste from the compact. Everyone is aware of the difficulties that followed as attempts were made to implement these laws and to meet the prescribed milestones to avoid financial penalties. Although the states (compacts) have labored for over 12 yr along this rocky road, no compact has developed and licensed a new disposal site prior to the January 1, 1993 deadline. A recent report by the Center for the Study of American Business at Washington University in St. Louis states that open-quotes The current regional interstate compact system for disposal of low-level radioactive waste is fatally flawed on both technical and practical political grounds.close quotes Thus, the system has broken down and the three original LLRW sites closed their gates (with the possible exception of Barnwell) as planned on January 1, 1993. It would appear that the fate of LLRW will be the same as that of high-level waste (HLW); it will be stored at the site of the generator until a solution to the problem is found. For the nonutility generator, storage is an entirely new problem. It must be appreciated that almost all nonutility generators are in the business of research or medical treatment and not in the business of storing LLRW. Thus, storage represents a new turn of events and a new aspect of doing business. It also means the diversion of limited resources to a problem that should not exist. Lastly, on-site LLRW storage for the nonutility generator will also require additional regulatory approval for the handling, storage, and ongoing monitoring of this waste

A Simple Approach to Characterize Gas-Aqueous Liquid Two-phase Flow Configuration Based on Discrete Solid-Liquid Contact Electrification.

Science.gov (United States)

Choi, Dongwhi; Lee, Donghyeon; Kim, Dong Sung

2015-10-14

In this study, we first suggest a simple approach to characterize configuration of gas-aqueous liquid two-phase flow based on discrete solid-liquid contact electrification, which is a newly defined concept as a sequential process of solid-liquid contact and successive detachment of the contact liquid from the solid surface. This approach exhibits several advantages such as simple operation, precise measurement, and cost-effectiveness. By using electric potential that is spontaneously generated by discrete solid-liquid contact electrification, the configurations of the gas-aqueous liquid two-phase flow such as size of a gas slug and flow rate are precisely characterized. According to the experimental and numerical analyses on parameters that affect electric potential, gas slugs have been verified to behave similarly to point electric charges when the measuring point of the electric potential is far enough from the gas slug. In addition, the configuration of the gas-aqueous liquid two-phase microfluidic system with multiple gas slugs is also characterized by using the presented approach. For a proof-of-concept demonstration of using the proposed approach in a self-triggered sensor, a gas slug detector with a counter system is developed to show its practicality and applicability.

Radwaste storage in crystalline rocks: a natural analog

International Nuclear Information System (INIS)

Brookins, D.G.; Abashian, M.S.; Cohen, L.H.; Wollenberg, H.A.

1982-01-01

The Eldora-Bryan Stock (Colorado) intruded the 1.4-1.6 billion year old metamorphic rocks of the Idaho Springs Formation 55 million years ago. The stock may be considered a giant analog of a radwaste form without canister or engineered backfill barriers. The authors' lanthanide studies show the following: (1) The intrusive rocks remained as a closed system. (2) Lanthanide/chondrite versus ionic radius plots show only local redistribution in the immediate contact zone, and that rocks in this zone have not gained lanthanides from the magma. (3) No whole rock perturbations for the lanthanides are noted at distances greater than 3 m from the contact. Stable oxygen isotopic variations show a narrow 9.0 +- 0.3 per mille range for the intrusive rocks and whole rock values from 7.6 to 10.0 per mille for the intruded rocks. The authors conclude: (1) The Idaho Springs Formation was not penetrated by hydrothermal fluids from the Eldora-Bryan magma except possibly on a local scale within 3 m of the contact. (2) The light lanthanides may be locally redistributed in the immediate contact zone, but without additions from the magma. (3) The oxygen isotopic data imply lack of hydrothermal fluids from the magma penetrating the intruded rocks, even in the highest temperature contact zones. Whole rock data imply closed system conditions for Rb, Sr, Th, U, Pb even where mineral ages have been lowered. Data for Co, Cr, Sc, Fe, Cs also indicate retention in whole rock systems and no exchange with the magma. The combined chemical, isotopic, petrographic and theoretical data and calculations indicate suitability of rocks of the Idaho Springs Formation, and thus of many types of crystalline rocks as well, for possible use for the storage of radioactive waste

Characterization of the solid waste stream of the Tohono O'odham nation.

Science.gov (United States)

Wolf, Ann Marie A; Spitz, Anna H; Olson, Gary; Závodská, Anita; Algharaibeh, Mamoun

2003-04-01

The Tohono O'odham Nation's Solid Waste Management Program (SWMP) and the Sonora Environmental Research Institute, Inc. (SERI) completed a waste characterization study for the Tohono O'odham Nation (the Nation) to aid in the development of an effective waste management plan. The Nation has recently switched from open dumping and burning of waste to collection in dumpsters and transportation to regulated landfills. The study indicated that members of the Nation produce approximately one-third of the average amount of municipal solid waste produced per person per day in the United States. Far fewer hazardous materials and yard trimmings are found in the waste stream than is the U.S. average. Source reduction options are limited because much of the residential waste comes from packaging materials. Recycling opportunities exist but are hampered by the long distance to markets, which forces the Nation to look at innovative ways of utilizing materials on site. An education program focusing on the traditional O'odham lifestyle has been implemented to help reduce solid waste generation while improving people's health and the environment.

Report: new guidelines for characterization of municipal solid waste: the Portuguese case.

Science.gov (United States)

da Graça Madeira Martinho, Maria; Silveira, Ana Isabel; Fernandes Duarte Branco, Elsa Maria

2008-10-01

This report proposes a new set of guidelines for the characterization of municipal solid waste. It is based on an analysis of reference methodologies, used internationally, and a case study of Valorsul (a company that handles recovery and treatment of solid waste in the North Lisbon Metropolitan Area). In particular, the suggested guidelines present a new definition of the waste to be analysed, change the sampling unit and establish statistical standards for the results obtained. In these new guidelines, the sampling level is the waste collection vehicle and contamination and moisture are taken into consideration. Finally, focus is on the quality of the resulting data, which is essential for comparability of data between countries. These new guidelines may also be applicable outside Portugal because the methodology includes, besides municipal mixed waste, separately collected fractions of municipal waste. They are a response to the need for information concerning Portugal (e.g. Eurostat or OECD inquiries) and follow European Union municipal solid waste management policies (e.g. packaging waste recovery and recycling targets and the reduction of biodegradable waste going to landfill).

Solid-state characterization and dissolution properties of meloxicam-moringa coagulant-PVP ternary solid dispersions.

Science.gov (United States)

Noolkar, Suhail B; Jadhav, Namdeo R; Bhende, Santosh A; Killedar, Suresh G

2013-06-01

The effect of ternary solid dispersions of poor water-soluble NSAID meloxicam with moringa coagulant (obtained by salt extraction of moringa seeds) and polyvinylpyrrolidone on the in vitro dissolution properties has been investigated. Binary (meloxicam-moringa and meloxicam-polyvinylpyrrolidone (PVP)) and ternary (meloxicam-moringa-PVP) systems were prepared by physical kneading and ball milling and characterized by Fourier transform infrared spectroscopy, differential scanning calorimetry, and X-ray diffractometry. The in vitro dissolution behavior of meloxicam from the different products was evaluated by means of United States Pharmacopeia type II dissolution apparatus. The results of solid-state studies indicated the presence of strong interactions between meloxicam, moringa, and PVP which were of totally amorphous nature. All ternary combinations were significantly more effective than the corresponding binary systems in improving the dissolution rate of meloxicam. The best performance in this respect was given by the ternary combination employing meloxicam-moringa-PVP ratio of [1:(3:1)] prepared by ball milling, with about six times increase in percent dissolution rate, whereas meloxicam-moringa (1:3) and meloxicam-PVP (1:4) prepared by ball milling improved dissolution of meloxicam by almost 3- and 2.5-folds, respectively. The achieved excellent dissolution enhancement of meloxicam in the ternary systems was attributed to the combined effects of impartation of hydrophilic characteristic by PVP, as well as to the synergistic interaction between moringa and PVP.

New techniques for the characterization of refuse-derived fuels and solid recovered fuels.

Science.gov (United States)

Rotter, Vera Susanne; Lehmann, Annekatrin; Marzi, Thomas; Möhle, Edda; Schingnitz, Daniel; Hoffmann, Gaston

2011-02-01

Solid recovered fuel (SRF) today refers to a waste-derived fuel meeting defined quality specifications, in terms of both origin (produced from non-hazardous waste) and levels of certain fuel properties. Refuse-derived fuel (RDF) nowadays is more used for unspecified waste after a basic processing to increase the calorific value and therefore this term usually refers to the segregated, high calorific fraction of municipal solid waste (MSW), commercial or industrial wastes. In comparison with conventional fuels, both types of secondary fuel show waste of inherently varying quality and an increased level of waste-specific contaminants.The transition from RDF to SRF in the emerging national and European market requires a quality assurance system with defined quality parameters and analytical methods to ensure reliable fuel characterization. However, due to the quality requirements for RDF and SRF, the current standardized analysis methods often do not meet these practical demands. Fast test methods, which minimize personnel, financial and time efforts and which are applicable for producers as well as users can be an important supporting tool for RDF- and SRF-characterization. Currently, a fast test system based on incineration and correlation analyses which enable the determination of relevant fuel parameters is under development. Fast test methods are not aimed at replacing current standardized test methods, but have to be considered as practical supporting tools for the characterization of RDF and SRF.

Simulation of the saturation process of a radwaste storage cell

International Nuclear Information System (INIS)

Robbe, M.F.; Clouard, A.

2001-01-01

This paper presents a simulation of the saturation of the barrier and the plug of a storage cell by the surrounding host rock. Generally speaking, the unsaturated barrier and plug start saturating immediately in the vicinity of the quasi-saturated host rock. Then the saturation front propagates towards the canisters and the symmetry axis. Apart from the part in contact with the plug, the barrier is saturated at about 30 years. The part of the barrier near the plug is saturated around 80 years. If the top of the plug is saturated very soon, the part in the corner near the gallery and the symmetry axis is not completely saturated after 100 years. In the site, we observe a small desaturation during the first month, at the limit with the plug and the barrier, and especially in the corner limited by both FoCa clay pieces. This transient phenomenon may be assigned to the time difference between the immediate suction of water by the unsaturated materials and the delayed water flows coming from the saturated host rock to compensate the water suction. The purpose of this computation was at once to estimate the time necessary for the saturation of the clay layers surrounding the radwaste canisters and to evaluate the hydro-mechanical behaviour of the storage cell during the saturation process. Therefore a mechanical simulation was performed using the present hydraulic results to initiate the mechanical computation. (authors)

International comparison of safety criteria applied to radwaste repositories. Safety aspects of the post-operational phase

International Nuclear Information System (INIS)

Baltes, B.

1994-01-01

There is a generally accepted system of framework safety conditions governing the construction, operation, and post-operational monitoring of radwaste repositories. Although the development of these framework conditions may vary from country to country, the resulting criteria are based on the commonly accepted system of priciples and purposes established for ultimate radioactive waste disposal. The experience accumulated by GRS in the course of the plan approval procedure for the Konrad mine site and the safety-relevant studies performed for the planned Morsleben repository clearly show demand for further development of the safety criteria. In Germany, it is especially the safety criteria and detailed requirements filling the framework safety conditions that need revision and in-depth definition, as well as comparison and harmonisation with internationally applied criteria. These activities will particularly consider the international convention on radioactive waste management currently in preparation under the auspieces of the IAEA. (orig.) [de

The design, construction, and operation of the Integrated Radwaste Treatment System (IRTS) Drum Cell

International Nuclear Information System (INIS)

Landau, B.; Russillo, A.; Frank, D.; Garland, D.

1989-12-01

This report describes the design, construction, and the operation of the Integrated Radwaste Treatment Systems (IRTS) Drum Cell at the West Valley Demonstration Project (WVDP), West Valley, New York. The IRTS Drum Cell was designed to provide a shielded, secure storage area for the remote handling and placement of low-level Class C radioactive waste produced in the IRTS. The Drum Cell was designed to contain up to approximately 8,804 drums from decontaminated supernatant processing. This waste is to be poured into 0.27m 3 in a temperature controlled environment to ensure the cement will not be subjected to freezing and thawing cycles. A Temporary Weather Structure (TWS), a pre-engineered building, now encloses the Drum Cell and associated equipment so that remote waste-handling and placement operations can continue without regard to weather conditions. The Drum Cell was designed so that this TWS could be removed and the low-level waste entombed in place. Final disposition of this low-level waste is currently being evaluated in an Environmental Impact Statement (EIS). 10 refs., 11 figs., 1 tab

Fluid bed dryer and Aeropep solidification system. Amendment 1 to topical report

International Nuclear Information System (INIS)

1975-01-01

Information is presented on interfaces between the aerojet fluid bed dryer and the liquid radwaste system, plant ventilation system, and radioactive solid waste handling system for BWR and PWR type reactors. (U.S.)

Thermal characterization of indirectly heated axi-symmetric solid cathode electron beam gun for melting application

International Nuclear Information System (INIS)

Prakash, B.; Gupta, S.; Malik, P.; Mishra, K.K.; Jha, M.N.; Kandaswamy, E.; Martin, M.

2015-01-01

Electron beam melting gun with indirectly heated axi-symmetric solid cathode was designed, fabricated and characterized experimentally. The thermal simulation and optical analysis of the electron gun was carried out to estimate the power required to achieve the emission temperature of the solid cathode, to obtain the temperature distribution in the assembly and the beam transportation. On the basis of the thermal simulation and electron optics, the electron gun design was finalised. The electron gun assembly was fabricated and installed in the vacuum chamber for carrying out the experiment to find the actual temperature distribution. Thermocouple and two colour pyrometer were used to measure the temperature at various locations in the electron gun. The attenuation effect of the viewing port glass of the vacuum chamber was compensated in the final reading of the temperature measured by the pyrometer. The temperature of solid cathode obtained by the experiment was found to be 2800K which is the emission temperature of solid cathode. (author)

Characterization and Design of Zeolite Catalysts Solid Acidity, Shape Selectivity and Loading Properties

CERN Document Server

Niwa, Miki; Okumura, Kazu

2010-01-01

Zeolites are microporous, aluminosilicate minerals commonly used as commercial adsorbents. Zeolite-based catalysts are used by industrial chemical companies in the interconversion of hydrocarbons and the alkylation of aromatic compounds. The current book deals with the characterization of specific properties of Zeolites and calculations for the design of catalysts. Measurements and utilization of solid acidity, shape selectivity, and loading properties, that are three prominent properties of a Zeolite catalyst, are treated in detail. These features concern chemical vapor deposition of silica, shape selectivity, loading properties, solid activity, Brønsted or Lewis character, ammonia temperature programmed desorption, control of the pore-opening size by chemical vapor deposition of silica and XAFS analysis of metals being highly dispersed inside and outside a framework.

Characterization and physical stability of spray dried solid dispersions of probucol and PVP-K30

DEFF Research Database (Denmark)

Thybo, Pia; Pedersen, Betty L; Hovgaard, Lars

2008-01-01

The main purpose of this study was to obtain stable, well-characterized solid dispersions (SDs) of amorphous probucol and polyvinylpyrrolidone K-30 (PVP-K30) with improved dissolution rates. A secondary aim was to investigate the flow-through dissolution method for in-vitro dissolution measuremen...

Solid Phase Characterization of Tank 241-AY-102 Annulus Space Particulate

Energy Technology Data Exchange (ETDEWEB)

Cooke, G. A.

2013-01-30

The Special Analytical Studies Group at the 222-S Laboratory (222-S) examined the particulate recovered from a series of samples from the annular space of tank 241-AY-102 (AY-102) using solid phase characterization (SPC) methods. These include scanning electron microscopy (SEM) using the ASPEX®1 scanning electron microscope, X-ray diffraction (XRD) using the Rigaku®2 MiniFlex X-ray diffractometer, and polarized light microscopy (PLM) using the Nikon®3 Eclipse Pol optical microscope. The SEM is equipped with an energy dispersive X-ray spectrometer (EDS) to provide chemical information.

Groundwater age and lifetime expectancy modelling approach for site characterization and performance assessment of radwaste repository in clay formation

International Nuclear Information System (INIS)

Cornaton, F.; Perrochet, P.; Benabderrahmane, H.

2010-01-01

Document available in extended abstract form only. A deep geological repository of high level and long lived radwaste requires an understanding of the far field and near field groundwater flow and of the transport properties, at actual and future climatic conditions. Andra, French National radioactive waste management Agency, is developing since last 15 years an integrated multi-scale hydrogeological model of whole Paris basin of 200000 km 2 of area (regional scale) to produce a regional flow field associated to groundwater behavior. It includes locally the Meuse/Haute Marne clay site of about 250 km 2 of area in the eastern part of the Paris basin that was chosen for the emplacement of a repository. The Callovo-Oxfordian host formation is a clay layer characterized by a very low permeability of the order 10 -14 m/s, a mean thickness of 130 m at about 500 m depth, and is embedded by calcareous aquifer formations (Dogger and Oxfordian). The hydrogeological conceptual model is based on stratigraphic and petro-physic modeling of the Paris basin and is accounting for the structural, geological, hydrogeological and geochemical data in an integrated way. This model represents 27 hydrogeological units at the scale of the Paris Basin, and it is refined at the scale of the sector to represent 27 different layers that range in age from the Trias to the Portlandian. The finite element flow and transport simulator Ground Water (GW) is used to solve for groundwater flow at steady-state in a 3 Million elements model, considering current climatic conditions. The model is calibrated against about 1250 hydraulic head measurements, and results in maximum absolute hydraulic head differences of 20 meters at the regional scale and 3 meters at the local scale. The calibrated reference model includes transmissive major faults as well as structures acting as barrier to flow. Groundwater age (the time elapsed since recharge) and lifetime expectancy (the time remaining prior to exit) are

Advanced methods for incineration of solid, burnable LLW and melting for recycling of scrap metals

International Nuclear Information System (INIS)

Krause, G.; Lorenzen, J.; Lindberg, M.; Olsson, L.; Wirendal, B.

2003-01-01

Radioactive contaminated waste is a great cost factor for nuclear power plants and other nuclear industry. On the deregulated electricity market the price on produced kWh is an important competition tool. Therefore the waste minimisation and volume reduction has given highest priority by many power producers in the process to achieve savings and hence low production cost. Studsvik RadWaste AB in Nykoeping, Sweden, is a company specialised in volume reduction of LLW, as solid combustible waste and as scrap metal for melting and recycling. The treatment facility in Sweden offers this kind of services - together with segmentation and decontamination when necessary - for several customers from Europe, Japan and USA. In addition to these treatment services a whole spectrum of services like transportation, measurement and safeguard, site assistance, industrial cleaning and decontamination in connection with demolition at site is offered from the Studsvik company. (orig.)

PREPARATION AND CHARACTERIZATION OF SOLID ELECTROLYTES: FUEL CELL APPLICATIONS

Energy Technology Data Exchange (ETDEWEB)

Rambabu Bobba; Josef Hormes; T. Wang; Jaymes A. Baker; Donald G. Prier; Tommy Rockwood; Dinesha Hawkins; Saleem Hasan; V. Rayanki

1997-12-31

The intent of this project with Federal Energy Technology Center (FETC)/Morgantown Energy Technology Center (METC) is to develop research infrastructure conductive to Fuel Cell research at Southern University and A and M College, Baton Route. A state of the art research laboratory (James Hall No.123 and No.114) for energy conversion and storage devices was developed during this project duration. The Solid State Ionics laboratory is now fully equipped with materials research instruments: Arbin Battery Cycling and testing (8 channel) unit, Electrochemical Analyzer (EG and G PAR Model 273 and Solartron AC impedance analyzer), Fuel Cell test station (Globe Tech), Differential Scanning Calorimeter (DSC-10), Thermogravimetric Analyzer (TGA), Scanning Tunneling Microscope (STM), UV-VIS-NIR Absorption Spectrometer, Fluorescence Spectrometer, FT-IR Spectrometer, Extended X-ray Absorption Fine Structure (EXAFS) measurement capability at Center for Advanced Microstructure and Devices (CAMD- a multimillion dollar DOE facility), Glove Box, gas hood chamber, high temperature furnaces, hydraulic press and several high performance computers. IN particular, a high temperature furnace (Thermodyne 6000 furnace) and a high temperature oven were acquired through this project funds. The PI Dr. R Bobba has acquired additional funds from federal agencies include NSF-Academic Research Infrastructure program and other DOE sites. They have extensively used the multimillion dollar DOE facility ''Center'' for Advanced Microstructures and Devices (CAMD) for electrochemical research. The students were heavily involved in the experimental EXAFS measurements and made use of their DCM beamline for EXAFS research. The primary objective was to provide hands on experience to the selected African American undergraduate and graduate students in experimental energy research.The goal was to develop research skills and involve them in the Preparation and Characterization of Solid

Characterization of the polymer Durolon as a solid state nuclear track detector

International Nuclear Information System (INIS)

Pugliesi, Fabio

2008-01-01

The polymer Durolon has been characterized as a solid state nuclear track detector. In these detectors a track, resulting from the damages in its molecular structure, induced by a heavy charged particle, is the testimony of the passage of the particle through the polymer. In order to characterize the Durolon the track diameter, track production rate, light transmission through the polymer and the critical angle of incidence of the particle have been studied. The main objective of such studies was to provide the necessary subsidies to understand the information registered. The damages have been induced by alpha particles from the nuclear reaction 10 B(n,α) 7 Li, by irradiating a boron screen in a thermal neutron field from an experimental facility installed in the beam-hole 08 of the IEA-R1 nuclear research reactor of IPEN-CNEN/SP. The study of the parameters have been performed by using a digital system developed in the present work. Its use has provided a higher quality and quickness regarding data acquisition and data analysis as well as the opportunity to quantify several other parameters regarding the imaging formation theory in solid state nuclear track detectors. The characteristics of the Durolon have been compared with the ones of two other detectors Makrofol-E and Makrofol-DE and have demonstrated its potentiality to use. (author)

Characterization of municipal solid waste from the main landfills of Havana city.

Science.gov (United States)

Espinosa Lloréns, Ma Del C; Torres, Matilde López; Alvarez, Haydee; Arrechea, Alexis Pellón; García, Jorge Alejandro; Aguirre, Susana Díaz; Fernández, Alejandro

2008-01-01

The city of Havana, the political, administrative and cultural centre of Cuba, is also the centre of many of the economic activities of the nation: industries, services, scientific research and tourism. All of these activities contribute to the generation of municipal solid waste (MSW), which also impact other Cuban cities. Inadequate handling of waste and the lack of appropriate and efficient solutions for its final disposal and treatment increase the risk and possibility of contamination. The main difficulty in the development of a system of management of MSW lies in the lack of knowledge of the chemical composition of the waste that is generated in the country as a whole, and especially in Havana, where solid waste management decisions are made. The present study characterizes MSW in Havana city during 2004. The Calle 100, Guanabacoa and Ocho Vías landfills were selected for physical-chemical characterization of MSW, as they are the three biggest landfills in the city. A total of 16 indicators were measured, and weather conditions were recorded. As a result, the necessary information regarding the physical-chemical composition of the MSW became available for the first time in Cuba. The information is essential for making decisions regarding the management of waste and constitutes a valuable contribution to the Study on Integrated Management Plan of MSW in Havana.

Characterization of municipal solid waste from the main landfills of Havana city

International Nuclear Information System (INIS)

Espinosa Llorens, Ma. del C; Lopez Torres, Matilde; Alvarez, Haydee; Pellon Arrechea, Alexis; Garcia, Jorge Alejandro; Diaz Aguirre, Susana; Fernandez, Alejandro

2008-01-01

The city of Havana, the political, administrative and cultural centre of Cuba, is also the centre of many of the economic activities of the nation: industries, services, scientific research and tourism. All of these activities contribute to the generation of municipal solid waste (MSW), which also impact other Cuban cities. Inadequate handling of waste and the lack of appropriate and efficient solutions for its final disposal and treatment increase the risk and possibility of contamination. The main difficulty in the development of a system of management of MSW lies in the lack of knowledge of the chemical composition of the waste that is generated in the country as a whole, and especially in Havana, where solid waste management decisions are made. The present study characterizes MSW in Havana city during 2004. The Calle 100, Guanabacoa and Ocho Vias landfills were selected for physical-chemical characterization of MSW, as they are the three biggest landfills in the city. A total of 16 indicators were measured, and weather conditions were recorded. As a result, the necessary information regarding the physical-chemical composition of the MSW became available for the first time in Cuba. The information is essential for making decisions regarding the management of waste and constitutes a valuable contribution to the Study on Integrated Management Plan of MSW in Havana

Solid State Division

International Nuclear Information System (INIS)

Green, P.H.; Watson, D.M.

1989-08-01

This report contains brief discussions on work done in the Solid State Division of Oak Ridge National Laboratory. The topics covered are: Theoretical Solid State Physics; Neutron scattering; Physical properties of materials; The synthesis and characterization of materials; Ion beam and laser processing; and Structure of solids and surfaces

Results of Characterization and Retrieval Testing on Tank 241-C-110 Heel Solids

Energy Technology Data Exchange (ETDEWEB)

Callaway, William S.

2013-09-30

Nine samples of heel solids from tank 241-C-110 were delivered to the 222-S Laboratory for characterization and dissolution testing. After being drained thoroughly, the sample solids were primarily white to light-brown with minor dark-colored inclusions. The maximum dimension of the majority of the solids was <2 mm; however, numerous pieces of aggregate, microcrystalline, and crystalline solids with maximum dimensions ranging from 5-70 mm were observed. In general, the larger pieces of aggregate solids were strongly cemented. Natrophosphate [Na{sub 7}F(PO{sub 4}){sub 2}°19H{sub 2}O] was the dominant solid phase identified in the heel solids. Results of chemical analyses suggested that 85-87 wt% of the heel solids were the fluoridephosphate double salt. The average bulk density measured for the heel solids was 1.689 g/mL; the reference density of natrophosphate is 1.71 g/mL. Dissolution tests on composite samples indicate that 94 to 97 wt% of the tank 241-C-110 heel solids can be retrieved by dissolution in water. Dissolution and recovery of the soluble components in 1 kg (0.59 L) of the heel solids required the addition of ≈9.5 kg (9.5 L) of water at 15 °C and ≈4.4 kg (4.45 L) of water at 45 °C. Calculations performed using the Environmental Simulation Program indicate that dissolution of the ≈0.86 kg of natrophosphate in each kilogram of the tank 241-C-110 heel solids would require ≈9.45 kg of water at 15 °C and ≈4.25 kg of water at 45 °C. The slightly larger quantities of water determined to be required to retrieve the soluble components in 1 kg of the heel solids are consistent with that required for the dissolution of solids composed mainly of natrophosphate with a major portion of the balance consisting of highly soluble sodium salts. At least 98% of the structural water, soluble phosphate, sodium, fluoride, nitrate, carbonate, nitrite, sulfate, oxalate, and chloride in the test composites was dissolved and recovered in the

Solid State Division

Energy Technology Data Exchange (ETDEWEB)

Green, P.H.; Watson, D.M. (eds.)

1989-08-01

This report contains brief discussions on work done in the Solid State Division of Oak Ridge National Laboratory. The topics covered are: Theoretical Solid State Physics; Neutron scattering; Physical properties of materials; The synthesis and characterization of materials; Ion beam and laser processing; and Structure of solids and surfaces. (LSP)

Liquid radwaste processing with spiral wound reverse osmosis

International Nuclear Information System (INIS)

Sengupta, S.K.; Buckley, L.P.; Rimpelainen, S.; Tremblay, A.Y.

1996-05-01

Two different reverse osmosis systems were investigated. The first was a 50-element plant-scale system that is used to treat 2200 m 3 of AECL liquid radwastes annually.It uses thin-film composite (TFC) membranes and operates at an applied pressure of 2760 kPa, with a fixed crossflow of about 40 L/min. The other system uses the same thin-film composite membranes for waste processing but is a two-element pilot-scale system. It is operated at pressures m ranging between 1500 and 7000 kPa, at a fixed crossflow of 55 L/min. The average lifetime of the thin-film composite membranes in the plant-scale processing application at AECL is about 3000 h. After this service life has expired the rejection efficiency declines rapidly from 99.5% to about 95% as the membranes become impaired from chemical cleaning procedures that are required after each 100 m 3 of waste is treated. The permeation flux for the plant-scale system decreases from about 2.2 L/min/element to below 0.5 L/min/element at the end of the membrane's useful service life. The plant-scale membrane elements, fouled by an assortment of chemicals including calcium phosphate and various organics, were successfully regenerated by exposing them to a threestep chemical cleaning procedure, using detergent, HCI, and an alkaline-based cleaning with EDTA. The three-step procedure was successful in elevating the flux from 0.5 L/min for the spent membrane to 1.2 L/min after cleaning. The 1.2-L/min postcleaning flux could be maintained provided that the crossflow velocity remained high. The decontamination factor (DF) for cesium for the plant-scale system, decreased from about 100 when the membranes were new, to about 30 after they were replaced. The strontium DF was unaffected by the applied pressure. 9 refs., 1 tab., 6 figs

Solid waste characterization and recycling potential for a university campus

International Nuclear Information System (INIS)

Armijo de Vega, Carolina; Ojeda Benitez, Sara; Ramirez Barreto, Ma. Elizabeth

2008-01-01

Integrated waste management systems are one of the greatest challenges for sustainable development. For these systems to be successful, the first step is to carry out waste characterization studies. In this paper are reported the results of a waste characterization study performed in the Campus Mexicali I of the Autonomous University of Baja California (UABC). The aim of this study was to set the basis for implementation of a recovery, reduction and recycling waste management program at the campus. It was found that the campus Mexicali I produces 1 ton of solid wastes per day; more than 65% of these wastes are recyclable or potentially recyclable. These results showed that a program for segregation and recycling is feasible on a University Campus. The study also showed that the local market for recyclable waste, under present conditions - number of recycling companies and amounts of recyclables accepted - can absorb all of these wastes. Some alternatives for the potentially recyclables wastes are discussed. Finally some strategies that could be used to reduce waste at the source are discussed as well

Solid Phase Characterization of Tank 241-AY-102 Annulus Space Particulate

International Nuclear Information System (INIS)

Cooke, G. A.

2013-01-01

The Special Analytical Studies Group at the 222-S Laboratory (222-S) examined the particulate recovered from a series of samples from the annular space of tank 241-AY-102 (AY-102) using solid phase characterization (SPC) methods. These include scanning electron microscopy (SEM) using the ASPEX(R)1 scanning electron microscope, X-ray diffraction (XRD) using the Rigaku(R)2 MiniFlex X-ray diffractometer, and polarized light microscopy (PLM) using the Nikon(R)3 Eclipse Pol optical microscope. The SEM is equipped with an energy dispersive X-ray spectrometer (EDS) to provide chemical information

Cocrystal of Ibuprofen–Nicotinamide: Solid-State Characterization and In Vivo Analgesic Activity Evaluation

Directory of Open Access Journals (Sweden)

Yori Yuliandra

2018-06-01

Full Text Available Ibuprofen is classified as a BCS class II drug which has low solubility and high permeability. We conducted the formation of the cocrystalline phase of ibuprofen with coformer nicotinamide to increase its solubility. The purpose of this study was to characterize the solid state of cocrystalline phase of ibuprofen-nicotinamide, determine the solubility, and evaluate its in vivo analgesic activity. The cocrystal of ibuprofen-nicotinamide was prepared by a slow evaporation method. The solid-state characterization was conducted by powder X-ray diffraction (PXRD analysis, differential thermal analysis (DTA, and scanning electron microscopy (SEM. To investigate the in vivo analgesic activity, 28 male Swiss-Webster mice were injected with acetic acid 0.5% following oral administration of intact ibuprofen, physical mixture, and its cocrystalline phase with nicotinamide (equivalent to 26 mg/kg ibuprofen. The number of writhes was counted, and pain inhibition was calculated. All data were analyzed with one-way ANOVA followed by Duncan’s Multiple Range Test (95% confidence interval. The results revealed that a new cocrystalline phase was successfully formed. The solubility testing showed that the cocrystal formation enhanced the solubility significantly as compared with the physical mixture and intact ibuprofen. A significant increase in the analgesic activity of cocrystal ibuprofen-nicotinamide was also confirmed.

Geological evaluation of spent fuel storage and low-intermediate level radwaste disposal in the site of NPP candidate

International Nuclear Information System (INIS)

Sucipta; Yatim, S.; Martono, H.; Pudyo, A.

1997-01-01

Based on the consideration of techno-economy and environmental safety, the radioactive waste treatment installation (RWI), interim storage of spen fuel (ISSF) and low-intermediate level disposal shall be sited in the surrounding of NPP area. The land suitability of NPP's site candidate at Muria Peninsula as spent fuel storage and low-intermediate level radwaste disposal need to be studied. Site selection was conducted by overlay method and scoring method, and based on safety criteria which include geological and environmental aspects. Land evaluation by overlay method has given result a potential site which have highest suitable land at surrounding of borehole L-15 about 17.5 hectares. Land evaluation by scoring method has given result two land suitability classes, i.e. moderate suitability class (includes 14 borehole) and high suitability class, include borehole L-2, L-14 and L-15 (author)

Characterization and morphology of solids suspended in rain water; Caracterizacion y morfologia de solidos suspendidos en agua de lluvia

Energy Technology Data Exchange (ETDEWEB)

Iturbe G, J.L.; Lopez M, B.E.; Torre O, J. De la [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, Mexico D.F. (Mexico)

2000-07-01

This work presents the results obtained from the analysis of rain water in Mexico. The study treats over the characterization and morphology of the solids suspended in form of particles in the atmosphere. The solids suspended were obtained of the pluvial precipitations after these have been centrifuged. Subsequently of the separation, the particulate matter was analysed by Sem and X-ray dispersive energy.

Characterization of domestic graywater and graywater solids.

Science.gov (United States)

Sievers, Jan Christian; Londong, Jörg

2018-03-01

The knowledge of loads and concentrations is fundamental for the design of graywater treatment units, but the data on the characteristics of graywater and in particular graywater solids are weak. As general design values regarding graywater treatment facilities are not available for Germany, the objective of this article is to elaborate the characteristics of graywater and graywater solids. This paper describes the results of six sampling campaigns carried out on graywater systems in the German cities Berlin, Lübeck and Kiel. All graywater samples were collected proportional to the flow and the graywater solids were gathered separately. The collected data include graywater volumes and characteristics regarding the organic pollution (chemical oxygen demand (COD), 5-day biochemical oxygen demand (BOD 5 )) and nutrients (total nitrogen (TN), total phosphorus (TP)). The graywater volume fluctuated depending on the location. The specific average flow was 68 litre per inhabitant per day (L/inh.d). Inhabitant-specific loads of 49.3 gCOD t /inh·d, 28 gBOD 5 /inh.d, 1 gTN t /inh.d and 0.38 gTP t /inh.d (subscript 't' = total) were found. Information about the composition of graywater solids in terms of quantity and quality is seriously lacking. Therefore, graywater solids were examined with respect to organic matter (COD) and nutrients (TN, TP). The contribution of graywater solids with particle sizes over 200 microns in relation to the total inhabitant-specific load was approximately 3-8% depending on the parameter. The qualitative and quantitative characteristics of the investigated graywater fractions may serve as a base for the estimation of design values.

Non-Destructive Testing for Control of Radioactive Waste Package

Science.gov (United States)

Plumeri, S.; Carrel, F.

2015-10-01

Characterization and control of radioactive waste packages are important issues in the management of a radioactive waste repository. Therefore, Andra performs quality control inspection on radwaste package before disposal to ensure the compliance of the radwast characteristics with Andra waste disposal specifications and to check the consistency between Andra measurements results and producer declared properties. Objectives of this quality control are: assessment and improvement of producer radwaste packages quality mastery, guarantee of the radwaste disposal safety, maintain of the public confidence. To control radiological characteristics of radwaste package, non-destructive passive methods (gamma spectrometry and neutrons counting) are commonly used. These passive methods may not be sufficient, for instance to control the mass of fissile material contained inside radwaste package. This is particularly true for large concrete hull of heterogeneous radwaste containing several actinides mixed with fission products like 137Cs. Non-destructive active methods, like measurement of photofission delayed neutrons, allow to quantify the global mass of actinides and is a promising method to quantify mass of fissile material. Andra has performed different non-destructive measurements on concrete intermediate-level short lived nuclear waste (ILW-SL) package to control its nuclear material content. These tests have allowed Andra to have a first evaluation of the performance of photofission delayed neutron measurement and to identify development needed to have a reliable method, especially for fissile material mass control in intermediate-level long lived waste package.

Risperidone – Solid-state characterization and pharmaceutical compatibility using thermal and non-thermal techniques

Energy Technology Data Exchange (ETDEWEB)

Daniel, Josiane Souza Pereira; Veronez, Isabela Pianna; Rodrigues, Larissa Lopes [Laboratório de Análise e Caracterização de Fármacos – LACFar, Instituto de Química, Universidade Federal de Alfenas, Alfenas, Minas Gerais (Brazil); Trevisan, Marcello G. [Laboratório de Análise e Caracterização de Fármacos – LACFar, Instituto de Química, Universidade Federal de Alfenas, Alfenas, Minas Gerais (Brazil); National Institute of Bioanalytics Science and Technology – INCTBio, Institute of Chemistry – UNICAMP, 13084-653, Campinas, São Paulo (Brazil); Garcia, Jerusa Simone, E-mail: jerusa.garcia@unifal-mg.edu.br [Laboratório de Análise e Caracterização de Fármacos – LACFar, Instituto de Química, Universidade Federal de Alfenas, Alfenas, Minas Gerais (Brazil)

2013-09-20

Highlights: • DSC was used to characterize Risperidone and study its compatibility with excipients. • FT-IR associated with PCA was used to complement DSC data. • LC analyzes confirmed the DSC and FT-IR/PCA results. • Risperidone was incompatible with three among five excipients evaluated. - Abstract: A full solid-state characterization of risperidone was conducted using differential scanning calorimetry (DSC), thermogravimetry (TG), powder X-ray diffraction (PXRD), Fourier transform infrared spectroscopy (FT-IR) and scanning electron microscopy (SEM) to examine its physicochemical properties and polymorphism. The primary aim of this work was to study the compatibility of risperidone with pharmaceutical excipients using DSC to obtain and compare the curves of the active pharmaceutical ingredient (API) and the excipients with their 1:1 (w/w) binary mixtures. These same binary mixtures were turned to room temperature and analyzed by FT-IR combined with principal component analysis (PCA) to evaluate solid-state incompatibilities. The chemical incompatibilities of these samples were verified using a stability-indicating liquid chromatography (LC) method to assay for the API and evaluate the formation of degradation products. All of these methods showed incompatibilities between risperidone and the excipients magnesium stearate, lactose and cellulose microcrystalline.

Low-level radioactive waste processing at nuclear power plants

International Nuclear Information System (INIS)

1992-12-01

The Solid Radwaste Processing Source Book is presented as a supplement to the Liquid Radwaste Source Book released in 1990 and updated in 1991. The publication is the result of an industry-wide survey, and is intended as a resource for technical and managerial decisions involving of the processing of solid radioactive waste including ''wet'' and ''dry'' active waste as found at both Pressurized and Boiling Water Reactor sites. In addition to information on processes, vendors, volumes, and in-plant management activities, technology under consideration for future use and computer applications are listed. Together with key personnel and contact information contained in the Liquid Source Books, the collected data will be of great use when seeking specific, unbiased experience on which to base decisions related to so processing, disposal policy, or potential economic and regulatory impact

Characterization of proton exchange membrane materials for fuel cells by solid state nuclear magnetic resonance

Energy Technology Data Exchange (ETDEWEB)

Kong, Zueqian [Iowa State Univ., Ames, IA (United States)

2010-01-01

Solid-state nuclear magnetic resonance (NMR) has been used to explore the nanometer-scale structure of Nafion, the widely used fuel cell membrane, and its composites. We have shown that solid-state NMR can characterize chemical structure and composition, domain size and morphology, internuclear distances, molecular dynamics, etc. The newly-developed water channel model of Nafion has been confirmed, and important characteristic length-scales established. Nafion-based organic and inorganic composites with special properties have also been characterized and their structures elucidated. The morphology of Nafion varies with hydration level, and is reflected in the changes in surface-to-volume (S/V) ratio of the polymer obtained by small-angle X-ray scattering (SAXS). The S/V ratios of different Nafion models have been evaluated numerically. It has been found that only the water channel model gives the measured S/V ratios in the normal hydration range of a working fuel cell, while dispersed water molecules and polymer ribbons account for the structures at low and high hydration levels, respectively.

The new MAW scrap processing facility

International Nuclear Information System (INIS)

Kueppers, L.

1994-01-01

The shielded bunker for heat-generating waste attached to the MAW scrap processing cell will be modified and extended to comprise several MAW scrap processing cells of enhanced throughput capacity, and a new building to serve as an airlock and port for acceptance of large shipping casks (shipping cask airlock, TBS). The new facility is to process scrap from decommissioned nuclear installations, and in addition radwaste accrued at operating plants of utilities. This will allow efficient and steady use of the new MAW scrap processing facility. The planning activities for modification and extension are based on close coordination between KfK and the GNS mbH, in order to put structural dimensioning and capacity planning on a realistic basis in line with expected amounts of radwaste from operating nuclear installations of utilities. The paper indicates the currently available waste amount assessments covering solid radwaste (MAW) from the decommissioning of the WAK, MZFR, and KNK II, and existing waste amounts consisting of core internals of German nuclear power plant. The figures show that the MAW scrap processing facility will have to process an overall bulk of about 1100 Mg of solid waste over the next ten years to come. (orig./HP) [de

Solid-state characterization of the HIV protease inhibitor

CERN Document Server

Kim, Y A

2002-01-01

The LB71350, (3S, 4R)-Epoxy-(5S)-[[N-(1-methylethoxy) carbonyl]-3-(methylsulfonyl)-L-valinyl]amin= o]-N-[2-methyl-(1R)-[(phenyl)carbonyl]propyl-6-phenylhexanamide, is a novel HIV protease inhibitor. Its equilibrium solubility at room temperature was less than 40 mu g/mL. It was speculated that the low aqueous solubility might be due to the high crystalline lattice energy resulting from intermolecular hydrogen bonds. The present study was carried out to learn the solid-state characteristics of LB71350 using analytical methods such as NMR, FT-IR and XRD. sup 1 sup 3 C Solid-state NMR, solution NMR, and FT-IR spectra of the various solid forms of LB71350 were used to identify the conformation and structure of the solid forms. The chemical shifts of sup 1 sup 3 C solid-state NMR spectra suggest that the crystalline form might have 3 intermolecular hydrogen bondings between monomers.

Research and development of radioactive waste treatment methods

International Nuclear Information System (INIS)

Nguyen Thi Nang

2000-01-01

The Nuclear Research Institute (NRI) uses the reactor for research, training, isotope production and activation analyses. NRI generates about 150 m 3 of liquid and 5 m 3 of solid wastes every year. The researched methods applied to treatment of radwastes are coagulation-precipitation and two steps ion-exchange for liquid waste and compaction for solid waste are described. (author)

Characterization of the constitutive behavior of municipal solid waste considering particle compressibility.

Science.gov (United States)

Lü, Xilin; Zhai, Xinle; Huang, Maosong

2017-11-01

This paper presents a characterization of the mechanical behavior of municipal solid waste (MSW) under consolidated drained and undrained triaxial conditions. The constitutive model was established based on a deviatoric hardening plasticity model. A power form function and incremental hyperbolic form function were proposed to describe the shear strength and the hardening role of MSW. The stress ratio that corresponds to the zero dilatancy was not fixed but depended on mean stress, making the Rowe's rule be able to describe the stress-dilatancy of MSW. A pore water pressure reduction coefficient, which attributed to the compressibility of a particle and the solid matrix, was introduced to the effective stress formulation to modify the Terzaghi's principle. The effects of particle compressibility and solid matrix compressibility on the undrained behavior of MSW were analyzed by parametric analysis, and the changing characteristic of stress-path, stress-strain, and pore-water pressure were obtained. The applicability of the proposed model on MSW under drained and undrained conditions was verified by model predictions of three triaxial tests. The comparison between model simulations and experiments indicated that the proposed model can capture the observed different characteristics of MSW response from normal soil, such as nonlinear shear strength, pressure dependent stress dilatancy, and the reduced value of pore water pressure. Copyright © 2017 Elsevier Ltd. All rights reserved.

Physicochemical characterization and dissolution enhancement of loratadine by solid dispersion technique

International Nuclear Information System (INIS)

Bandari, Suresh; Jadav, Subash; Eedara, Basanth Babu; Jukanti, Raju; Veerareddy, Prabhakar Reddy

2013-01-01

The purpose of this investigation was to enhance the dissolution rate of loratadine using polyethylene glycol 6000 (PEG) solid dispersions (SDs). The solubility behavior of loratadine in the presence of polyethylene glycol 4000 and polyethylene glycol 6000 in water showed linear increase with increasing concentrations of PEG, indicating A L type solubility diagrams. SDs of loratadine with PEG 6000 were prepared at 1 : 1, 1 : 3, 1 : 5, 1 : 7 and 1 : 9 ratios by the solvent evaporation method. Solid dispersions were characterized for drug content, dissolution behavior and for physicochemical characteristics. The dissolution rate of loratadine was enhanced rapidly with increasing concentrations of PEG 6000 in SDs. Fourier transform infrared (FTIR) studies showed the stability of loratadine and the absence of a well-defined loratadine - PEG 6000 interaction. Differential scanning calorimetry (DSC) and X-ray powder diffractometry (XRD) studies revealed the amorphous state of loratadine in SDs of loratadine with PEG 6000 which was further confirmed from scanning electron microscopy (SEM) studies. The flow properties of the blend, physical characteristics and disintegration time of the tablets formulated indicated that PEG 6000 SD can be used to formulate fast release loratadine tablets

Physicochemical characterization and dissolution enhancement of loratadine by solid dispersion technique

Energy Technology Data Exchange (ETDEWEB)

Bandari, Suresh; Jadav, Subash; Eedara, Basanth Babu; Jukanti, Raju; Veerareddy, Prabhakar Reddy [St. Peter’s Institute of Pharmaceutical Sciences, Warangal (India)

2013-01-15

The purpose of this investigation was to enhance the dissolution rate of loratadine using polyethylene glycol 6000 (PEG) solid dispersions (SDs). The solubility behavior of loratadine in the presence of polyethylene glycol 4000 and polyethylene glycol 6000 in water showed linear increase with increasing concentrations of PEG, indicating A{sub L} type solubility diagrams. SDs of loratadine with PEG 6000 were prepared at 1 : 1, 1 : 3, 1 : 5, 1 : 7 and 1 : 9 ratios by the solvent evaporation method. Solid dispersions were characterized for drug content, dissolution behavior and for physicochemical characteristics. The dissolution rate of loratadine was enhanced rapidly with increasing concentrations of PEG 6000 in SDs. Fourier transform infrared (FTIR) studies showed the stability of loratadine and the absence of a well-defined loratadine - PEG 6000 interaction. Differential scanning calorimetry (DSC) and X-ray powder diffractometry (XRD) studies revealed the amorphous state of loratadine in SDs of loratadine with PEG 6000 which was further confirmed from scanning electron microscopy (SEM) studies. The flow properties of the blend, physical characteristics and disintegration time of the tablets formulated indicated that PEG 6000 SD can be used to formulate fast release loratadine tablets.

Highly Quantitative Electrochemical Characterization of Non-Aqueous Electrolytes & Solid Electrolyte Interphases

Energy Technology Data Exchange (ETDEWEB)

Sergiy V. Sazhin; Kevin L. Gering; Mason K. Harrup; Harry W. Rollins

2012-10-01

The methods to measure solid electrolyte interphase (SEI) electrochemical properties and SEI formation capability of non-aqueous electrolyte solutions are not adequately addressed in the literature. And yet, there is a strong demand in new electrolyte generations that promote stabilized SEIs and have an influence to resolve safety, calendar life and other limitations of Li-ion batteries. To fill this gap, in situ electrochemical approach with new descriptive criteria for highly quantitative characterization of SEI and electrolytes is proposed. These criteria are: SEI formation capacity, SEI corrosion rate, SEI maintenance rate, and SEI kinetic stability. These criteria are associated with battery parameters like irreversible capacity, self-discharge, shelf-life, power, etc. Therefore, they are especially useful for electrolyte development and standard fast screening, allowing a skillful approach to narrow down the search for the best electrolyte. The characterization protocol also allows retrieving information on interfacial resistance for SEI layers and the electrochemical window of electrolytes, the other important metrics of characterization. The method validation was done on electrolyte blends containing phosphazenes, developed at Idaho National Laboratory, as 1.2M LiPF6 [80 % EC-MEC (2:8) (v/v) + 20% Phosphazene variety] (v/v), which were targeted for safer electrolyte variations.

Characterization of degradation products of amorphous and polymorphic forms of clopidogrel bisulphate under solid state stress conditions

DEFF Research Database (Denmark)

Raijada, Dhara K; Prasad, Bhagwat; Paudel, Amrit

2010-01-01

The present study deals with the stress degradation studies on amorphous and polymorphic forms of clopidogrel bisulphate. The objective was to characterize the degradation products and postulate mechanism of decomposition of the drug under solid state stress conditions. For that, amorphous form, ...

characterization and composition analysis of municipal solid waste

African Journals Online (AJOL)

userpc

ABSTRACT. Municipal Solid Waste (MSW) is produced through human activities and in the last two ... Solid waste samples were collected and analysed from the four major dumpsites in ..... Technology, Ueberlandstrasse 133,. Switzerland.

Production and Characterization of Lipases by Two New Isolates of Aspergillus through Solid-State and Submerged Fermentation

Science.gov (United States)

Colla, Luciane Maria; Ficanha, Aline M. M.; Rizzardi, Juliana; Bertolin, Telma Elita; Reinehr, Christian Oliveira; Costa, Jorge Alberto Vieira

2015-01-01

Due to the numerous applications of lipases in industry, there is a need to study their characteristics, because lipases obtained from different sources may present different properties. The aim of this work was to accomplish the partial characterization of lipases obtained through submerged fermentation and solid-state fermentation by two species of Aspergillus. Fungal strains were isolated from a diesel-contaminated soil and selected as good lipases producers. Lipases obtained through submerged fermentation presented optimal activities at 37°C and pH 7.2 and those obtained through solid-state fermentation at 35°C and pH 6.0. The enzymes produced by submerged fermentation were more temperature-stable than those obtained by solid-state fermentation, presenting 72% of residual activity after one hour of exposition at 90°C. Lipases obtained through submerged fermentation had 80% of stability in acidic pH and those obtained through solid-state fermentation had stability greater than 60% in alkaline pH. PMID:26180809

Production and Characterization of Lipases by Two New Isolates of Aspergillus through Solid-State and Submerged Fermentation

Directory of Open Access Journals (Sweden)

Luciane Maria Colla

2015-01-01

Full Text Available Due to the numerous applications of lipases in industry, there is a need to study their characteristics, because lipases obtained from different sources may present different properties. The aim of this work was to accomplish the partial characterization of lipases obtained through submerged fermentation and solid-state fermentation by two species of Aspergillus. Fungal strains were isolated from a diesel-contaminated soil and selected as good lipases producers. Lipases obtained through submerged fermentation presented optimal activities at 37°C and pH 7.2 and those obtained through solid-state fermentation at 35°C and pH 6.0. The enzymes produced by submerged fermentation were more temperature-stable than those obtained by solid-state fermentation, presenting 72% of residual activity after one hour of exposition at 90°C. Lipases obtained through submerged fermentation had 80% of stability in acidic pH and those obtained through solid-state fermentation had stability greater than 60% in alkaline pH.

Composition, production rate and characterization of Greek dental solid waste.

Science.gov (United States)

Mandalidis, Alexandros; Topalidis, Antonios; Voudrias, Evangelos A; Iosifidis, Nikolaos

2018-05-01

The overall objective of this work is to determine the composition, characterization and production rate of Greek dental solid waste (DSW). This information is important to design and cost management systems for DSW, for safety and health considerations and for assessing environmental impact. A total of 141 kg of DSW produced by a total of 2542 patients in 20 dental practices from Xanthi, Greece was collected, manually separated and weighed over a period of four working weeks. The waste was separated in 19 sub fractions, which were classified in 2 major categories, according to Greek regulations: Domestic-type waste comprising 8% and hazardous waste comprising 92% by weight of total DSW. The latter was further classified in infectious waste, toxic waste and mixed type waste (infectious and toxic together), accounting for 88.5%, 3.5% and 0.03% of total DSW by weight, respectively. The overall unit production rates (mean ± standard error of the mean) were 381 ± 15 g/practice/d and 53.3 ± 1.4 g/patient/d for total DSW, 337 ± 14 g/practice/d and 46.6 ± 1.2 g/patient/d for total infectious DSW, 13.4 ± 0.7 g/practice/d and 2.1 ± 0.1 g/patient/d for total toxic DSW and 30.4 ± 2.5 g/practice/d and 4.6 ± 0.4 g/patient/d for domestic-type waste. Daily DSW production was correlated with daily number of patients and regression correlations were produced. DSW was subject to laboratory characterization in terms of bulk density, calorific value, moisture, ash and volatile solids content. Measured calorific values were compared to predictions from empirical models. Copyright © 2018 Elsevier Ltd. All rights reserved.

Synthesis, characterization and thermal expansion studies on ThO2-SmO1.5 solid solutions

International Nuclear Information System (INIS)

Panneerselvam, G.; Antony, M.P.

2008-01-01

Full text: A highly homogeneous Th 1-x Sm x O 2 ; 0 ≤ x ≤ 0.8 solid solutions were synthesized by co-precipitation technique and the co-precipitated samples were sintered at 1473 K. Compositions of the solid solutions were characterized by standard wet-chemical analysis. X-ray diffraction measurements were performed in the sintered pellets for structural analysis, lattice parameter calculation and determination of solid solubility of SmO 1.5 in ThO 2 matrix. Bulk and theoretical densities of solid solutions were also determined. A fluorite structure was observed for ThO 2 -SmO 1.5 solid solutions with 0-55.2 mol % SmO 1.5 . Their thermal expansion coefficients were measured using high temperature X-ray diffraction technique. The mean linear thermal expansivity, αm for ThO 2 -SmO 1.5 solid solutions containing 17.9, 41.7 and 52.0 mole percent of SmO 1.5 were determined in the temperature range 298 to 2000 K for the first time. The mean linear thermal expansion coefficients for ThO 2 -SmO 1.5 solid solutions are 10.47x10 -6 K -1 , 11.16x10 -6 K -1 and 11.45x10 -6 K -1 , respectively. The percentage linear thermal expansion in this temperature range, for ThO 2 -SmO 1.5 solid solutions containing 17.9, 41.7 and 52.0 mol % SmO 1.5 are 1.82,1.94 and 1.99 respectively. It is suggested that the solid solutions are stable up to 2000 K. It is also suggested that the effect and nature of the dopant are the important parameters influenced in the thermal expansion of the ThO 2

The development of safety assessment technology for the radwaste disposal

International Nuclear Information System (INIS)

Han, Kyong Won; Cho, Won Jin; Lee, Han Soo; Lee, Jai Wan; Park, Chung Kyun; Lee, Myun Joo; Cho, Young Hwan; Choi, Heui Joo; Lee, Youn Myoung; Park, Hee Sung

1989-02-01

This report is composed of three parts. In part I, an improved radwaste disposal safety assessment code named SADROCM, was developed by upgrading the existing SADROC. A numerical approach was adopted for the simulation of diffusion into rock pore and advection in the fracture. Also quantification of resaturation time in repository was obtained by introducing theoretical resaturation model and groundwater flow model. In radiation dose model the calculated dose by existing model was compared with that by LIMCAL code. Part II resulted in several findings. Regarding the leaching of radionuclide, two steps were observed. It was identified that in the initial step, radionuclide leaching occurred at the surface of solidified waste, and then leaching proceeded by dissolution and diffusion of radionuclide from inside of the solidified waste.The results of the sorption experiments on Cs, Co, Sr for the rock samples from four regions, showed that Kd value of F-site quartz-porphery was the lowest, and that of B-site Rhyolitic tuff the highest. E-site granite, M-site granite gneiss showed medium sorption capacities. The Kd values of each radionuclide were in the following order: Cs > Co > Sr . For the radionuclide migration through fractured rock, examination of hydraulic dispersion model and channeling model was carried out to simulate the dispersion phenomena through the fractured rock. In part III, optimum model was established which allows mathematical prediction of the container corrosion rate and leach rate.Based on this model, the equations were obtained to predict corrosion rate and radionuclide leach rate. A good agreement of these equations and existing experimental data was considered to be an indication that it can be used effectively for the estimation of long-term leaching. (Author)

The community's R and D programme on radioactive waste management and storage

International Nuclear Information System (INIS)

1978-01-01

The objective of the R and D actions is the demonstration of either the technical potential or, for further advanced projects, the feasibility and even the industrial availability of methods for treating and storing radwaste. The following aspects are investigated: processing of solid waste from reactors, reprocessing plants and the plutonium manufacture; intermediate and terminal storage of high activity and alpha waste; advanced waste management methods as the storage of gaseous waste. In addition to the scientific-technical R and D actions, a survey of the legal, administrative and financial problems encountered in radwaste management and storage is an essential part of the Communities' programme

Fabrication and characterization of solid PbI2 nanocrystals

International Nuclear Information System (INIS)

Kasi, Gopi K; Dollahon, Norman R; Ahmadi, Temer S

2007-01-01

Lead iodide nanoparticles are synthesized in reverse micelle solution of AOT/H 2 O/n-heptane. Optical absorption spectra and TEM analysis indicated the formation of crystalline particles with an average radius of 1.5 nm, which is less than the Bohr radius of the exciton (1.9 nm) in bulk PbI 2 . Using theoretical models and optical spectra of quantum confined PbI 2 nanoparticles, a radius of 1.5 nm and a thickness of 1.7 nm was calculated, which are in full agreement with the TEM results. Particles were isolated from the dispersed medium and were analysed by powder XRD and Raman spectroscopy, indicating the formation of a predominantly 2H-PbI 2 polytype. This work presents the first case of fully isolated, fully characterized solid nanoparticles of PbI 2 . It also presents XRD and Raman spectrum for the first time for PbI 2 nanoparticles of intermediate quantum confinement

Characterization of a Cyclic Nucleotide-Activated K+ Channel and its Lipid Environment by Using Solid-State NMR Spectroscopy

NARCIS (Netherlands)

Cukkemane, A.A.; Baldus, M.

2013-01-01

Voltage-gated ion channels are large tetrameric multidomain membrane proteins that play crucial roles in various cellular transduction pathways. Because of their large size and domain-related mobility, structural characterization has proved challenging. We analyzed high-resolution solid-state NMR

Low Temperature Solid-State Synthesis and Characterization of LaBO3

Directory of Open Access Journals (Sweden)

Azmi Seyhun KIPÇAK

2016-11-01

Full Text Available Rare earth (lanthanide series borates, possess high vacuum ultraviolet (VUV transparency, large electronic band gaps, chemical and environmental stability and exceptionally large optical damage thresholds and used in the development of plasma display panels (PDPs. In this study the synthesis of lanthanum borates via solid-state method is studied. For this purpose, lanthanum oxide (La2O3 and boric acid (H3BO3 are used for as lanthanum and boron sources, respectively. Different elemental molar ratios of La to B (between 3:1 to 1:6 as La2O3:H3BO3 were reacted by solid-state method at the reaction temperatures between 500°C - 700°C with the constant reaction time of 4 h. Following the synthesis, characterizations of the synthesized products are conducted by X-ray diffraction (XRD, Fourier transform infrared spectroscopy (FT-IR, Raman spectroscopy and scanning electron microscope (SEM. From the results of the experiments, three types of lanthanum borates of; La3BO6, LaBO3 and La(BO23 were observed at different reaction parameters. Among these three types of lanthanum borates LaBO3 phase were obtained as a major phase.

Thermal and Ash Characterization of Indonesian Bamboo and Its Potential for Solid Fuel and Waste Valorization

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Aprilina Purbasari

2016-08-01

Full Text Available Bamboo has been widely used in Indonesia for construction, handicrafts, furniture and other uses. However, the use of bamboo as a biomass for renewable energy source has not been extensively explored. This paper describes the thermal and ash characterization of three bamboo species found in Indonesia, i.e. Gigantochloa apus, Gigantochloa levis and Gigantochloa atroviolacea. Characterization of bamboo properties as a solid fuel includes proximate and ultimate analyses, calorific value measurement and thermogravimetric analysis. Ash characterization includes oxide composition analysis and phase analysis by X-Ray diffraction. The selected bamboo species have calorific value comparable with wood with low nitrogen and sulphur contents, indicating that they can be used as renewable energy sources. Bamboo ash contains high silicon so that bamboo ash has potential to be used further as building materials or engineering purposes. Ash composition analysis also indicates high alkali that can cause ash sintering and slag formation in combustion process. This implies that the combustion of bamboo requires the use of additives to reduce the risk of ash sintering and slag formation. Article History: Received May 15, 2016; Received in revised form July 2nd, 2016; Accepted July 14th, 2016; Available online How to Cite This Article: Purbasari, A., Samadhi, T.W. & Bindar, Y. (2016 Thermal and Ash Characterization of Indonesian Bamboo and its Potential for Solid Fuel and Waste Valorization. Int. Journal of Renewable Energy Development, 5(2, 95-100. http://dx.doi.org/10.14710/ijred.5.2.96-100 

Preliminary Electrochemical Characterization of Anode Supported Solid Oxide Cell (AS-SOC) Produced in the Institute of Power Engineering Operated in Electrolysis Mode (SOEC)

Science.gov (United States)

Kupecki, Jakub; Motyliński, Konrad; Skrzypkiewicz, Marek; Wierzbicki, Michał; Naumovich, Yevgeniy

2017-12-01

The article discusses the operation of solid oxide electrochemical cells (SOC) developed in the Institute of Power Engineering as prospective key components of power-to-gas systems. The fundamentals of the solid oxide cells operated as fuel cells (SOFC - solid oxide fuel cells) and electrolysers (SOEC - solid oxide fuel cells) are given. The experimental technique used for electrochemical characterization of cells is presented. The results obtained for planar cell with anodic support are given and discussed. Based on the results, the applicability of the cells in power-to-gas systems (P2G) is evaluated.

Preparation and Characterization of Solid Dispersions of Artemether by Freeze-Dried Method

Directory of Open Access Journals (Sweden)

Muhammad Tayyab Ansari

2015-01-01

Full Text Available Solid dispersions of artemether and polyethylene glycol 6000 (PEG6000 were prepared in ratio 12 : 88 (group-1. Self-emulsified solid dispersions of artemether were prepared by using polyethylene glycol 6000, Cremophor-A25, olive oil, Transcutol, and hydroxypropyl methylcellulose (HPMC in ratio 12 : 75 : 5 : 4 : 2 : 2, respectively (group-2. In third group, only Cremophor-A25 was replaced with Poloxamer 188 compared to group-2. The solid dispersions and self-emulsified solid dispersions were prepared by physical and freeze dried methods, respectively. All samples were characterized by X-ray diffraction, attenuated total reflectance Fourier transform infrared spectroscopy, differential scanning calorimeter, scanning electron microscopy, and solubility, dissolution, and stability studies. X-ray diffraction pattern revealed artemether complete crystalline, whereas physical mixture and freeze-dried mixture of all three groups showed reduced peak intensities. In attenuated total reflectance Fourier transform infrared spectroscopy spectra, C–H stretching vibrations of artemether were masked in all prepared samples, while C–H stretching vibrations were representative of polyethylene glycol 6000, Cremophor-A25, and Poloxamer 188. Differential scanning calorimetry showed decreased melting endotherm and increased enthalpy change (ΔH in both physical mixture and freeze-dried mixtures of all groups. Scanning electron microscopy of freeze-dried mixtures of all samples showed glassy appearance, size reduction, and embedment, while their physical mixture showed size reduction and embedment of artemether by excipients. In group-1, solubility was improved up to 15 times, whereas group-2 showed up to 121 times increase but, in group-3, when Poloxamer 188 was used instead of Cremophor-A25, solubility of freeze-dried mixtures was increased up to 135 times. In fasted state simulated gastric fluid at pH 1.6, the dissolution of physical

Preparation and characterization of celecoxib solid dispersions; comparison of poloxamer-188 and PVP-K30 as carriers

Directory of Open Access Journals (Sweden)

Alireza Homayouni

2014-05-01

Full Text Available Objective(s:Solid dispersion formulation is the most promising strategy to improve oral bioavailability of poorly water soluble drugs. The aim of this study was to compare the effect of polyvinylpyrrolidone K30 (PVP and poloxamer-188 (PLX as carrier in solid dispersion formulations of celecoxib (CLX. Materials and Methods: Solid dispersions of CLX:PVP or CLX:PLX were prepared at different ratios (2:1, 1:1, 1:2, 1:4, 1:6 by solvent evaporation and melting methods, respectively. The characterization of samples was performed using differential scanning calorimetery (DSC, X-Ray powder diffraction (XRPD and Fourier transform infrared spectroscopy (FT-IR. The Gordon-Taylor equation was used to estimate the Tg of solid dispersion systems and the possibility of the interaction between CLX and PVP. Also, the dissolution rate of all samples was determined. Results: DSC and XRPD analyses confirmed the presence of amorphous state of drug in solid dispersion systems. FT-IR studies showed CLX could participate in hydrogen bonding with PVP whilst no specific interaction between CLX and PLX was observed. Both PVP and PLX enhanced the dissolution rate of drug in solid dispersion samples. The dissolution rate was dependent on the ratio of drug: carrier. Interestingly, the solid dispersion samples of PLX at 2:1 and 1:1 drug: carrier showed slower dissolution rate than pure CLX, whilst these results were not observed for PVP. Conclusion: The effect of PVP on dissolution rate enhancement was more pronounced compared to the other carrier. Having a higher Tg and more effect on dissolution rate, PVP could be considered as a more suitable carrier compared to PLX in solid dispersion formulation of CLX.

Solid Phase Characterization Of Heel Samples From Tank 241-C-110

International Nuclear Information System (INIS)

Page, J.S.; Cooke, G.A.; Pestovich, J.A.; Huber, H.J.

2011-01-01

During sluicing operations of tank 241-C-110, a significant amount of solids were unable to be retrieved. These solids (often referred to as the tank 'heel') were sampled in 2010 and chemically and mineralogically analyzed in the 222-S Laboratory. Additionally, dissolution tests were performed to identify the amount of undissolvable material after using multiple water contacts. This report covers the solid phase characterization of six samples from these tests using scanning electron microscopy, polarized light microscopy, and X-ray diffraction. The chemical analyses, particle size distribution analysis, and dissolution test results are reported separately. Two of the samples were from composites created from as-received material - Composite A and Composite B. The main phase in these samples was sodium-fluoride-phosphate hydrate (natrophosphate) - in the X-ray diffraction spectra, this phase was the only phase identifiable. Polarized light microscopy showed the presence of minor amounts of gibbsite and other phases. These phases were identified by scanning electron microscopy - energy dispersive X-ray spectroscopy as sodium aluminosilicates, sodium diuranate, and sodium strontium phosphate hydrate (nastrophite) crystals. The natrophosphate crystals in the scanning electron microscopy analysis showed a variety of erosive and dissolution features from perfectly shaped octahedral to well-rounded appearance. Two samples were from water-washed Composites A and B, with no change in mineralogy compared to the as-received samples. This is not surprising, since the water wash had only a short period of water contact with the material as opposed to the water dissolution tests. The last two samples were residual solids from the water dissolution tests. These tests included multiple additions of water at 15 C and 45 C. The samples were sieved to separate a coarser fraction of > 710 μm and a finer fraction of < 710 μm. These two fractions were analyzed separately. The coarser

Cultivation and Characterization of Cynara Cardunculus for Solid Biofuels Production in the Mediterranean Region

Directory of Open Access Journals (Sweden)

Nicholas G. Danalatos

2008-07-01

Full Text Available Technical specifications of solid biofuels are continuously improved towards the development and promotion of their market. Efforts in the Greek market are limited, mainly due to the climate particularity of the region, which hinders the growth of suitable biofuels. Taking also into account the increased oil prices and the high inputs required to grow most annual crops in Greece, cardoon (Cynara cardunculus L. is now considered the most important and promising sources for solid biofuel production in Greece in the immediate future. The reason is that cardoon is a perennial crop of Mediterranean origin, well adapted to the xerothermic conditions of southern Europe, which can be utilized particularly for solid biofuel production. This is due to its minimum production cost, as this perennial weed may perform high biomass productivity on most soils with modest or without any inputs of irrigation and agrochemicals. Within this framework, the present research work is focused on the planning and analysis of different land use scenarios involving this specific energy crop and the combustion behaviour characterization for the solid products. Such land use scenarios are based on quantitative estimates of the crop’s production potential under specific soil-climatic conditions as well as the inputs required for its realization in comparison to existing conventional crops. Concerning its decomposition behaviour, devolatilisation and char combustion tests were performed in a non-isothermal thermogravimetric analyser (TA Q600. A kinetic analysis was applied and accrued results were compared with data already available for other lignocellulosic materials. The thermogravimetric analysis showed that the decomposition process of cardoon follows the degradation of other lignocellulosic fuels, meeting high burnout rates. This research work concludes that Cynara cardunculus, under certain circumstances, can be used as a solid biofuel of acceptable quality.

Characterization of solids in the Three Mile Island Unit 2 reactor defueling water

International Nuclear Information System (INIS)

Campbell, D.O.

1987-12-01

Because of the impact of poor water clarity on defueling operations at the Three Mile Island Unit 2 Nuclear Power Station, a study was undertaken to characterize suspended particulates in the reactor defueling water. The examination included cascade filtration through Nuclepore filters of progressively smaller pore sizes, using three water samples obtained at different times and after varying degrees of clarification. The solids collected on the filters were examined with a scanning electron microscope and analyzed with energy-dispersive x-ray fluorescence. A wide variety of solids was observed, and 26 elements were detected. These included all the materials expected from the reactor system (uranium, zirconium, silver, cadmium, indium, iron, chromium, and nickel), chemicals and zeolites used to decontaminate the water (aluminum, silicon, sodium), common impurities (potassium, chlorine, sulfur, magnesium, calcium, and others), as well as some unexpected metals (molybdenum, manganese, bromine, and lead). There was also evidence for the presence of organic material. A diverse assortment of particles with widely varying surface properties was found to be present

Characterization of van der Waals type bimodal,- lambda,- meta- and spinodal phase transitions in liquid mixtures, solid suspensions and thin films.

Science.gov (United States)

Rosenholm, Jarl B

2018-03-01

The perfect gas law is used as a reference when selecting state variables (P, V, T, n) needed to characterize ideal gases (vapors), liquids and solids. Van der Waals equation of state is used as a reference for models characterizing interactions in liquids, solids and their mixtures. Van der Waals loop introduces meta- and unstable states between the observed gas (vapor)-liquid P-V transitions at low T. These intermediate states are shown to appear also between liquid-liquid, liquid-solid and solid-solid phase transitions. First-order phase transitions are characterized by a sharp discontinuity of first-order partial derivatives (P, S, V) of Helmholtz and Gibbs free energies. Second-order partial derivatives (K T , B, C V , C P , E) consist of a static contribution relating to second-order phase transitions and a relaxation contribution representing the degree of first-order phase transitions. Bimodal (first-order) and spinodal (second-order) phase boundaries are used to separate stable phases from metastable and unstable phases. The boundaries are identified and quantified by partial derivatives of molar Gibbs free energy or chemical potentials with respect to P, S, V and composition (mole fractions). Molecules confined to spread Langmuir monolayers or adsorbed Gibbs monolayers are characterized by equation of state and adsorption isotherms relating to a two-dimensional van der Waals equation of state. The basic work of two-dimensional wetting (cohesion, adsorption, spreading, immersion), have to be adjusted by a horizontal surface pressure in the presence of adsorbed vapor layers. If the adsorption is extended to liquid films a vertical surface pressure (Π) may be added to account for the lateral interaction, thus restoring PV = ΠAh dependence of thin films. Van der Waals attraction, Coulomb repulsion and structural hydration forces contribute to the vertical surface pressure. A van der Waals type coexistence of ordered (dispersed) and disordered

Physical-Chemical Characterization and Formulation Considerations for Solid Lipid Nanoparticles.

Science.gov (United States)

Chauhan, Harsh; Mohapatra, Sarat; Munt, Daniel J; Chandratre, Shantanu; Dash, Alekha

2016-06-01

Pure glyceryl mono-oleate (GMO) (lipid) and different batches of GMO commonly used for the preparation of GMO-chitosan nanoparticles were characterized by modulated differential scanning calorimetry (MDSC), cryo-microscopy, and cryo-X-ray powder diffraction techniques. GMO-chitosan nanoparticles containing poloxamer 407 as a stabilizer in the absence and presence of polymers as crystallization inhibitors were prepared by ultrasonication. The effect of polymers (polyvinyl pyrrolidone (PVP), Eudragits, hydroxyl propyl methyl cellulose (HPMC), polyethylene glycol (PEG)), surfactants (poloxamer), and oils (mineral oil and olive oil) on the crystallization of GMO was investigated. GMO showed an exothermic peak at around -10°C while cooling and another exothermic peak at around -12°C while heating. It was followed by two endothermic peaks between 15 and 30 C, indicative of GMO melting. The results are corroborated by cryo-microscopy and cryo-X-ray. Significant differences in exothermic and endothermic transition were observed between different grades of GMO and pure GMO. GMO-chitosan nanoparticles resulted in a significant increase in particle size after lyophilization. MDSC confirmed that nanoparticles showed similar exothermic crystallization behavior of lipid GMO. MDSC experiments showed that PVP inhibits GMO crystallization and addition of PVP showed no significant increase in particle size of solid lipid nanoparticle (SLN) during lyophilization. The research highlights the importance of extensive physical-chemical characterization for successful formulation of SLN.

Preparation and Characterization of a Solid Acid Catalyst from Macro Fungi Residue for Methyl Palmitate Production

Directory of Open Access Journals (Sweden)

Min Wang

2015-07-01

Full Text Available During the process of fungal polysaccharide extraction for health care products and food factories, a large quantity of macro-fungi residues are produced, but most of the residues are abandoned and become environmental pollutants. A solid acid catalyst, prepared by sulfonating carbonized Phellinus igniarius residue, was shown to be an efficient and environmentally benign catalyst for the esterification of palmitate acid (PA and methanol. As a comparison, two types of common biomass catalysts, wheat straws and wood chips, were prepared. In this study, characterizations, including scanning electron microscopy, thermo-gravimetric analysis, Fourier transform infrared spectrometry, Brunauer-Emmett-Teller assays and elemental analysis, and reaction conditions for the synthesis of methyl palmitate (MP using solid acid catalysts were investigated. Experiments showed that the solid acid catalyst prepared from P. igniarius residue had a higher catalytic activity than the other two catalysts, and the highest yield of MP catalyzed by P. igniarius residue solid acid catalyst was 91.5% under the following optimum conditions: molar ratio of methanol/PA of 10:1, reaction temperature of 60 °C, mass ratio of catalyst/substrate of 2%, and a reaction time of 1.5 h. Thus, the use of this catalyst offers a method for producing MP.

Lab-scale pyrolysis of the Automotive Shredder Residue light fraction and characterization of tar and solid products.

Science.gov (United States)

Anzano, Manuela; Collina, Elena; Piccinelli, Elsa; Lasagni, Marina

2017-06-01

The general aim of this study is the recovery of Automotive Shredder Residue (ASR). The ASR light fraction, or car fluff, that was collected at an Italian shredding plant was pyrolysed at various temperatures (500-800°C) in a lab-scale reactor. The condensable gases (tar) and solid residue yields increased with decreasing temperature, and these products were characterized to suggest a potential use to reclaim them. The higher heating value (HHV) of tar was 34-37MJ/kg, which is comparable with those of fossil fuels. Furthermore, the ash content was low (0.06-4.98%). Thus, tar can be used as an alternative fuel. With this prospect, the concentrations of polychlorinated dibenzodioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs) in tar were determined. The toxicity of tar changes with temperature (1-5ng I-TEQ/g), and the PCDFs significantly contribute to tar toxicity, which was 75-100% with a maximum of 99.6% at 700°C. Regarding the characterization of the solid residue, the low HHV (2.4-3.3MJ/kg) does not make it suitable for energy recovery. Regarding material recovery, we considered its use as a filler in construction materials or a secondary source for metals. It shows a high metal concentration (280,000-395,000mg/kg), which is similar at different pyrolysis temperatures. At 500°C, polycyclic aromatic hydrocarbons (PAHs) were not detected in the solid residue, whereas the maximum total PAH concentration (19.41ng/g, 700°C) was lower than that in fly ash from MSWI. In conclusion, 500°C is a suitable pyrolysis temperature to obtain valuable tar and solid residue. Copyright © 2017 Elsevier Ltd. All rights reserved.

Solid-state 13C NMR characterization of polyanilines

International Nuclear Information System (INIS)

Kaplan, S.

1988-01-01

13 C solid-state nuclear magnetic resonance measurements are reported for the leucoemeraldine base, emeraldine base, and emeraldine hydrochloride forms of polyaniline in order to characterize the structures of these three distinct polymers. Chemical shift assignments are facilitated by use of the cross-depolarization technique to distinguish carbons with and without directly bonded hydrogens. Comparison of the spectra of emeraldine base with those of leucoemeraldine base and air-oxidized leucoemeraldine (which partially converts to emeraldine base) establishes that emeraldine base is essentially an alternating copolymer of reduced 1A (-(C 6 H 4 )N(H)(C 6 H 4 )N(H)-) and oxidized 2A (-(C 6 H 4 )N double-bond(C 6 H 4 )double-bond N-) repeat units. The 8-12 ppm spectral line widths measured for both emeraldine base and leucoemeraldine base are attributed to local fluctuations in conformational and configurational geometries, a distribution in chain packing, and compositional defects. 13 C spin-echo measurements establish that the 60 ppM wide line from the conducting emeraldine hydrochloride is inhomogeneously broadened. It is postulated that this line width is due to local variations in charge density along the polymer backbone arising from polymer structural heterogeneity. 47 refs., 5 figs., 1 tab

Solid waste management: an overview

International Nuclear Information System (INIS)

Ayoub, G.M.

1995-01-01

The source, effect and characterization of solid wastes are discussed. Constituents of municipal solid wastes and a comparative compositions of municipal solid waste with some data on Lebanon are given. Collection, transport and processing practices are next introduced. Finally treatment and disposal techniques are presented with emphasis on the solid waste as energy source and as material source. Methods of recycling are evaluated in respect with their environmental impact. 7 refs. 2 tabs

National Radwaste Repository Mochovce

International Nuclear Information System (INIS)

2000-01-01

In this leaflet the National Radioactive Waste Repository in Mochovce (Repository) is described. The Mochovce National Radioactive Waste Repository is a surface multi-barrier type storage facility for solid and treated solidified radioactive wastes generated from the Slovak Republic nuclear power plants operation and decommissioning, research institutes, laboratories and hospitals. The Repository comprises a system of single- and double-row storage boxes. The first double-row is enclosed by a steel-structure building. The 18 x 6 x 5.5 m storage boxes are made of reinforced concrete. The wall thickness is 600 mm. Two-double-rows, i.e. 80 storage boxes were built as part of Stage I (1 row = 20 storage boxes). Each storage box has a storage capacity of 90 fibre concrete containers of 3.1 m 3 volume. The total storage capacity is 7200 containers with the overall storage volume of 22320 m 3

Characterization of solid surfaces

National Research Council Canada - National Science Library

Kane, Philip F; Larrabee, Graydon B

1974-01-01

.... A comprehensive review of surface analysis, this important volume surveys both principles and techniques of surface characterization, describes instrumentation, and suggests the course of future research...

Characterization of solid residues from coal liquefaction processes. Phase I

Energy Technology Data Exchange (ETDEWEB)

Potter, J.; McDougall, W.M.; Kybett, B.D.; Neufeld, C.

1981-01-01

Various coal liquefaction and beneficiation processes are being investigated by independent research groups sponsored by the Canadian Federal Government. These processes include the co-processing of heavy oils and bitumen with coal, oxygen removal and hydrogenation of coal and supercritical gas extraction of coal. The end products, gaseous and liquid fuels and insoluble organic residues, vary with the experimental conditions. The physical properties and origin of the insoluble residue may influence such factors as degree of conversion, efficiency of the process, and ultimately, gaseous and liquid yields. One of the most suitable methods of assessing the nature of the insoluble residues is the use of petrography. This report deals with petrographic assessment of the coals and residues from various coal conversion processes; attempts were made to characterize the solid phases in the residues; to assess them in a quantitative manner and where possible; to correlate the results with experimental data; and to assess their effects on conversion. (30 refs.)

Fast characterization of solid organic waste content with near infrared spectroscopy in anaerobic digestion.

Science.gov (United States)

Charnier, Cyrille; Latrille, Eric; Jimenez, Julie; Lemoine, Margaux; Boulet, Jean-Claude; Miroux, Jérémie; Steyer, Jean-Philippe

2017-01-01

The development of anaerobic digestion involves both co-digestion of solid wastes and optimization of the feeding recipe. Within this context, substrate characterisation is an essential issue. Although it is widely used, the biochemical methane potential is not sufficient to optimize the operation of anaerobic digestion plants. Indeed the biochemical composition in carbohydrates, lipids, proteins and the chemical oxygen demand of the inputs are key parameters for the optimisation of process performances. Here we used near infrared spectroscopy as a robust and less-time consuming tool to predict the solid waste content in carbohydrates, lipids and nitrogen, and the chemical oxygen demand. We built a Partial Least Square regression model with 295 samples and validated it with an independent set of 46 samples across a wide range of solid wastes found in anaerobic digestion units. The standard errors of cross-validation were 90mgO 2 ⋅gTS -1 carbohydrates, 2.5∗10 -2 g⋅gTS -1 lipids, 7.2∗10 -3 g⋅gTS -1 nitrogen and 99mgO 2 ⋅gTS -1 chemical oxygen demand. The standard errors of prediction were 53mgO 2 ⋅gTS -1 carbohydrates, 3.2∗10 -2 g⋅gTS -1 lipids, 8.6∗10 -3 g⋅gTS -1 nitrogen and 83mgO 2 ⋅gTS -1 chemical oxygen demand. These results show that near infrared spectroscopy is a new fast and cost-efficient way to characterize solid wastes content and improve their anaerobic digestion monitoring. Copyright © 2016 Elsevier Ltd. All rights reserved.

Pressurized water reactor nuclear power plant. Environmental characterization information report

International Nuclear Information System (INIS)

1981-01-01

The typical plant chosen for characterization is a 10000-MWe nameplate rating with wet-natural-draft cooling towers and modern radwaste control and processing equipment. The process, plant operating parameters, resources needed, and the environmental residuals and products associated with the power plant are presented. Annual resource usage and pollutant discharges are shown in English and metric units, assuming an annual plant capacity factor of 70%. In addition to annual quantities, the summary table gives quantities in terms of 10 12 Btu (about 293 million kWh) of electrical energy produced for comparison among energy processes. Supporting information and calculation procedures for the data are given. Thirteen environmental points of interest are discussed individually. Cost information, typical radioactive releases, and use of cooling ponds as an alternative cooling method are discussed in appendixes. A glossary and list of acronyms and abbreviations are provided

Applicability of UV laser-induced solid-state fluorescence spectroscopy for characterization of solid dosage forms.

Science.gov (United States)

Woltmann, Eva; Meyer, Hans; Weigel, Diana; Pritzke, Heinz; Posch, Tjorben N; Kler, Pablo A; Schürmann, Klaus; Roscher, Jörg; Huhn, Carolin

2014-10-01

High production output of solid pharmaceutical formulations requires fast methods to ensure their quality. Likewise, fast analytical procedures are required in forensic sciences, for example at customs, to substantiate an initial suspicion. We here present the design and the optimization of an instrumental setup for rapid and non-invasive characterization of tablets by laser-induced fluorescence spectroscopy (with a UV-laser (λ ex = 266 nm) as excitation source) in reflection geometry. The setup was first validated with regard to repeatability, bleaching phenomena, and sensitivity. The effect on the spectra by the physical and chemical properties of the samples, e.g. their hardness, homogeneity, chemical composition, and granule grain size of the uncompressed material, using a series of tablets, manufactured in accordance with design of experiments, was investigated. Investigation of tablets with regard to homogeneity, especially, is extremely important in pharmaceutical production processes. We demonstrate that multiplicative scatter correction is an appropriate tool for data preprocessing of fluorescence spectra. Tablets with different physical and chemical characteristics can be discriminated well from their fluorescence spectra by subjecting the results to principal component analysis.

Characterization of gliclazide-polyethylene glycol solid dispersion and its effect on dissolution

Directory of Open Access Journals (Sweden)

Moreshwar Pandharinath Patil

2011-03-01

Full Text Available The present study was initiated with the objective of studying the in vitro dissolution behavior of gliclazide from its solid dispersion with polyethylene glycol 6000. In this work, a solid dispersion of gliclazide with polyethylene glycol was prepared by the fusion method. In vitro dissolution study of gliclazide, its physical mixture and solid dispersion were carried out to demonstrate the effect of PEG 6000. Analytical techniques of FT-IR spectroscopy, differential scanning calorimetry and X-ray diffractometry were used to characterize the drug in the physical mixtures and solid dispersions. The dissolution studies of solid dispersion and physical mixture showed greater improvement compared to that of the pure drug. The mechanisms for increased dissolution rate may include reduction of crystallite size, a solubilization effect of the carrier, absence of aggregation of drug crystallites, improved wettability and dispersbility of the drug from the dispersion, dissolution of the drug in the hydrophilic carrier or conversion of drug to an amorphous state. The FT-IR spectra suggested that there was no interaction between gliclazide and PEG 6000 when prepared as a solid dispersion. DSC and XRD study indicated that the drug was converted in the amorphous form.O presente trabalho foi realizado com o objetivo de estudar o comportamento in vitro da dissolução da gliclazida a partir da sua dispersão sólida com polietileno glicol 6000. Neste trabalho, as dispersões sólidas de gliclazida com polietileno glicol foram preparadas pelo método de fusão. Os estudo de dissolução in vitro da gliclazida, na mistura física e nas dispersões sólidas foram realizados para demonstrar o efeito de PEG 6000. Técnicas analíticas como espectroscopia FT-IR, calorimetria diferencial de varredura e difração de raios-X foram empregadas para caracterizar o fármaco nas misturas físicas e nas dispersoes sólidas. Os estudos de dissolução demonstraram maior

Application of the dose conversion factor for a NaI(Tl) detector to the radwaste drum assay

International Nuclear Information System (INIS)

Ji, Young-Yong; Hong, Dae-Seok; Kim, Tae-Kuk; Kwak, Kyung-Kil; Ryu, Woo-Seog

2011-01-01

The dose-to-curie (DTC) conversion method has been known that there could be extremely high uncertainty associated with establishing the radioactivity of gamma emitters in a drum. However, the DTC conversion method is still an effective assay method to calculate the radioisotope inventory because of the simple and easy procedures to be applied. In order to make the DTC conversion method practical, numerous assumptions and limitations placed on its use. These assumptions and limitations are related to the dose rate measurement and the relative abundance of gamma emitters in a drum. However, these two variables were generally obtained from the different detection mechanisms even using the different radwaste each other. Unfortunately, that expanded the limitation of using the DTC conversion method. In order to obtain two variables in a drum to be assayed at once, the dose conversion factor for a NaI(Tl) detector was first calculated from the MCNP code. The pulse height spectrum from a simulated drum inserted into a standard source was measured by a NaI(Tl) detector, and then, two variables were calculated from the dose conversion factor and the net count rate of detected gamma emitters in the pulse height spectrum.

Laser ablation/ionization characterization of solids: Second interim progress report of the strategic environmental research development program

International Nuclear Information System (INIS)

Hess, W.P.; Bushaw, B.A.; McCarthy, M.I.; Campbell, J.A.; Colson, S.D.; Dickinson, J.T.

1996-10-01

The Department of Energy is undertaking the enormous task of remediating defense wastes and environmental insults which have occurred over 50 years of nuclear weapons production. It is abundantly clear that significant technology advances are needed to characterize, process, and store highly radioactive waste and to remediate contaminated zones. In addition to the processing and waste form issues, analytical technologies needed for the characterization of solids, and for monitoring storage tanks and contaminated sites do not exist or are currently expensive labor-intensive tasks. This report describes progress in developing sensitive, rapid, and widely applicable laser-based mass spectrometry techniques for analysis of mixed chemical wastes and contaminated soils

Physicochemical characterization of some solid materials by inverse gas chromatography

International Nuclear Information System (INIS)

Hamieh, T.; Abdessater, S.

2004-01-01

Full text.New equations and models on two-dimensional state of solid surfaces were previously elaborated in many other studies. results obtained were used in this paper to the determination and the quantification of some physicochemical properties of some solid surfaces, and especially, to study the acid-base superficial characteristics of some solid substrates like oxides and/or polymer adsorbed on oxides, carbon fibers, cements, etc. The technique used was the inverse gas chromatography (CGI) at infinite dilution. The acid-base constants were calculated for many solid surfaces: Al 2 O 3 , SiO 2 , MgO, ZnO, some cements, textiles and carbon fibers

Preparation and Characterization of Emamectin Benzoate Solid Nanodispersion

OpenAIRE

Yang, Dongsheng; Cui, Bo; Wang, Chunxin; Zhao, Xiang; Zeng, Zhanghua; Wang, Yan; Sun, Changjiao; Liu, Guoqiang; Cui, Haixin

2017-01-01

The solid nanodispersion of 15% emamectin benzoate was prepared by the method of solidifying nanoemulsion. The mean particle size and polydispersity index of the solid nanodispersions were 96.6±1.7 nm and 0.352±0.041, respectively. The high zeta potential value of 31.3±0.5 mV and stable crystalline state of the nanoparticles suggested the excellent physical and chemical stabilities. The contact angle and retention compared with microemulsions and water dispersible granules on rice, cabbage, a...

Structural characterization of pure and doped calcium phosphate bioceramics prepared by simple solid state method

International Nuclear Information System (INIS)

Ahmed, S.; Kabir, H.; Nigar, F.

2011-01-01

Calcium Phosphate based bioceramic materials, in pure and doped forms have been successfully synthesized from egg shells by using solid-state method for the first time. Considering the diverse role of zinc and fluoride in biological functions, these two ions were chosen to develop the substituted bioceramic materials. Structural characterizations of these developed bioceramics were performed by using FTIR, XRD, SEM and EDS techniques. The results revealed that the fluoride doped apatite was formed in single phase containing hydroxyapatite while pure and Zinc doped apatites contained -TCP with hydroxyapatite. Experimental results and the crystallographic parameters matched well with the literature values indicating that the present experimental protocol favoured the formation of the desired bioceramics. However, to synthesize the (Ca (PO)) based bioceramic materials, such a simple solid-state approach would obviously be very helpful, not only in making the process economically feasible, but also in creating an effective material recycling technology for waste-management. (author)

Cement/slag chemistry studies

International Nuclear Information System (INIS)

Glasser, F.P.; Macphee, D.; Atkins, M.; Beckley, N.; Carson, S.O.; Wilding, C.R.; McHugh, G.

1988-01-01

The performance of cement-based matrices intended for radwaste immobilization is assessed. The long-term performance of the matrix is characterized by thermodynamic evaluation of experimental data. The results are presented in a general form, amenable to a range of specific formulations. The interaction of specific radwaste components with cements has been studied, using Iodine as an example. It occurs as both I - and IO 3 - species, but these differ sharply in sorption characteristics. The effect of ionizing radiation of the pH and E h of cement matrices is reported. (author)

The Community's R and D Programme on radioactive waste management and storage

International Nuclear Information System (INIS)

1980-01-01

The objective of the R and D actions to be achieved by 1980 is the demonstration of either the technical potential or, for further advanced projects, the feasibility and even the industrial availability of methods for treating and storing radwaste. The following aspects are investigated: - processing of solid waste from reactors, reprocessing plants and the plutonium fuel fabrication; - intermediate and terminal storage of high activity and alpha wastes; - advanced waste management methods as the storage of gaseous wastes. This report presents the most important results achieved under the programme. In addition to the scientific-technical R and D actions, a survey of the legal, administrative and financial problems encountered in radwaste management and storage is an essential part of the Communities' programme

Mechanical characterization of municipal solid waste from two waste dumps at Delhi, India.

Science.gov (United States)

Ramaiah, B J; Ramana, G V; Datta, Manoj

2017-10-01

The article presents the physical and mechanical properties of the emplaced municipal solid waste (MSW) recovered from different locations of the Ghazipur and Okhla dumps both located at Delhi, India. Mechanical compressibility and shear strength of the collected MSW were evaluated using a 300×300mm direct shear (DS) shear box. Compression ratio (C c ') of MSW at these two dumps varied between 0.11 and 0.17 and is falling on the lower bound of the range (0.1-0.5) of the data reported in the literature for MSW. Low C c ' of MSW is attributed to the relatively low percentages of compressible elements such as textiles, plastics and paper, coupled with relatively high percentages of inert materials such as soil-like and gravel sized fractions. Shear strength of MSW tested is observed to be displacement dependent. The mobilized shear strength parameters i.e., the apparent cohesion intercept (c') and friction angle (ϕ') of MSW at these two dumps are best characterized by c'=13kPa and ϕ'=23° at 25mm displacement and c'=17kPa and ϕ'=34° at 55mm displacement and are in the range reported for MSW in the literature. A large database on the shear strength of MSW from 18 countries that includes: the experimental data from 277 large-scale DS tests (in-situ and laboratory) and the data from back analysis of 11 failed landfill slopes is statistically analyzed. Based on the analysis, a simple linear shear strength envelope, characterized by c'=17kPa and ϕ'=32°, is proposed for MSW for preliminary use in the absence of site-specific data for stability evaluation of the solid waste landfill under drained conditions. Copyright © 2017 Elsevier Ltd. All rights reserved.

Petrographic characterization of the solid products of coal- pitch coprocessing

Energy Technology Data Exchange (ETDEWEB)

Potter, J.; Kybett, B.D.; McDougall, W.J.; Nambudiri, E.M.V.; Rahimi, P.; Price, J.T.

1986-06-01

Petrographic studies were conducted on four solid residues resulting from the hydrogenation process of 1) Forestburg sub- bituminous coal alone, 2) the coal with a non-coking solvent (anthracene oil), 3) pitch (Cold Lake vacuum-bottom deposits), and 4) a mixture of coal and pitch. The purpose was to determine the amounts of coal and pitch-derived solids in the residues. All the residues were produced under identical severe conditions of liquefaction to promote the formation of solids. The coal processed with anthracene oil gives a residue consisting mainly of isotropic huminitic solids. If the coal is hydrogenated under similar conditions but without a solvent, the predominant residual solids are anisotropic semicokes displaying coarse mosaic textures, which form from vitroplast. The residual products from the hydrogenated Cold Lake vacuum- bottom deposits are also dominantly anisotropic semicokes; these display coarse mosaics and flow textures, and form by the growth and coalescence of mesophase spherules. Both coal- and pitch-derived solids are identified in a residue produced by coprocessing the Forestburg coal with the pitch from the Cold Lake vacuum-bottom deposits. It is concluded that the huminite macerals in the coal generate the fine-grained, mosaic-textured semicokes, whereas the pitch produces the coarse mosaics and flow-textured semicokes.

Organic Molecular Solids

CERN Document Server

Schwoerer, Marcus

2007-01-01

This is the first comprehensive textbook on the physical aspects of organic solids. All phenomena which are necessary in order to understand modern technical applications are being dealt with in a way which makes the concepts of the topics accessible for students. The chapters - from the basics, production and characterization of organic solids and layers to organic semiconductors, superconductors and opto-electronical applications - have been arranged in a logical and well thought-out order.

Characterization of Solids in Residual Wastes from Single-Shell Tanks at the Hanford Site, Washington, USA - 9277

International Nuclear Information System (INIS)

Krupka, Kenneth M.; Cantrell, Kirk J.; Schaef, Herbert T.; Arey, Bruce W.; Heald, Steve M.; Deutsch, William J.; Lindberg, Michael J.

2009-01-01

Solid-phase characterization methods have been used in an ongoing study of residual wastes (i.e., waste remaining after final retrieval operations) from the underground single-shell storage tanks 241-C-103, 241-C-106, 241-C-202, 241-C-203, and 241-S-112 at the U.S. Department of Energy's Hanford Site in Washington State. The results of studies completed to date show significant variability in the compositions of those residual wastes and the compositions, morphologies, and crystallinities of the individual phases that make up these wastes. These differences undoubtedly result from the various waste types stored and transferred in and out each tank and the sluicing and retrieval operations used for waste retrieval. Our studies indicate that these residual wastes are chemically-complex assemblages of crystalline and amorphous solids that contain contaminants as discrete phases and/or co-precipitated within oxide phases. Depending on the specific tank, various solids (e.g., gibbsite; boehmite; dawsonite; cancrinite; Fe oxides such as hematite, goethite, and maghemite; rhodochrosite; lindbergite; whewellite; nitratine; and numerous amorphous or poorly crystalline phases) have been identified by X-ray diffraction and scanning electron microscopy/energy dispersive X-ray spectroscopy in residual wastes studied to date. Our studies also show that contact of residual wastes with Ca(OH)2- and CaCO3-saturated aqueous solutions, which were used as surrogates for the compositions of pore-fluid leachants derived from young and aged cements respectively, may alter the compositions of solid phases present in the contacted wastes. Fe oxides/hydroxides have been identified in all residual wastes studied to date. They occur in these wastes as discrete particles, particles intergrown within a matrix of other phases, and surface coatings on other particles or particle aggregates. These Fe oxides/hydroxides typically contain trace concentrations of other transition metals, such Cr, Mn

Solid acid catalysis from fundamentals to applications

CERN Document Server

Hattori, Hideshi

2014-01-01

IntroductionTypes of solid acid catalystsAdvantages of solid acid catalysts Historical overviews of solid acid catalystsFuture outlookSolid Acids CatalysisDefinition of acid and base -Brnsted acid and Lewis acid-Acid sites on surfacesAcid strengthRole of acid sites in catalysisBifunctional catalysisPore size effect on catalysis -shape selectivity-Characterization of Solid Acid Catalysts Indicator methodTemperature programmed desorption (TPD) of ammoniaCalorimetry of adsorption of basic moleculesInfrare

Characterization of the solid radioactive waste from Cernavoda NPP

International Nuclear Information System (INIS)

Iordache, M.; Lautaru, V.; Bujoreanu, D.

2005-01-01

During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from each other. For a CANDU type reactor, the occurrence of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

Solid state division progress report, period ending February 29, 1980

Energy Technology Data Exchange (ETDEWEB)

1980-09-01

Research is reported concerning theoretical solid state physics; surface and near-surface properties of solids; defects in solids; transport properties of solids; neutron scattering; crystal growth and characterization; and isotope research materials.

Solid state division progress report, period ending February 29, 1980

International Nuclear Information System (INIS)

1980-09-01

Research is reported concerning theoretical solid state physics; surface and near-surface properties of solids; defects in solids; transport properties of solids; neutron scattering; crystal growth and characterization; and isotope research materials

Lithium-ion transport in inorganic solid state electrolyte

International Nuclear Information System (INIS)

Gao Jian; Li Hong; Zhao Yu-Sheng; Shi Si-Qi

2016-01-01

An overview of ion transport in lithium-ion inorganic solid state electrolytes is presented, aimed at exploring and designing better electrolyte materials. Ionic conductivity is one of the most important indices of the performance of inorganic solid state electrolytes. The general definition of solid state electrolytes is presented in terms of their role in a working cell (to convey ions while isolate electrons), and the history of solid electrolyte development is briefly summarized. Ways of using the available theoretical models and experimental methods to characterize lithium-ion transport in solid state electrolytes are systematically introduced. Then the various factors that affect ionic conductivity are itemized, including mainly structural disorder, composite materials and interface effects between a solid electrolyte and an electrode. Finally, strategies for future material systems, for synthesis and characterization methods, and for theory and calculation are proposed, aiming to help accelerate the design and development of new solid electrolytes. (topical review)

Paleocorrosion studies in deep sea sediments and the geological disposal of nuclear wastes

International Nuclear Information System (INIS)

Fehrenbach, L.; Maurette, M.; Guichard, F.; Havette, A.; Monaco, A.

1984-01-01

Uncertainties still surround assessment of the safety of disposal of nuclear wastes incorporated into 'radwaste' matrices. This is mostly due to the long time required for radioactive decay of 237 Np. The present work explores the usefulness of an experimental approach in 'paleocorrosion', which should help in minimizing such uncertainties. In this approach, polished sections of sediments containing high concentrations of natural analogues of radwaste matrices are subjected to element micromapping. Thus it is possible to characterize the long-term interactions of such analogues in their geological repositories, and to identify which generate reaction aureoles and protective and/or unprotective coatings. These analogues include grains incorporated in deep sea sediments (uraninite and quartz from the Oklo uranium ore deposit; volcanic ash particles; magnetic cosmic spherules). The present results indicate that uraninite should be a much more durable radwaste matrix than any type of glass in deep sea sediments. (orig./TWO)

Characterization of the solid radioactive waste From Cernavoda NPP

International Nuclear Information System (INIS)

Iordache, M.; Laotaru, V.

2005-01-01

Full text: During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from which other. For a CANDU type reactor, the appearance of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

Characterized hydrochar of algal biomass for producing solid fuel through hydrothermal carbonization.

Science.gov (United States)

Park, Ki Young; Lee, Kwanyong; Kim, Daegi

2018-06-01

The aim of this work was to study the characterized hydrochar of algal biomass to produce solid fuel though hydrothermal carbonization. Hydrothermal carbonization conducted at temperatures ranging from 180 to 270 °C with a 60 min reaction improved the upgrading of the fuel properties and the dewatering of wet-basis biomasses such as algae. The carbon content, carbon recovery, energy recovery, and atomic C/O and C/H ratios in all the hydrochars in this study were improved. These characteristic changes in hydrochar from algal biomass are similar to the coalification reactions due to dehydration and decarboxylation with an increase in the hydrothermal reaction temperature. The results of this study indicate that hydrothermal carbonization can be used as an effective means of generating highly energy-efficient renewable fuel resources using algal biomass. Copyright © 2018 Elsevier Ltd. All rights reserved.

Atomic characterization of Au clusters in vapor-liquid-solid grown silicon nanowires

International Nuclear Information System (INIS)

Chen, Wanghua; Roca i Cabarrocas, Pere; Pareige, Philippe; Castro, Celia; Xu, Tao; Grandidier, Bruno; Stiévenard, Didier

2015-01-01

By correlating atom probe tomography with other conventional microscope techniques (scanning electron microscope, scanning transmission electron microscope, and scanning tunneling microscopy), the distribution and composition of Au clusters in individual vapor-liquid-solid grown Si nanowires is investigated. Taking advantage of the characteristics of atom probe tomography, we have developed a sample preparation method by inclining the sample at certain angle to characterize the nanowire sidewall without using focused ion beam. With three-dimensional atomic scale reconstruction, we provide direct evidence of Au clusters tending to remain on the nanowire sidewall rather than being incorporated into the Si nanowires. Based on the composition measurement of Au clusters (28% ± 1%), we have demonstrated the supersaturation of Si atoms in Au clusters, which supports the hypothesis that Au clusters are formed simultaneously during nanowire growth rather than during the cooling process

Atomic characterization of Au clusters in vapor-liquid-solid grown silicon nanowires

Energy Technology Data Exchange (ETDEWEB)

Chen, Wanghua; Roca i Cabarrocas, Pere [Laboratoire de Physique des Interfaces et Couches Minces (LPICM), UMR 7647, CNRS, Ecole Polytechnique, 91128 Palaiseau (France); Pareige, Philippe; Castro, Celia [Groupe de Physique des Matériaux (GPM), Université et INSA de Rouen, UMR 6634, CNRS, Av. de l' Université, BP 12, 76801 Saint Etienne du Rouvray (France); Xu, Tao; Grandidier, Bruno; Stiévenard, Didier [Institut d' Electronique et de Microélectronique et de Nanotechnologies (IEMN), UMR 8520, CNRS, Département ISEN, 41 bd Vauban, 59046 Lille Cedex (France)

2015-09-14

By correlating atom probe tomography with other conventional microscope techniques (scanning electron microscope, scanning transmission electron microscope, and scanning tunneling microscopy), the distribution and composition of Au clusters in individual vapor-liquid-solid grown Si nanowires is investigated. Taking advantage of the characteristics of atom probe tomography, we have developed a sample preparation method by inclining the sample at certain angle to characterize the nanowire sidewall without using focused ion beam. With three-dimensional atomic scale reconstruction, we provide direct evidence of Au clusters tending to remain on the nanowire sidewall rather than being incorporated into the Si nanowires. Based on the composition measurement of Au clusters (28% ± 1%), we have demonstrated the supersaturation of Si atoms in Au clusters, which supports the hypothesis that Au clusters are formed simultaneously during nanowire growth rather than during the cooling process.

DWPF waste glass Product Composition Control System

International Nuclear Information System (INIS)

Brown, K.G.; Postles, R.L.

1992-01-01

The Defense Waste Processing Facility (DWPF) will be used to blend aqueous radwaste (PHA) with solid radwaste (Sludge) in a waste receipt vessel (the SRAT). The resulting SRAT material is transferred to the SME an there blended with ground glass (Frit) to produce a batch of melter feed slurry. The SME material is passed to a hold tank (the MFT) which is used to continuously feed the DWPF melter. The melter. The melter produces a molten glass wasteform which is poured into stainless steel canisters for cooling and, ultimately, shipment to and storage in a geologic repository. The Product Composition Control System (PCCS) is the system intended to ensure that the melt will be processible and that the glass wasteform will be acceptable. This document provides a description of this system

Crystallized solids characterization by X-ray diffraction

International Nuclear Information System (INIS)

Broll, N.

1996-01-01

This work deals with the crystallized solids characterization by X-ray diffraction. The powders diffraction principle is described. Then are given the different powders diffraction experimental methods. An X-ray diffraction device is essentially constituted of three parts: the X-rays source, the sample and the detector. The source is usually constituted by an X-rays tube whereas the sample can be fixed on a photographic chamber or put on a goniometer. The different photographic chambers which can be used (Debye-Scherrer, Seeman-Bohlin and Guinier) are described. The powders diffractometer the most used is a Bragg-Brentano focusing diffractometer because it allows to obtain very sharp spectral lines and an important diffracted intensity. The detectors which are the mainly used are the scintillation counters. The most important use in powders diffractometry is the identification of the different phases of a sample. The phases identification consists to compare the unknown sample spectrum at those of standard materials indexed until now. Two methods exist at present. They are explained and their limits in the phases search are given. Another use of the X-ray diffraction is the quantitative analysis. It consists to determine the concentrations of each crystal phases of a sample. The principles of these quantitative methods are given. The lattice parameters of a polycrystal material can be determined from its X-ray pattern too with a very high precision. The way to index powders patterns is given. The residual stresses of materials can also be estimated. The principle of this measured method is explained. It is at last possible to study from an X-ray pattern, the material grain orientations during the different steps of preparation and working. (O.M.). 13 refs., 19 figs., 1 tab

Krsko NPP radioactive waste characteristics

International Nuclear Information System (INIS)

Skanata, D.; Kroselj, V.; Jankovic, M.

2007-01-01

In May 2005 Krsko NPP initiated the Radioactive Waste Characterization Project and commissioned its realization to the consulting company Enconet International, Zagreb. The Agency for Radwaste Management was invited to participate on the Project. The Project was successfully closed out in August 2006. The main Project goal consisted of systematization the existing and gathering the missing radiological, chemical, physical, mechanical, thermal and biological information and data on radioactive waste. In a general perspective, the Project may also be considered as a part of broader scope of activities to support state efforts to find a disposal solution for radioactive waste in Slovenia. The operational low and intermediate level radioactive waste has been structured into 6 waste streams that contain evaporator concentrates and tank sludges, spent ion resins, spent filters, compressible and non-compressible waste as well as specific waste. For each of mentioned waste streams, process schemes have been developed including raw waste, treatment and conditioning technologies, waste forms, containers and waste packages. In the paper the main results of the Characterization Project will be briefly described. The results will indicate that there are 17 different types of raw waste that have been processed by applying 9 treatment/conditioning technologies. By this way 18 different waste forms have been produced and stored into 3 types of containers. Within each type of container several combinations should be distinguished. Considering all of this, there are 34 different types of waste packages altogether that are currently stored in the Solid Radwaste Storage Facility at the Krsko NPP site. Because of these findings a new identification system has been recommended and consequently the improvement of the existing database on radioactive waste has been proposed. The potential areas of further in depth characterization are indicated. In the paper a brief description on the

Physical, mechanical and electrochemical characterization of all-perovskite intermediate temperature solid oxide fuel cells

Science.gov (United States)

Mohammadi, Alidad

Strontium- and magnesium-doped lanthanum gallate (LSGM) has been considered as a promising electrolyte for solid oxide fuel cell (SOFC) systems in recent years due to its high ionic conductivity and chemical stability over a wide range of oxygen partial pressures and temperatures. This research describes synthesis, physical and mechanical behavior, electrochemical properties, phase evolution, and microstructure of components of an all-perovskite anode-supported intermediate temperature solid oxide fuel cell (ITSOFC), based on porous La 0.75Sr0.25Cr0.5Mn0.5O3 (LSCM) anode, La0.8Sr0.2Ga0.8Mg0.2O 2.8 (LSGM) electrolyte, and porous La0.6Sr0.4Fe 0.8Co0.2O3 (LSCF) cathode. The phase evolution of synthesized LSGM and LSCM powders has been investigated, and it has been confirmed that there is no reaction between LSGM and LSCM at sintering temperature. Using different amounts of poreformers and binders as well as controlling firing temperature, porosity of the anode was optimized while still retaining good mechanical integrity. The effect of cell operation conditions under dry hydrogen fuel on the SOFC open circuit voltage (OCV) and cell performance were also investigated. Characterization study of the synthesized LSGM indicates that sintering at 1500°C obtains higher electrical conductivity compared to the currently published results, while conductivity of pellets sintered at 1400°C and 1450°C would be slightly lower. The effect of sintering temperature on bulk and grain boundary resistivities was also discussed. The mechanical properties, such as hardness, Young's modulus, fracture toughness and modulus of rupture of the electrolyte were determined and correlated with scanning electron microscopy (SEM) morphological characterization. Linear thermal expansion and thermal expansion coefficient of LSGM were also measured.

Assessment of LANL solid low-level waste management documentation

International Nuclear Information System (INIS)

Klein, R.B.; Jennrich, E.A.; Lund, D.M.; Danna, J.G.; Davis, K.D.; Rutz, A.C.

1991-04-01

DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section's capabilities regarding preparation and maintenance of appropriate criteria, plans and procedures and identify particular areas where these documents are not presently in existence or being fully implemented. DOE Order 5820.2A, Radioactive Waste Management, Chapter III sets forth the requirements and guidelines for preparation and implementation of criteria, plans and procedures to be utilized in the management of solid low-level waste. The documents being assessed in this report are: Solid Low-Level Waste Acceptance Criteria, Solid Low-Level Waste Characterization Plan, Solid Low-Level Waste Certification Plan, Solid Low-Level Waste Acceptance Procedures, Solid Low-Level Waste Characterization Procedures, Solid Low-Level Waste Certification Procedures, Solid Low-Level Waste Training Procedures, and Solid Low-Level Waste Recordkeeping Procedures. Suggested outlines for these documents are presented as Appendix A

Characterization investigations during mechanical alloying and sintering of Ni-W solid solution alloys dispersed with WC and Y2O3 particles

International Nuclear Information System (INIS)

Genc, Aziz; Luetfi Ovecoglu, M.

2010-01-01

Research highlights: → Characterization investigations on the Ni-W solid solution alloys fabricated via mechanical alloying and the evolution of the properties of the powders with increasing MA durations. → Reinforcement of the selected Ni-W powders with WC and Y 2 O 3 particles and further MA together for 12 h. → There is no reported literature on the development and characterization of Ni-W solid solution alloys matrix composites fabricated via MA. → Sintering of the developed composites and the characterization investigations of the sintered samples. → Identification of new 'pomegranate-like' structures in the bulk of the samples. - Abstract: Blended elemental Ni-30 wt.% W powders were mechanically alloyed (MA'd) for 1 h, 3 h, 6 h, 12 h, 24 h, 36 h and 48 h in a Spex mixer/mill at room temperature in order to investigate the effects of MA duration on the solubility of W in Ni and the grain size, hardness and particle size. Microstructural and phase characterizations of the MA'd powders were carried out using X-ray diffractometer (XRD), scanning electron microscope (SEM) and transmission electron microscope (TEM). On the basis of achieved saturation on the solid solubility, hardness and particle size, the Ni-30 wt.% W powders MA'd for 48 h were chosen as the matrix which was reinforced with different amounts of WC and/or with 1 wt.% Y 2 O 3 particles. The reinforced powders were further MA'd for 12 h. The MA'd powders were sintered at 1300 o C for 1 h under Ar and H 2 gas flowing conditions. Microstructural characterizations of the sintered samples were conducted via XRD and SEM. Sintered densities were measured by using the Archimedes' method. Vickers microhardness tests were performed on both MA'd powders and the sintered samples. Sliding wear experiments were done in order to investigate wear behaviors of the sintered samples.

Preparation, characterization and thermal properties of PMMA/n-heptadecane microcapsules as novel solid-liquid microPCM for thermal energy storage

International Nuclear Information System (INIS)

Sari, Ahmet; Alkan, Cemil; Karaipekli, Ali

2010-01-01

This study is focused on the preparation, characterization and thermal properties of microencapsulated n-heptadecane with polymethylmethacrylate shell. The PMMA/heptadecane microcapsules were synthesized as novel solid-liquid microencapsulated phase change material (microPCMs) by emulsion polymerization method. The chemical and thermal characterization of the microPCMs were investigated using scanning electron microscopy (SEM), differential scanning calorimetry (DSC) and thermogravimetry analysis (TGA). The diameters of microPCMs were found in the narrow range (0.14-0.40 μm) under the stirring speed of 2000 rpm. The spherical surfaces of microPCMs were smooth and compact. The DSC results show that microPCMs have good energy storage capacity. Thermal cycling test showed that the microPCMs have good thermal reliability with respect to the changes in their thermal properties after repeated 5000 thermal cycling. TGA analyses also indicated that the microPCMs degraded in three steps and have good thermal stability. Based on all results, it can be considered that the PMMA/heptadecane microcapsules as novel solid-liquid microPCMs have good energy storage potential.

Solid dispersion application in pharmaceutical technology: Methods of preparation and characterization

OpenAIRE

Medarević, Đorđe; Ibrić, Svetlana; Đuriš, Jelena; Đurić, Zorica

2013-01-01

A growing number of newly synthesized drugs exhibit low aqueous solubility, leading to poor bioavailability. Therefore, improving drug solubility and dissolution rate became one of the greatest challenges during formulation development. Solid dispersions formulation is one of the commonly investigated techniques for improving solubility of poorly soluble drugs. Solid dispersions are dispersions of one or more drugs in an inert carrier (matrix) in the solid state prepared by melting, solvent, ...

Fabrication and characterization of a cathode-supported tubular solid oxide fuel cell

Energy Technology Data Exchange (ETDEWEB)

Zhao, Chunhua; Liu, Renzhu; Wang, Shaorong; Wang, Zhenrong; Qian, Jiqin; Wen, Tinglian [CAS Key Laboratory of Materials for Energy Conversion, Shanghai Institute of Ceramics, Chinese Academy of Sciences (SICCAS), 1295 Dingxi Road, Shanghai 200050 (China)

2009-07-15

A cathode-supported tubular solid oxide fuel cell (CTSOFC) with the length of 6.0 cm and outside diameter of 1.0 cm has been successfully fabricated via dip-coating and co-sintering techniques. A crack-free electrolyte film with a thickness of {proportional_to}14 {mu}m was obtained by co-firing of cathode/cathode active layer/electrolyte/anode at 1250 C. The relative low densifying temperature for electrolyte was attributed to the large shrinkage of the green tubular which assisted the densification of electrolyte. The assembled cell was electrochemically characterized with humidified H{sub 2} as fuel and O{sub 2} as oxidant. The open circuit voltages (OCV) were 1.1, 1.08 and 1.06 V at 750, 800 and 850 C, respectively, with the maximum power densities of 157, 272 and 358 mW cm{sup -2} at corresponding temperatures. (author)

Synthesis and characterization of cobaltite nanotubes for solid-oxide fuel cell cathodes

Energy Technology Data Exchange (ETDEWEB)

Napolitano, F; Baque, L; Troiani, H; Granada, M; Serquis, A, E-mail: aserquis@cab.cnea.gov.a [Instituto Balseiro-Centro Atomico Bariloche and CONICET, San Carlos de Bariloche (Argentina)

2009-05-01

La{sub 1-x}Sr{sub x}Co{sub 1-y}FeyO{sub 3-d}elta oxides are good candidates for solid oxide fuel cell (SOFC) cathodes because these materials present high ionic and electronic conductivity, and compatibility with Cerium Gadolinium Oxide (CGO) electrolytes allowing a lower operation temperature. In this work, we report the synthesis of La{sub 0.4}Sr{sub 0.6}Co{sub 0.8}Fe{sub 0.2}O{sub 3-d}elta (LSCF) nanotubes prepared by a porous polycarbonate membrane approach, obtaining different microstructures depending on sintering conditions. The structure and morphology of the nanotubes and deposited films were characterized by X-ray diffraction, transmission and scanning microscopy. Finally, we obtained nanostructured films of vertically aligned LSCF tubes deposited over the whole surface of CGO pellets with diameter up to 2.5cm in a direct and single step process.

Characterization of past and present solid waste streams from the plutonium finishing plant

Energy Technology Data Exchange (ETDEWEB)

Duncan, D.R.; Mayancsik, B.A. [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J.A.; Vejvoda, E.J.; Reddick, J.A.; Sheldon, K.M.; Weyns, M.I. [Los Alamos Technical Associates, Kennewick, WA (United States)

1993-02-01

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing (WRAP) Facility, and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico for final disposal. Over 50% of the TRU waste to be retrieved for shipment to the WIPP has been generated at the Plutonium Finishing Plant (PFP), also known as the Plutonium Processing and Storage Facility and Z Plant. The purpose of this report is to characterize the radioactive solid wastes generated by the PFP since its construction in 1947 using process knowledge, existing records, and history-obtained from interviews. The PFP is currently operated by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE).

Characterization of past and present solid waste streams from the plutonium finishing plant

International Nuclear Information System (INIS)

Duncan, D.R.; Mayancsik, B.A.; Pottmeyer, J.A.; Vejvoda, E.J.; Reddick, J.A.; Sheldon, K.M.; Weyns, M.I.

1993-02-01

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing (WRAP) Facility, and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico for final disposal. Over 50% of the TRU waste to be retrieved for shipment to the WIPP has been generated at the Plutonium Finishing Plant (PFP), also known as the Plutonium Processing and Storage Facility and Z Plant. The purpose of this report is to characterize the radioactive solid wastes generated by the PFP since its construction in 1947 using process knowledge, existing records, and history-obtained from interviews. The PFP is currently operated by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE)

Solid dispersions of Myricetin with enhanced solubility: Formulation, characterization and crystal structure of stability-impeding Myricetin monohydrate crystals

Science.gov (United States)

Mureşan-Pop, M.; Pop, M. M.; Borodi, G.; Todea, M.; Nagy-Simon, T.; Simon, S.

2017-08-01

Three solid dispersion forms of Myricetin combined with the Polyvinylpyrrolidone were successfully prepared by spray drying method, and characterized by X-ray powder diffraction, thermal analysis, infrared spectroscopy and optical microscopy. Zeta potential measurements provided indications on solid dispersions stability in aqueous suspension related to their storage at elevated temperature and relative humidity, which depends on the Myricetin load. By increase of Myricetin load, the stability of the solid dispersion is impeded due to growth of Myricetin monohydrate crystals. The amorphous dispersions with 10% and 50% Myricetin load are stable and, compared to pure Myricetin, their aqueous solubility is enhanced by a factor of 47 and 13, respectively. The dispersion with 80% Myricetin load is unstable on storage, and this behavior acts in conjunction with the development of Myricetin monohydrate crystals. Single-crystal X-ray diffraction results obtained for Myricetin monohydrate reveal a structure of an infinite 2D network of hydrogen-bonded molecules involving all six hydroxyl groups of Myricetin. The water molecules are positioned in between the infinite chains, and contribute via H-bonds to robust crystal packing. The calculated needle-like morphology of monohydrate form is in agreement with the optical microscopy results. The study shows that the solid amorphous dispersions with up to 50% Myricetin load are a viable option for achieving substantial solubility improvement of Myricetin, and supports their potential use in pharmaceutical applications.

Getter Incorporation into Cast Stone and Solid State Characterizations

Energy Technology Data Exchange (ETDEWEB)

Asmussen, Robert M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lawter, Amanda R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Stephenson, John R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bowden, Mark E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Washton, Nancy M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Neeway, James J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Du, Yingge [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Pearce, Carolyn I. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Clayton, Ray E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Saslow, Sarah A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buck, Edgar C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Cordova, Elsa [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Qafoku, Nikolla [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-09-28

Washington River Protection Solutions (WRPS) is collecting relevant available data on waste forms for use as a supplemental immobilization technology, to provide the additional capacity needed to treat low-activity waste (LAW) in Hanford Site tanks and complete the tank waste cleanup mission in a timely and cost-effective manner. One candidate supplemental waste form, fabricated using a low-temperature process, is a cementitious grout called Cast Stone. Cast Stone has been under investigation for this application at Pacific Northwest National Laboratory (PNNL) since initial screening tests in FY13. This report is the culmination of work to lower the diffusivities of Tc and I from Cast Stone using getters. Getters are compounds added to a system designed to selectively sequester a species of interest to provide increased stability to the species. The work contained within this report is related to waste form development and testing, and does not directly support the 2017 integrated disposal facility (IDF) performance assessment. However, this work contains valuable information which may be used in performance assessment maintenance past FY17, and in future waste form development. This report on performance characterization of Tc and I getters in Cast Stone fabricated with simulated LAW covers several areas of interest and major findings to WRPS: investigating performance of potassium metal sulfide (KMS-2-SS) and tin (II) apatite (Sn-A) as Tc getters when incorporated into Cast Stone; investigating performance of silver exchanged zeolite (Ag-Z) and argentite (Arg) as I getters when incorporated into Cast Stone; utilizing sequential addition of Tc and I getters to overcome any deleterious interactions between the getters in solution; determining, for the first time, Tc distribution within the cured Cast Stone and its evolution during leaching; and performing solid state characterization of getters and Cast Stone samples to support leach test findings and develop a

Radioactive waste management in Romania

International Nuclear Information System (INIS)

Barariu, Gheorghe; Radu, Maria; Dobos, Ion; Glodeanu, Florin; Popescu, V. Ion; Rotarescu, Gheorghe; Turcanu, Cornel

1998-01-01

The paper presents the main aspects of management of radwastes generated within the frame of Nuclear Fuel Cycle (NFC) and out of Nuclear Fuel Cycle in Romania. There are mentioned the Romanian legislative and regulatory framework concerning nuclear activities which include provisions for radwaste management generated in Romania. The paper lists the radwaste producers, mentions waste inventory and gives future estimates for radwaste generation, all determining development of the radwaste management strategy. Choosing selected strategy for radwaste management, the main responsible organizations have been established as well as the planned facilities for treatment conditioning, storage and disposal of radwastes generated within the frame of both NFC and out of NFC fields of peaceful nuclear activity. (authors)

A Study on Improvement of Algorithm for Source Term Evaluation

International Nuclear Information System (INIS)

Park, Jeong Ho; Park, Do Hyung; Lee, Jae Hee

2010-03-01

The program developed by KAERI for source term assessment of radwastes from the advanced nuclear fuel cycle consists of spent fuel database analysis module, spent fuel arising projection module, and automatic characterization module for radwastes from pyroprocess. To improve the algorithm adopted the developed program, following items were carried out: - development of an algorithm to decrease analysis time for spent fuel database - development of setup routine for a analysis procedure - improvement of interface for spent fuel arising projection module - optimization of data management algorithm needed for massive calculation to estimate source terms of radwastes from advanced fuel cycle The program developed through this study has a capability to perform source term estimation although several spent fuel assemblies with different fuel design, initial enrichment, irradiation history, discharge burnup, and cooling time are processed at the same time in the pyroprocess. It is expected that this program will be very useful for the design of unit process of pyroprocess and disposal system

Processing by both classical and mechanosynthesis routes and characterization of a new solid solution of tungsten-bronze structure ceramics

International Nuclear Information System (INIS)

Khachane, M.; Moure, A.; Elaatmani, M.; Zegzouti, A.; Daoud, M.; Castro, A.

2006-01-01

A new family of ferroelectric compounds with Ba 2-x Na 1+x Li x Nb 5 O 15 composition (0 ≤ x ≤ 1) and tetragonal tungsten-bronze structure is processed for the first time. This new family of materials derived from Ba 2 NaNb 5 O 15 compound was processed by classical solid-state reaction and by mechanosynthesis. The powders prepared by these two routes were characterized by X-ray diffraction (at room and high temperature), differential thermal analysis, thermogravimetry and scanning electron microscopy. The results confirm the formation of the solid solution in the whole range of composition. The influence of Li addition on the dielectric permittivity and losses and on the ferro-paraelectric transition temperature is also studied

Nanoscale Chemical Characterization of Solid-State Microbattery Stacks by Means of Auger Spectroscopy and Ion-Milling Cross Section Preparation.

Science.gov (United States)

Uhart, A; Ledeuil, J B; Pecquenard, B; Le Cras, F; Proust, M; Martinez, H

2017-09-27

The current sustained demand for "smart" and connected devices has created a need for more miniaturized power sources, hence for microbatteries. Lithium-ion or "lithium-free" all-solid-state thin-film batteries are adapted solutions to this issue. The capability to carry out spatially resolved chemical analysis is fundamental for the understanding of the operation in an all-solid-state microbattery. Classically cumbersome and not straightforward techniques as TEM/STEM/EELS and FIB preparation methods could be used to address this issue. The challenge in this work is to make the characterization of Li-based material possible by coupling ion-milling cross section preparation method and AES techniques to characterize the behavior of a LiCoO 2 positive electrode in an all solid state microbattery. The surface chemistry of LiCoO 2 has been studied before and after LiPON deposition. Modifications of the chemical environments characteristic of the positive electrode have been reported at different steps of the electrochemical process. An original qualitative and a semiquantitative analysis has been used in this work with the peak deconvolution method based on real, certified reference spectra to better understand the lithiation/delithiation process. This original coupling has demonstrated that a full study of the pristine, cycled, and post mortem positive electrode in a microbattery is also possible. The ion-milling preparation method allows access to a large area, and the resolution of Auger analysis is highly resolved in energy to separate the lithium and the cobalt signals in an accurate way.

Synthesis and characterization of type solid solution in the binary ...

Indian Academy of Sciences (India)

We have investigated Bi2O3–Eu2O3 binary system by doping with Eu2O3 in the composition range from 1 to 10 mole% via solid state reactions and succeeded to stabilize -Bi2O3 ... Our experimental observations strongly suggested that oxygen deficiency type non-stoichiometry is present in doped type solid solutions.

Calculation characterization of spent fuel hazard related to partitioning and transmutation of minor actinides and fission products

International Nuclear Information System (INIS)

Gerasimov, A. S.; Bergelson, B. R.; Tikhomirov, G.V.; Volovik, A.I. . E-mail of corresponding author: geras@itep.ru; Gerasimov, A.S.)

2005-01-01

Radiotoxicity is one of important characteristics of radwaste hazard. Radiotoxicity of actinides and fission products from spent fuel of VVER-1000 reactor for processes of burnup, long-term storage, and transmutation is discussed. (author)

Solid State NMR Characterization and Adsorption Properties of ...

African Journals Online (AJOL)

NICOLAAS

of acid were removed and the AgNO3 chloride test proved nega- tive. The purified ... (VNMRS WB 500 solids) static magnetic field strength: 11.7 T ..... polyethersulfone-organophilic montmorillonite hybrid particles for the removal of bisphenol ...

Flame Characterization Using a Tunable Solid-State Laser with Direct UV Pumping

Science.gov (United States)

Kamal, Mohammed M.; Dubinskii, Mark A.; Misra, Prabhakar

1996-01-01

Tunable solid-state lasers with direct UV pumping, based on d-f transitions of rare earth ions incorporated in wide band-gap dielectric crystals, are reliable sources of laser radiation that are suitable for excitation of combustion-related free radicals. We have employed such a laser for analytical flame characterization utilizing Laser-Induced Fluorescence (LIF) techniques. LIF spectra of alkane-air flames (used for studying combustion processes under normal and microgravity conditions) excited in the region of the A-X (0,0) OH-absorption band have been recorded and found to be both temperature-sensitive and positionally-sensitive. In addition, also clearly noticeable was the sensitivity of the spectra to the specific wavelength used for data registration. The LiCAF:Ce laser shows good prospects for being able to cover the spectral region between 280 and 340 nm and therefore be used excitation of combustion-intermediates such as the hydroxyl OH, methoxy CH30 and methylthio CH3S radicals.

Synthesis, characterization and thermal stability of solid solutions Zr (Y, Fe, MoO2

Directory of Open Access Journals (Sweden)

Felipe Legorreta-García

2015-05-01

Full Text Available The synthesis of Fe3+, Mo4+ and Y3+ fully stabilized zirconia by the nitrate/urea combustion route and thermal stability in air was investigated. The solid solution obtained was characterized by X ray diffraction (XRD, scanning electron microscopy (SEM and used the BET method for determining specific surface. The ceramic powders obtained were calcined at 1473 K in air atmosphere in order to determine their thermal stability. The scanning electron microscopy (SEM results showed a homogeneous grain surface, measuring several tens of micrometers across. The crystallographic study revealed that by this method it was successfully achieved zirconia doped with Fe3+, Mo4+ and Y3+ ions in the zirconia tetragonal monophase, even after calcinations.

Synthesis and characterization of nano-crystalline Ce_1-xGd _xO_2-x/2 (x = 0-0.30) solid solutions

DEFF Research Database (Denmark)

Jadhav, L. D.; Chourashiya, M. G.; Jamale, A. P.

2010-01-01

glycine-nitrate process (GNP) has been presented. Evolution of structural and morphological properties of nano-powders as a function of heat treatment has also been studied. The prepared samples were characterized using TG-DTA, FT-IR, Raman spectroscopy, XRD, SEM, etc. In addition, the effect of Gd......In recent years, doped ceria is an established and promising candidate as solid electrolyte for intermediate temperature solid oxide fuel cell (IT-SOFC). In this investigation, synthesis and characterizations of nano-crystalline Gd doped ceria, (Ce1-xGdxO2-x/2, where x = 0-0.3), prepared using...... of sintered samples was observed to hinder with an increase in Gd content....

Fabrication and characterization of a solid-state nanopore with self-aligned carbon nanoelectrodes for molecular detection

International Nuclear Information System (INIS)

Spinney, Patrick S; Collins, Scott D; Smith, Rosemary L; Howitt, David G

2012-01-01

Stochastic molecular sensors based on resistive pulse nanopore modalities are envisioned as facile DNA sequencers. However, recent advances in nanotechnology fabrication have highlighted promising alternative detection mechanisms with higher sensitivity and potential single-base resolution. In this paper we present the novel self-aligned fabrication of a solid-state nanopore device with integrated transverse graphene-like carbon nanoelectrodes for polyelectrolyte molecular detection. The electrochemical transduction mechanism is characterized and found to result primarily from thermionic emission between the two transverse electrodes. Response of the nanopore to Lambda dsDNA and short (16-mer) ssDNA is demonstrated and distinguished. (paper)

Seasonal characterization of municipal solid waste (MSW) in the city of Chihuahua, Mexico

International Nuclear Information System (INIS)

Gomez, Guadalupe; Meneses, Montserrat; Ballinas, Lourdes; Castells, Francesc

2009-01-01

Management of municipal solid waste (MSW) has become a significant environmental problem, especially in fast-growing cities. The amount of waste generated increases each year and this makes it difficult to create solutions which due to the increase in waste generation year after year and having to identify a solution that will have minimum impact on the environment. To determine the most sustainable waste management strategy for Chihuahua, it is first necessary to identify the nature and composition of the city's urban waste. The MSW composition varied considerably depending on many factors, the time of year is one of them. Therefore, as part of our attempt to implement an integral waste management system in the city of Chihuahua, we conducted a study of the characteristics of MSW composition for the different seasons. This paper analyzes and compares the findings of the study of the characterization and the generation of solid waste from households at three different socio-economic levels in the city over three periods (April and August, 2006 and January, 2007). The average weight of waste generated in Chihuahua, taking into account all three seasons, was 0.592 kg capita -1 day -1 . Our results show that the lowest income groups generated the least amount of waste. We also found that less waste was generated during the winter season. The breakdown for the composition of the waste shows that organic waste accounts for the largest proportion (45%), followed by paper (17%) and others (16%).

Seasonal characterization of municipal solid waste (MSW) in the city of Chihuahua, Mexico.

Science.gov (United States)

Gómez, Guadalupe; Meneses, Montserrat; Ballinas, Lourdes; Castells, Francesc

2009-07-01

Management of municipal solid waste (MSW) has become a significant environmental problem, especially in fast-growing cities. The amount of waste generated increases each year and this makes it difficult to create solutions which due to the increase in waste generation year after year and having to identify a solution that will have minimum impact on the environment. To determine the most sustainable waste management strategy for Chihuahua, it is first necessary to identify the nature and composition of the city's urban waste. The MSW composition varied considerably depending on many factors, the time of year is one of them. Therefore, as part of our attempt to implement an integral waste management system in the city of Chihuahua, we conducted a study of the characteristics of MSW composition for the different seasons. This paper analyzes and compares the findings of the study of the characterization and the generation of solid waste from households at three different socio-economic levels in the city over three periods (April and August, 2006 and January, 2007). The average weight of waste generated in Chihuahua, taking into account all three seasons, was 0.592 kg capita(-1) day(-1). Our results show that the lowest income groups generated the least amount of waste. We also found that less waste was generated during the winter season. The breakdown for the composition of the waste shows that organic waste accounts for the largest proportion (45%), followed by paper (17%) and others (16%).

Radionanalysis in solid waste research and management

International Nuclear Information System (INIS)

Das, H.A.

1994-01-01

Risk assessment of dumping or recycling of solid waste makes part of environmental geochemistry. Radioanalysis provides efficient procedures for the characterization of solid wastes, both granular and as recycled products. Radiotracers are applied to measure the situ values of transport parameters. Activation analysis is used in the determination of trace constituents in solids and leachates. This text summarizes some important applications of radioanalysis in this part of environmental monitoring

Solid NMR characterization of hydrogen solid storage matrices

International Nuclear Information System (INIS)

Pilette, M.A.; Charpentier, T.; Berthault, P.

2007-01-01

The aim of this work is to develop and validate characterization tools by NMR imagery and spectroscopy of the structure of materials for hydrogen storage, and of their evolution during load/unload cycles. The two main topics of this work are in one hand the analysis of the local structure of the materials and the understanding of their eventual modifications, and in another hand, the in-situ analysis of the distribution and diffusion of hydrogen inside the storage material. (O.M.)

Dissolution of two NWCF calcines: Extent of dissolution and characterization of undissolved solids

International Nuclear Information System (INIS)

Brewer, K.N.; Herbst, R.S.; Tranter, T.J.

1995-01-01

A study was undertaken to determine the dissolution characteristics of two NWCF calcine types. A two-way blended calcine made from 4 parts nonradioactive aluminum nitrate and one part WM-102 was studied to determine the extent of dissolution for aluminum-type calcines. A two-way blend of 3.5 parts fluorinel waste from WM-187 and 1 part sodium waste from WM-185 was used to determine the extent of dissolution for zirconium-type calcines. This study was necessary to develop suitable aqueous separation flowsheets for the partitioning of actinides and fission products from ICPP calcines and to determine the disposition of the resulting undissolved solids (UDS). The dissolution flowsheet developed by Herbst was used to dissolve these two NWCF calcine types. Results show that greater than 95 wt% of aluminum and zirconium calcine types were dissolved after a single batch contact with 5 M HNO 3 . A characterization of the UDS indicates that the weight percent of TRU elements in the UDS resulting from both calcine type dissolutions increases by approximately an order of magnitude from their concentrations prior to dissolution. Substantial activities of cesium and strontium are also present in the UDS resulting from the dissolution of both calcine types. Multiple TRU, Cs, and Sr analyses of both UDS types show that these solids are relatively homogeneous. From this study, it is estimated that between 63.5 and 635 cubic meters of UDS will be generated from the dissolution of 3800 M 3 of calcine. The significant actinide and fission product activities in these UDS will preclude their disposal as low-level waste. If the actinide and fission activity resulting from the UDS is the only considered source in the dissolved calcine solutions, an estimated 99.9 to 99.99 percent of the solids must be removed from this solution for it to meet non-TRU Class A low-level waste

MIR/NIR/FIR characterization of poly-ammo and poly-bamo and their precursors as energetic binders to Be used in solid propellants

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Jose Irineu S. de; Diniz, Milton F.; Kawamoto, Aparecida M.; Dutra, Rita C.L. [Divisao de Quimica (AQI) Instituto de Aeronautica e Espaco (IAE) do Comando-Geral de Tecnologia Aeroespacial (CTA), Praca Marechal Eduardo Gomes, 50 Campus do CTA - Vila das Acacias, 12228-904 Sao Jose dos Campos - SP (Brazil); Keicher, Thomas [Fraunhofer Institut Chemische Technologie (ICT), Joseph-von-Fraunhofer-Str. 7, 76327 Pfinztal (Germany)

2006-10-15

To establish the relation between structure and properties of composite solid propellants it is important to know the structure of the elastomeric binder that has been used in the system. Therefore this study is focused on the characterization of polymers containing energetic groups that has been synthesized at ICT. The characterization uses the wide spectral band of infrared, NIR/MIR/FIR. This gives an identification of the analytical bands and allows quantitative and kinetic studies of these compounds. (Abstract Copyright [2006], Wiley Periodicals, Inc.)

Thermal Analysis by Structural Characterization as a Method for Assessing Heterogeneity in Complex Solid Pharmaceutical Dosage Forms.

Science.gov (United States)

Alhijjaj, Muqdad; Reading, Mike; Belton, Peter; Qi, Sheng

2015-11-03

Characterizing inter- and intrasample heterogeneity of solid and semisolid pharmaceutical products is important both for rational design of dosage forms and subsequent quality control during manufacture; however, most pharmaceutical products are multicomponent formulations that are challenging in this regard. Thermal analysis, in particular differential scanning calorimetry, is commonly used to obtain structural information, such as degree of crystallinity, or identify the presence of a particular polymorph, but the results are an average over the whole sample; it cannot directly provide information about the spatial distribution of phases. This study demonstrates the use of a new thermo-optical technique, thermal analysis by structural characterization (TASC), that can provide spatially resolved information on thermal transitions by applying a novel algorithm to images acquired by hot stage microscopy. We determined that TASC can be a low cost, relatively rapid method of characterizing heterogeneity and other aspects of structure. In the examples studied, it was found that high heating rates enabled screening times of 3-5 min per sample. In addition, this study demonstrated the higher sensitivity of TASC for detecting the metastable form of polyethylene glycol (PEG) compared to conventional differential scanning calorimetry (DSC). This preliminary work suggests that TASC will be a worthwhile additional tool for characterizing a broad range of materials.

Sample Results from MCU Solids Outage

Energy Technology Data Exchange (ETDEWEB)

Peters, T.; Washington, A.; Oji, L.; Coleman, C.; Poirier, M.

2014-09-22

additional details are provided below as recommendations. From this point on, IC-Anions analyses of the DSSHT should be part of the monthly routine analysis in order to spot negative trends in the oxalate leaving the MCU system. Care must be taken to monitor the oxalate content to watch for sudden precipitation of oxalate salts in the system; Conduct a study to optimize the cleaning strategy at ARP-MCU through decreasing the concentration or entirely eliminating the oxalic acid; The contents of the SSFT should remain unagitated. Routine visual observation should be maintained to ensure there is not a large buildup of solids. As water with agitation provided sufficient removal of the solids in the feed tank, it should be considered as a good means for dissolving oxalate solids if they are found in the future; Conduct a study to improve prediction of oxalate solubility in salt batch feed materials. As titanium and mercury have been found in various solids in this report, evaluate if either element plays a role in oxalate solubility during processing; Salt batch characterization focuses primarily on characterization and testing of unaltered Tank 21H material; however, non-typical feeds are developed through cleaning, washing, and/or sump transfers. As these solutions are processed through MCU, they may precipitate solids or reduce performance. Salt batch characterization and testing should be expanded to encompass a broader range of feeds that may be processed through ARPMCU.

Preparation and Characterization of Emamectin Benzoate Solid Nanodispersion

Directory of Open Access Journals (Sweden)

Dongsheng Yang

2017-01-01

Full Text Available The solid nanodispersion of 15% emamectin benzoate was prepared by the method of solidifying nanoemulsion. The mean particle size and polydispersity index of the solid nanodispersions were 96.6±1.7 nm and 0.352±0.041, respectively. The high zeta potential value of 31.3±0.5 mV and stable crystalline state of the nanoparticles suggested the excellent physical and chemical stabilities. The contact angle and retention compared with microemulsions and water dispersible granules on rice, cabbage, and cucumber leaves indicated its improved wettability and adhesion properties. The bioassay compared with microemulsions and water dispersible granules against diamondback moths and green peach aphids provided an evidence of its enhanced biological activity. This formulation composition could avoid organic solvents and obviously reduce surfactants. It is perspective in raising bioavailability and reducing residual pollution of pesticides and further improving agricultural production and environmental safety.

Preparation and characterization of solid oral dosage forms containing soy isoflavones

Directory of Open Access Journals (Sweden)

Stela R. de Oliveira

2013-02-01

Full Text Available Soy isoflavones have been extensively used for menopausal symptoms and prevention of hormone-related cancer, osteoporosis and cardiovascular diseases. Commercially available forms of isoflavones include supplements, capsules and tablets. However, the non-standardization of soy isoflavones extracts and different dissolution profiles of these solid dosage forms highlight the need of additional studies on the development of well characterized pharmaceutical dosage forms of isoflavones. In this work, immediate release oral tablets of soy isoflavones were obtained and evaluated. Genistein and daidzein, were the main constituents of the dried soy extract. Preparation of the tables was accomplished in a rotary tableting machine following either a dry mixture for direct compression or wet granulation with different excipients. Powder, granules and tablets were evaluated for several parameters, including flow properties, Carr and Hausner indexes, hardness, friability, disintegration time and drug release profile. Also, a fast and validated HPLC analytical method for both genistein and daidzein was developed. Formulations containing sodium croscarmellose and sodium dodecyl sulfate resulted in better flowability as indicated by the flow rate and angle of repose, faster disintegration time and immediate release dissolution profile.

Characterization investigations during mechanical alloying and sintering of Ni-W solid solution alloys dispersed with WC and Y{sub 2}O{sub 3} particles

Energy Technology Data Exchange (ETDEWEB)

Genc, Aziz, E-mail: agenc@itu.edu.t [Particulate Materials Laboratories, Department of Metallurgical and Materials Engineering, Istanbul Technical University, Maslak, 34469 Istanbul (Turkey); Luetfi Ovecoglu, M. [Particulate Materials Laboratories, Department of Metallurgical and Materials Engineering, Istanbul Technical University, Maslak, 34469 Istanbul (Turkey)

2010-10-15

Research highlights: {yields} Characterization investigations on the Ni-W solid solution alloys fabricated via mechanical alloying and the evolution of the properties of the powders with increasing MA durations. {yields} Reinforcement of the selected Ni-W powders with WC and Y{sub 2}O{sub 3} particles and further MA together for 12 h. {yields} There is no reported literature on the development and characterization of Ni-W solid solution alloys matrix composites fabricated via MA. {yields} Sintering of the developed composites and the characterization investigations of the sintered samples. {yields} Identification of new 'pomegranate-like' structures in the bulk of the samples. - Abstract: Blended elemental Ni-30 wt.% W powders were mechanically alloyed (MA'd) for 1 h, 3 h, 6 h, 12 h, 24 h, 36 h and 48 h in a Spex mixer/mill at room temperature in order to investigate the effects of MA duration on the solubility of W in Ni and the grain size, hardness and particle size. Microstructural and phase characterizations of the MA'd powders were carried out using X-ray diffractometer (XRD), scanning electron microscope (SEM) and transmission electron microscope (TEM). On the basis of achieved saturation on the solid solubility, hardness and particle size, the Ni-30 wt.% W powders MA'd for 48 h were chosen as the matrix which was reinforced with different amounts of WC and/or with 1 wt.% Y{sub 2}O{sub 3} particles. The reinforced powders were further MA'd for 12 h. The MA'd powders were sintered at 1300 {sup o}C for 1 h under Ar and H{sub 2} gas flowing conditions. Microstructural characterizations of the sintered samples were conducted via XRD and SEM. Sintered densities were measured by using the Archimedes' method. Vickers microhardness tests were performed on both MA'd powders and the sintered samples. Sliding wear experiments were done in order to investigate wear behaviors of the sintered samples.

Synthesis and Characterization of Zeolite Na−Y and Its Conversion to the Solid Acid Zeolite H−Y

DEFF Research Database (Denmark)

Warner, Terence Edwin; Galsgaard Klokker, Mads; Nielsen, Ulla Gro

2017-01-01

Zeolite Y has an iconic crystal structure, but more importantly, the hydrogen modification zeolite H−Y is the classic example of a solid acid which is used extensively as a catalyst in the oil industry. This metastable compound cannot be synthesized directly, which creates an opportunity to discuss...... various preparative strategies with the students, such as the three-stage procedure described here. Stage I concerns the hydrothermal synthesis of zeolite Na−Y, followed by ion-exchange with an ammonium acetate solution to form zeolite NH4−Y, and the latter is subsequently converted to zeolite H......−Y by thermolysis. Stages II and III may instead be performed using commercially available zeolites, Na−Y and NH4−Y, respectively, which shifts the learning objectives to structural characterization of zeolites. The characterization of the product and intermediate materials gives the students a practical insight...

Synthesis and characterization of solid solutions in ABCO 4 system

Science.gov (United States)

Novoselov, A.; Zimina, G.; Komissarova, L.; Pajaczkowska, A.

2006-01-01

Formation of continuous solid solutions with a tetragonal structure of K 2NiF 4-type was investigated by direct solid-state synthesis, carbonate precipitations, the freeze-drying method and the Czochralski crystal growth technique. In the systems of SrLaAlO 4-CaLaAlO 4, SrNdAlO 4-CaNdAlO 4, SrPrAlO 4-CaPrAlO 4, SrLaAlO 4-SrLaGaO 4 and SrLaAlO 4-SrLaFeO 4 solid solutions are formed in the whole concentration range (0.0⩽ x⩽1.0) and in the systems of SrLaAlO 4-SrLaMnO 4 and SrLaAlO 4-SrLaCrO 4 in the limited compositional interval of (0.0⩽ x⩽0.20) and (0.0⩽ x⩽0.25), respectively, with composition dependency of lattice constants following Vegard's law.

Program plan for the development of Solid Waste Storage Area 7 at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Lomenick, T.F.; Gonzales, S.; Byerly, D.W.

1984-02-01

The need for additional waste-burial facilities for low-level radwastes generated at Oak Ridge National Laboratory mandates development of a program to identify and evaluate an acceptable new Solid Waste Storage Area (SWSA 7). Provisions of this program include plans for identifying and evaluating SWSA 7 as well as plans for the necessary technical efforts for designing and monitoring a waste-burial facility. The development of the program plan is in accordance with general procedures issued by ORNL, and if adhered to, should meet proposed criteria and guidelines issued by such organizations as the Nuclear Regulatory Commission, the Environmental Protection Agency, the Department of Energy, and the Tennessee Department of Health. The major parts of the program include plans for (1) the acquisition of data necessary for geotechnical evaluation of a site, (2) the engineering design and construction of a facility which would be compatible with the geology and the classification and particular character of the wastes to be disposed, and (3) a monitoring system for achieving health and safety standards and environmental protection. The objective of the program, to develop SWSA 7, can only be achieved through sound management. Plans provided in this program which will ensure successful management include quality assurance, corrective measures, safety analysis, environmental impact statements, and schedule and budget

All-solid-state potassium-selective electrode using graphene as the solid contact

DEFF Research Database (Denmark)

Li, Fenghua; Ye, Junjin; Zhou, Min

2012-01-01

Graphene sheets are used for the first time to fabricate a new type of solid-contact ion-selective electrode (SC-ISE) as the intermediate layer between an ionophore-doped solvent polymeric membrane and a glassy carbon electrode. The new transducing layer was characterized by transmission electron...

Brain-targeted solid lipid nanoparticles containing riluzole: preparation, characterization and biodistribution.

Science.gov (United States)

Bondì, Maria Luisa; Craparo, Emanuela Fabiola; Giammona, Gaetano; Drago, Filippo

2010-01-01

Developments within nanomedicine have revealed a great potential for drug delivery to the brain. In this study nanoparticulate systems as drug carriers for riluzole, with sufficiently high loading capacity and small particle size, were prepared to a reach therapeutic drug level in the brain. Solid lipid nanoparticles containing riluzole have great potential as drug-delivery systems for amyotrophic lateral sclerosis and were produced by using the warm oil-in-water microemulsion technique. The resulting systems obtained were approximately 88 nm in size and negatively charged. Drug-release profiles demonstrated that a drug release was dependent on medium pH. Biodistribution of riluzole blended into solid lipid nanoparticles was carried out after administration to rats and the results were compared with those obtained by riluzole aqueous dispersion administration. Rats were sacrificed at time intervals of 8, 16 and 30 h, and the riluzole concentration in the blood and organs such as the brain, liver, spleen, heart and kidney was determined. It was demonstrated that these solid lipid nanoparticles were able to successfully carry riluzole into the CNS. Moreover, a low drug biodistribution in organs such as the liver, spleen, heart, kidneys and lung was found when riluzole was administered as drug-loaded solid lipid nanoparticles. Riluzole-loaded solid lipid nanoparticles showed colloidal size and high drug loading, a greater efficacy than free riluzole in rats, a higher capability to carry the drug into the brain and a lower indiscriminate biodistribution.

Summary of environmental characterization activities at the Oak Ridge National Laboratory Solid Waste Storage Area Six, FY 1986 through 1987

International Nuclear Information System (INIS)

Davis, E.C.; Solomon, D.K.; Dreier, R.B.; Lee, S.Y.; Kelmers, A.D.; Lietzke, D.A.; Craig, P.M.

1987-01-01

The Oak Ridge National Laboratory (ORNL) Remedial Action Program (RAP), has supported characterization activities in Solid Waste Storage Area (SWSA 6) to acquire information necessary for identification and planning of remedial actions that may be warranted, and to facilitate eventual closure of the site. In FY 1986 investigations began in the areas of site hydrology, geochemistry, soils, geology, and geohydrologic model application. This report summarizes work carried out in each of these areas during FY's 1986 and 1987 and serves as a status report pulling together the large volume of data that has resulted. Characterization efforts are by no means completed; however, a sufficient data base has been generated to begin data interpretation and analysis of site contaminants

Synthesis, characterization and thermal stability of solid solutions Zr (Y, Fe, Mo)O {sub 2}

Energy Technology Data Exchange (ETDEWEB)

Legorreta-Garcia, F.; Esperanza Hernandez-Cruz, L.; Villanueva-Ibanez, M.; Flores-Gonzalez, M. A.

2015-10-01

The synthesis of Fe{sup 3}+, Mo{sup 4+} and Y{sup 3+} fully stabilized zirconia by the nitrate/urea combustion route and thermal stability in air was investigated. The solid solution obtained was characterized by X ray diffraction (XRD), scanning electron microscopy (SEM) and used the BET method for determining specific surface. The ceramic powders obtained were calcined at 1473 K in air atmosphere in order to determine their thermal stability. The scanning electron microscopy (SEM) results showed a homogeneous grain surface, measuring several tens of micrometers across. The crystallographic study revealed that by this method it was successfully achieved zirconia doped with Fe{sup 3+}, Mo{sup 4+} and Y{sup 3+} ions in the zirconia tetragonal monophase, even after calcinations. (Author)

Low-level radioactive waste processing at nuclear power plants

International Nuclear Information System (INIS)

1992-12-01

This survey was limited to systems and materials used to process waste liquids contaminated with radionuclides. Since the chemical and radiological character of collected liquids may change dramatically, the survey describes waste and cleanup process streams encountered during normal outage or power production conditions. Influents containing specific organic compounds, salts, or solids common to local sources, and the special techniques developed to remove or concentrate these materials are not detailed in this report. The names and phone numbers of the individuals responsible for investigating and solving these problems, however, provides easy access to data which will save time and expense when facing abnormal processing, purchasing, or engineering challenges. The Liquid Radwaste Source Book contains information collected from 31 of 36 BWR's as well as contact information from all licensed commercial units. Since some sites share common radwaste processing facilities, not all units are represented by individual data sheets

How drops start sliding over solid surfaces

Science.gov (United States)

Gao, Nan; Geyer, Florian; Pilat, Dominik W.; Wooh, Sanghyuk; Vollmer, Doris; Butt, Hans-Jürgen; Berger, Rüdiger

2018-02-01

It has been known for more than 200 years that the maximum static friction force between two solid surfaces is usually greater than the kinetic friction force--the force that is required to maintain the relative motion of the surfaces once the static force has been overcome. But the forces that impede the lateral motion of a drop of liquid on a solid surface are not as well characterized, and there is a lack of understanding about liquid-solid friction in general. Here, we report that the lateral adhesion force between a liquid drop and a solid can also be divided into a static and a kinetic regime. This striking analogy with solid-solid friction is a generic phenomenon that holds for liquids of different polarities and surface tensions on smooth, rough and structured surfaces.

A high pressure x-ray photoelectron spectroscopy experimental method for characterization of solid-liquid interfaces demonstrated with a Li-ion battery system

Energy Technology Data Exchange (ETDEWEB)

Maibach, Julia; Xu, Chao; Gustafsson, Torbjörn; Edström, Kristina [Department of Chemistry–Ångström Laboratory, Uppsala University, Box 538, SE-751 21 Uppsala (Sweden); Eriksson, Susanna K. [Department of Chemistry–Ångström Laboratory, Uppsala University, Box 523, SE-751 20 Uppsala (Sweden); Åhlund, John [VG Scienta AB, Box 15120, SE-750 15 Uppsala (Sweden); Siegbahn, Hans; Rensmo, Håkan; Hahlin, Maria, E-mail: maria.hahlin@physics.uu.se [Department of Physics and Astronomy, Uppsala University, Box 516, SE-751 20 Uppsala (Sweden)

2015-04-15

We report a methodology for a direct investigation of the solid/liquid interface using high pressure x-ray photoelectron spectroscopy (HPXPS). The technique was demonstrated with an electrochemical system represented by a Li-ion battery using a silicon electrode and a liquid electrolyte of LiClO{sub 4} in propylene carbonate (PC) cycled versus metallic lithium. For the first time the presence of a liquid electrolyte was realized using a transfer procedure where the sample was introduced into a 2 mbar N{sub 2} environment in the analysis chamber without an intermediate ultrahigh vacuum (UHV) step in the load lock. The procedure was characterized in detail concerning lateral drop gradients as well as stability of measurement conditions over time. The X-ray photoelectron spectroscopy (XPS) measurements demonstrate that the solid substrate and the liquid electrolyte can be observed simultaneously. The results show that the solid electrolyte interphase (SEI) composition for the wet electrode is stable within the probing time and generally agrees well with traditional UHV studies. Since the methodology can easily be adjusted to various high pressure photoelectron spectroscopy systems, extending the approach towards operando solid/liquid interface studies using liquid electrolytes seems now feasible.

Solid State Division progress report, September 30, 1981

Energy Technology Data Exchange (ETDEWEB)

1982-04-01

Progress made during the 19 months from March 1, 1980, through September 30, 1981, is reported in the following areas: theoretical solid state physics (surfaces, electronic and magnetic properties, particle-solid interactions, and laser annealing); surface and near-surface properties of solids (plasma materials interactions, ion-solid interactions, pulsed laser annealing, and semiconductor physics and photovoltaic conversion); defects in solids (radiation effects, fracture, and defects and impurities in insulating crystals); transport properties of solids (fast-ion conductors, superconductivity, and physical properties of insulating materials); neutron scattering (small-angle scattering, lattice dynamics, and magnetic properties); crystal growth and characterization (nuclear waste forms, ferroelectric mateirals, high-temperature materials, and special materials); and isotope research materials. Publications and papers are listed. (WHK)

Solid State Division progress report, September 30, 1981

International Nuclear Information System (INIS)

1982-04-01

Progress made during the 19 months from March 1, 1980, through September 30, 1981, is reported in the following areas: theoretical solid state physics (surfaces, electronic and magnetic properties, particle-solid interactions, and laser annealing); surface and near-surface properties of solids (plasma materials interactions, ion-solid interactions, pulsed laser annealing, and semiconductor physics and photovoltaic conversion); defects in solids (radiation effects, fracture, and defects and impurities in insulating crystals); transport properties of solids (fast-ion conductors, superconductivity, and physical properties of insulating materials); neutron scattering (small-angle scattering, lattice dynamics, and magnetic properties); crystal growth and characterization (nuclear waste forms, ferroelectric mateirals, high-temperature materials, and special materials); and isotope research materials. Publications and papers are listed

Synthesis and characterization of CeO2-TiO2-Pr6O11 solid solutions for environmentally benign nontoxic red pigments

International Nuclear Information System (INIS)

George, Giable; Rao, Padala Prabhakar; Reddy, Mundlapudi Lakshmipathi

2006-01-01

New inorganic pigments Ce 1-(x+y) Ti x Pr y O 2 (x ranges from 0.05 to 0.195 and y ranges from 0.005 to 0.15) based on CeO 2 -TiO 2 -Pr 6 O 11 solid solutions have been synthesized by solid-state route with a goal of preparing environmentally secure red colorants. Characterizations using XRD, UV-vis spectroscopy and CIE 1976 color coordinates assessment reveals the formation of pigments displaying colors ranging from brick red to dark brown. The coloring mechanism is based on the introduction of additional electronic level of energy in the cerianite forbidden band from the unpaired 4f electron of lanthanide ion. (author)

Radwaste incineration, is it ready for use

International Nuclear Information System (INIS)

Coplan, B.W.

1982-01-01

The incinerator installed at JAERI in 1973 has the record of being operated continually for eight years without noticeable damage even in the refractories. We are convinced that it can be used for along period of time. These incinerators in Japan are now regarded as the useful and reliable waste management facilities, though they are processing the restricted sorts of wastes, such as low level ombustible solids and oils. In the future, incinerators of these types are supposed to increase in number in Japan, and they will continue to contribute as an important volume reduction measure which can also convert the wastes to chemically stable substances

Combined Approach for the Structural Characterization of Alkali Fluoroscandates: Solid-State NMR, Powder X-ray Diffraction, and Density Functional Theory Calculations.

Science.gov (United States)

Rakhmatullin, Aydar; Polovov, Ilya B; Maltsev, Dmitry; Allix, Mathieu; Volkovich, Vladimir; Chukin, Andrey V; Boča, Miroslav; Bessada, Catherine

2018-02-05

The structures of several fluoroscandate compounds are presented here using a characterization approach combining powder X-ray diffraction and solid-state NMR. The structure of K 5 Sc 3 F 14 was fully determined from Rietveld refinement performed on powder X-ray diffraction data. Moreover, the local structures of NaScF 4 , Li 3 ScF 6 , KSc 2 F 7 , and Na 3 ScF 6 compounds were studied in detail from solid-state 19 F and 45 Sc NMR experiments. The 45 Sc chemical shift ranges for six- and seven-coordinated scandium environments were defined. The 19 F chemical shift ranges for bridging and terminal fluorine atoms were also determined. First-principles calculations of the 19 F and 45 Sc NMR parameters were carried out using plane-wave basis sets and periodic boundary conditions (CASTEP), and the results were compared with the experimental data. A good agreement between the calculated shielding constants and experimental chemical shifts was obtained. This demonstrates the good potential of computational methods in spectroscopic assignments of solid-state 45 Sc NMR spectroscopy.

Safety control and minimization of radioactive wastes

International Nuclear Information System (INIS)

Wang Jinming; Rong Feng; Li Jinyan; Wang Xin

2010-01-01

Compared with the developed countries, the safety control and minimization of the radwastes in China are under-developed. The research of measures for the safety control and minimization of the radwastes is very important for the safety control of the radwastes, and the reduction of the treatment and disposal cost and environment radiation hazards. This paper has systematically discussed the safety control and the minimization of the radwastes produced in the nuclear fuel circulation, nuclear technology applications and the process of decommission of nuclear facilities, and has provided some measures and methods for the safety control and minimization of the radwastes. (authors)

Solid-state characterization and impurities determination of fluconazol generic products marketed in Morocco

Science.gov (United States)

Bourichi, Houda; Brik, Youness; Hubert, Philipe; Cherrah, Yahia; Bouklouze, Abdelaziz

2012-01-01

In this paper, we report the results of quality control based in physicochemical characterization and impurities determination of three samples of fluconazole drug substances marketed in Morocco. These samples were supplied by different pharmaceuticals companies. The sample A, as the discovered product, was supplied by Pfizer, while samples B and C (generics), were manufactured by two different Indian industries. Solid-state characterization of the three samples was realized with different physicochemical methods as: X-ray powder diffraction, Fourier-transformation infrared spectroscopy, differential scanning calorimetry. High performance liquid chromatography was used to quantify the impurities in the different samples. The results from the physicochemical methods cited above, showed difference in polymorph structure of the three drug substances. Sample A consisted in pure polymorph III, sample B consisted in pure polymorph II, sample C consisted in a mixture of fluconazole Form III, form II and the monohydrate. This result was confirmed by differential scanning calorimetry. Also it was demonstrated that solvents used during the re-crystallization step were among the origins of these differences in the structure form. On the other hand, the result of the stability study under humidity and temperature showed that fluconazole polymorphic transformation could be owed to the no compliance with the conditions of storage. The HPLC analysis of these compounds showed the presence of specific impurities for each polymorphic form, and a possible relationship could be exist between impurities and crystalline form of fluconazole. PMID:29403776

Production and Characterization of Anti-LH Polyclonal Antibodies for Establishment of Sepharose Solid Phase Radioimmunoassay

International Nuclear Information System (INIS)

Ebeid, N.H.; Mehany, N.L.

2016-01-01

The present study was designed to achieve the production and characterization of polyclonal antibody of luteinizing hormone (Anti-LH) as a basic component of LH radioimmunoassay (RIA). The main objective was to improve the immunogenicity of LH by conjugation of LH with bovine serum albumin (LH: BSA) as a protein carrier using Ethyl dimethylaminopropyl Carbodiimide (ECDI). Production of Anti-LH was described where LH : BSA immunogen was immunized into three male mature white New-Zealand rabbits through primary immunization and four boosters. The criteria for selecting LH antiserum for liquid phase RIA system were mainly titer, displacement and immuno response profile and followed by partial purification of IgG-LH. The radioiodinated 125 I-LH tracer was carried out using Chloramine-T as an oxidizing agent and the tracer was purified through PD-10 column. The preparation of LH standards was carried out. Coupling of purified IgG-LH to activated Sepharose particles CL-4B was carried out after activation of Sepharose particles with 1,1-carbonyldiimidazole. Extensive studies were carried out to obtain the optimum conditions of using solid phase Sepharose particles to reach the optimum separation efficiency. The results of validation tests revealed that the local solid phase RIA system is precise and accurate to detect LH concentration in human serum to be used as a diagnostic tool in investigating the infertility in the hypothalamic pituitary gonadal disorders

Summary of environmental characterization activities at the Oak Ridge National Laboratory Solid Waste Storage Area Six, FY 1986 through 1987

Energy Technology Data Exchange (ETDEWEB)

Davis, E.C.; Solomon, D.K.; Dreier, R.B.; Lee, S.Y.; Kelmers, A.D.; Lietzke, D.A. (Oak Ridge National Lab., TN (United States)); Craig, P.M. (Environmental Consulting Engineers, Inc., Knoxville, TN (United States))

1987-09-30

The Oak Ridge National Laboratory (ORNL) Remedial Action Program (RAP), has supported characterization activities in Solid Waste Storage Area (SWSA 6) to acquire information necessary for identification and planning of remedial actions that may be warranted, and to facilitate eventual closure of the site. In FY 1986 investigations began in the areas of site hydrology, geochemistry, soils, geology, and geohydrologic model application. This report summarizes work carried out in each of these areas during FY's 1986 and 1987 and serves as a status report pulling together the large volume of data that has resulted. Characterization efforts are by no means completed; however, a sufficient data base has been generated to begin data interpretation and analysis of site contaminants.

Oriented solid-state NMR spectrosocpy

DEFF Research Database (Denmark)

Bertelsen, Kresten

This thesis is concerned with driving forward oriented solid-state NMR spectroscopy as a viable technique for studying peptides in membrane bilayers. I will show that structural heterogeneity is an intrinsic part of the peptide/lipid system and that NMR can be used to characterize static...... and dynamic structural features of the peptides and its local surroundings. In fact one need to take into account the dynamical features of the system in order to correctly predict the structure from oriented solid-state NMR spectra.      ...

Cements in radioactive waste management. Characterization requirements of cement products for acceptance and quality assurance purposes

International Nuclear Information System (INIS)

Rahman, A.A.; Glasser, F.P.

1987-01-01

Cementitious materials are used as immobilizing matrices for low (LLW) and medium-level wastes (MLW) and are also components of the construction materials in the secondary barriers and the repositories. This report has concerned itself with a critical assessment of the quality assurance aspects of the immobilization and disposal of MLW and LLW cemented wastes. This report has collated the existing knowledge of the use and potential of cementitious materials in radioactive waste immobilization and highlighted the physico-chemical parameters. Subject areas include an assessment of immobilization objectives and cement as a durable material, waste stream and matrix characterization, quality assurance concepts, nature of cement-based systems, chemistry and modelling of cement hydration, role and effect of blending agents, radwaste-cement interaction, assessment of durability, degradative and radiolytic processes in cements and the behaviour of cement-based matrices and their near-field interactions with the environment and the repository conditions

Solid State Division: Progress report for period ending September 30, 1987

Energy Technology Data Exchange (ETDEWEB)

Green, P.H.; Watson, D.M. (eds.)

1988-03-01

This paper contains a collection of articles on research done at the Solid State Division of ORNL. General topics covered are: theoretical solid state physics; neutron scattering; physical properties of superconductors and ceramics; synthesis and characterization of solids; ion beam and laser processing; and surface and defect studies. (LSP)

Solid State Division: Progress report for period ending September 30, 1987

International Nuclear Information System (INIS)

Green, P.H.; Watson, D.M.

1988-03-01

This paper contains a collection of articles on research done at the Solid State Division of ORNL. General topics covered are: theoretical solid state physics; neutron scattering; physical properties of superconductors and ceramics; synthesis and characterization of solids; ion beam and laser processing; and surface and defect studies

Project management of radwaste retrofits

International Nuclear Information System (INIS)

Vaught, D.L.

1988-01-01

Many utilities are finding it necessary to provide additional radioactive waste processing facilities at operating or nearly completed nuclear stations in order to accommodate the ever-changing regulatory, political and socio-economic environment in which we operate. This paper describes the project approach taken at Duke Power Company to provide a comprehensive radioactive waste processing facility at Oconee Nuclear Station. Following a historical perspective, the philosophy and mechanics of the project team are discussed. The goal of the project team was to provide a facility which could meet the liquid and solid radioactive waste processing needs of Oconee within the restraints of a utility budget and schedule. The unique quality of the project team approach was the integral involvement of all of the necessary departments in every part of the design, construction and start-up phases. The project team thereby utilized feedback from over thirty reactor years of operational experience. The remainder of the paper provides examples of the problems encountered and their resolution (eg. equipment layout, materials handling, vendor improvements and regulatory changes all required design-in-progress changes). It has been the integration and concentration of the diverse resources of a large utility into a cross-departmental team which has allowed the timely resolution of the necessary changes. This same philosophy is being applied to the facility start-up program and to other major projects at Duke Power Company

Fabrication and Characterization of Graded Anodes for Anode-Supported Solid Oxide Fuel Cells by Tape Casting and Lamination

DEFF Research Database (Denmark)

Beltran-Lopez, J.F.; Laguna-Bercero, M.A.; Gurauskis, Jonas

2014-01-01

Graded anodes for anode-supported solid oxide fuel cells (SOFCs) are fabricated by tape casting and subsequent cold lamination of plates using different compositions. Rheological parameters are adjusted to obtain stable suspensions for tape casting. The conditions for the tape casting and laminat......Graded anodes for anode-supported solid oxide fuel cells (SOFCs) are fabricated by tape casting and subsequent cold lamination of plates using different compositions. Rheological parameters are adjusted to obtain stable suspensions for tape casting. The conditions for the tape casting...... and lamination will be described. Flexural strength of the reduced cermets measured using three-point bending configuration is 468±37MPa. The graded anode supports are characterized by scanning electron microscope observations, mercury porosimetry intrusion, and resistivity measurements, showing an adequate...... of tapes at room temperature without using plasticizers. This is made by the combination of two different binders with varying Tg (glass transition temperature) which resulted in plastic deformation at room temperature. Those results indicate that the proposed process is a cost-effective method...

Structural characterization of lignin in the process of cooking of cornstalk with solid alkali and active oxygen.

Science.gov (United States)

Yang, Qiulin; Shi, Jianbin; Lin, Lu; Zhuang, Junping; Pang, Chunsheng; Xie, Tujun; Liu, Ying

2012-05-09

A novel, efficient, and environmentally friendly technology is used in cornstalk cooking, active oxygen (O₂ and H₂O₂) cooking with solid alkali (MgO). After the cooking, the milled wood lignin in the raw material and pulp and the water-soluble and insoluble lignin in the yellow liquor were all characterized by attenuated total reflectance Fourier transform infrared spectroscopy and two-dimensional heteronuclear single-quantum coherence NMR. The results showed that the cooking procedure with solid alkali and active oxygen had a high selectivity for delignification, which could remove 85.5% of the lignin from the raw material. The syringyl (S/S'/S') units could be dissolved preferentially because of their high reactivity, and a novel guaiacyl unit with a carbonyl group (G') was generated in the cooking process. Moreover, during the cooking, the β-O-4' (A/A'/A″) structures as the main side-chain linkages in all the lignins could be partly broken and the β-O-4' (A') with a ring-conjugated structure was readily attacked by oxygen, whereas the H unit and β-5' and β-β' structures were found to stay stable without characteristic reaction.

Characterization of the volatile profiles of beer using headspace solid-phase microextraction and gas chromatography-mass spectrometry.

Science.gov (United States)

Rossi, Serena; Sileoni, Valeria; Perretti, Giuseppe; Marconi, Ombretta

2014-03-30

The objective of this study was a multivariate characterization of the volatile profile of beers. Such a characterization is timely considering the increasing worldwide consumption of beer, the continuous growth of microbreweries and the importance of volatile compounds to beer flavour. A method employing solid-phase microextraction and gas chromatography-mass spectrometry (SPME-GC-MS) was optimized and then applied to a sample set of 36 industrial and craft beers of various styles and fermentation types. The volatile profiles of different beer styles is described, with particular attention paid to the volatile compounds characteristic of a spontaneously fermented lambic raspberry framboise beer. Furthermore, it was also possible to identify which specific volatile compounds are principally responsible for the differences in the volatile profiles of top- and bottom-fermented beers. Moreover, a volatile fingerprint of the craft top-fermented Italian beers was defined, as they show a very similar volatile profile. Finally, the volatile compounds that are characteristic of the bock-style beers are described. The SPME-GC-MS analytical method optimized in this study is suitable for characterizing the volatile fingerprint of different beers, especially on the basis of the kind of fermentation (top, bottom or spontaneous), the method of production and the style of the beer. © 2013 Society of Chemical Industry.

A Toolbox of Solid-State NMR Experiments for the Characterization of Soft Organic Nanomaterials

KAUST Repository

Straasø, Lasse Arnt

2016-02-02

Determining how organic molecules self-assemble into a solid material is a challenging and demanding task if a single crystal of the material cannot be produced. Solid-state NMR spectroscopy offers access to such molecular details via an appropriate selection of techniques. This report gives a selected overview of 1D and 2D solid-state NMR techniques for elucidating the structure of soft organic solids. We focus on how the solid-state NMR techniques are designed from the perspective of the different nuclear interactions, using average Hamiltonian theory and product operators. We also introduce recent methods for quantification and reduction of experimental artifacts. Finally, we highlight how the solid-state NMR techniques can be applied to soft organic materials by reviewing recent applications to semicrystalline polymers, π-conjugated polymers, natural silk, and graphene-related materials.

A Toolbox of Solid-State NMR Experiments for the Characterization of Soft Organic Nanomaterials

KAUST Repository

Straasø , Lasse Arnt; Saleem, Qasim; Hansen, Michael Ryan

2016-01-01

Determining how organic molecules self-assemble into a solid material is a challenging and demanding task if a single crystal of the material cannot be produced. Solid-state NMR spectroscopy offers access to such molecular details via an appropriate selection of techniques. This report gives a selected overview of 1D and 2D solid-state NMR techniques for elucidating the structure of soft organic solids. We focus on how the solid-state NMR techniques are designed from the perspective of the different nuclear interactions, using average Hamiltonian theory and product operators. We also introduce recent methods for quantification and reduction of experimental artifacts. Finally, we highlight how the solid-state NMR techniques can be applied to soft organic materials by reviewing recent applications to semicrystalline polymers, π-conjugated polymers, natural silk, and graphene-related materials.

Immobilization of radwastes in glass containers and products formed thereby

International Nuclear Information System (INIS)

Macedo, P.B.; Litovitz, T.A.; Simmons, C.J.; Simmons, J.H.; Lagakos, N.; Tran, D.C.

1982-01-01

A mixture of glass packing and radioactive or other toxic material is placed in a solid glass container, and the container is heated to drive off volatile components and collapse and seal the container

Status of radioactive waste management in Taiwan

International Nuclear Information System (INIS)

Huang, C.C.

1993-01-01

Taiwan started to generate nuclear power in 1977. The peaceful uses of nuclear energy generated radwaste. The major radwaste generators are nuclear power plants of Taiwan Power Company (Taipower). The other generators are the Institute of Nuclear Energy Research (INER), industry, medicine, agriculture, and education. Radwaste Administration (RWA), a subsidiary of Atomic Energy Council (AEC), is the regulatory body of radwaste in Taiwan. Radwaste management projects in Taiwan include: (1) construction of a Volume Reduction Center (VRC); (2) construction of a low-level radwaste transport ship; (3) construction of low-level waste final disposal facility; (4) construction of a spent fuel interim storage facility; (5) construction of spent fuel disposal facility. In the near future, final disposal of low-level waste is the most important work of both Taipower and RWA. Both organizations will put much more effort into this work

Characterization of the solid, airborne materials created when UF6 reacts with moist air flowing in single-pass mode

International Nuclear Information System (INIS)

Pickrell, P.W.

1985-10-01

A series of experiments has been performed in which UF 6 was released into flowing air in order to characterize the solid particulate material produced under non-static conditions. In two of the experiments, the aerosol was allowed to stagnate in a static chamber after release and examined further but in the other experiments characterization was done only on material collected a few seconds after release. Transmission electron microscopy and mass measurement by cascaded impactor were used to characterize the aerosol particles which were usually single spheroids with little agglomeration in evidence. The goal of the work is to determine the chemistry and physics of the UF 6 -atmospheric moisture reaction under a variety of conditions so that information about resulting species and product morphologies is available for containment and removal (knockdown) studies as well as for dispersion plume modeling and toxicology studies. This report completes the milestone for reporting the information obtained from releases of UF 6 into flowing rather than static air. 26 figs., 3 tabs

Development of techniques for radwaste systems in CANDU power stations

International Nuclear Information System (INIS)

Bourns, W.T.; Buckley, L.P.; Burrill, K.A.

1979-04-01

Techniques to reduce the volume of CANDU reactor wastes and to bitumenize them are being developed at Chalk River Nuclear Laboratories. Reverse osmosis is suitable for initial purification of dilute radioactive aqueous wastes. Tubular membranes are used to concentrate wastes to 5 weight percent solids, and while the membranes do foul, they may be cleaned mechanically, chemically, or with fresh feed. A wiped-film evaporator then concentrates the retentate to a 20 weight-percent slurry. A twin-screw extruder-evaporator has been used to bitumenize this slurry, and it will also handle ion exchange resin and dry incinerator ash. Work on a wiped-film evaporator as a bitumenizer for various feeds is in progress. More experience in handling solid feeds is needed before work can proceed to the demonstraton phase. (auth)

Solid State Division progress report for period ending September 30, 1984

International Nuclear Information System (INIS)

Green, P.H.; Watson, D.M.

1985-03-01

During the reporting period, relatively minor changes have occurred in the research areas of interest to the Division. Nearly all the research of the Division can be classified broadly as mission-oriented basic research. Topics covered include: theoretical solid state physics; surface and near-surface properties of solids; defects in solids; transport properties of solids; neutron scattering; and preparation and characterization of research materials

Solid State Division progress report for period ending September 30, 1984

Energy Technology Data Exchange (ETDEWEB)

Green, P.H.; Watson, D.M. (eds.)

1985-03-01

During the reporting period, relatively minor changes have occurred in the research areas of interest to the Division. Nearly all the research of the Division can be classified broadly as mission-oriented basic research. Topics covered include: theoretical solid state physics; surface and near-surface properties of solids; defects in solids; transport properties of solids; neutron scattering; and preparation and characterization of research materials. (GHT)

Physico-Chemical Characterizations of Sawdust-Derived Bio char as Potential Solid Fuels

International Nuclear Information System (INIS)

Wan Azlina Wan Ab Karim Ghani

2014-01-01

Characterization Malaysian rubber-wood sawdust derived bio char (MRWSB) produced in the fixed bed pyrolysis under different temperatures (450 to 850 degree Celsius) were studied for its applicability as a solid fuel. A range of analyses were carried out, including bio char oxidation reactivity , inorganic species, oxygen and hydrogen contents in the bio chars, release of heteroatoms in bio char as the gaseous product, and bio char structural evolution during pyrolysis process. The results show that the optimum temperature for carbonization to obtain a char having moderately high yield was found as 450 degree Celsius. Thermogravimetric analyses (TG) shows that temperatures induces a progressively more ordered carbonaceous structure and leads to a significant changes in the bio char reactivity. The process is coupled with the loss of heteroatoms, released as dominantly carbon dioxide (C0 2 ) and carbon dioxide (CO). In addition, the elemental study of wood-derived bio char shows the higher carbon content but with low H/C and 0/C ratio suggested this material was dominated by highly aromatic structures and this were revealed in the Fourier transform infra-red (FTIR). More importantly, insignificant amount of inorganic species is evidenced in the samples. (author)

Fusion fuel cycle solid radioactive wastes

International Nuclear Information System (INIS)

Gore, B.F.; Kaser, J.D.; Kabele, T.J.

1978-06-01

Eight conceptual deuterium-tritium fueled fusion power plant designs have been analyzed to identify waste sources, materials and quantities. All plant designs include the entire D-T fuel cycle within each plant. Wastes identified include radiation-damaged structural, moderating, and fertile materials; getter materials for removing corrosion products and other impurities from coolants; absorbents for removing tritium from ventilation air; getter materials for tritium recovery from fertile materials; vacuum pump oil and mercury sludge; failed equipment; decontamination wastes; and laundry waste. Radioactivity in these materials results primarily from neutron activation and from tritium contamination. For the designs analyzed annual radwaste volume was estimated to be 150 to 600 m 3 /GWe. This may be compared to 500 to 1300 m 3 /GWe estimated for the LMFBR fuel cycle. Major waste sources are replaced reactor structures and decontamination waste

Liquid radioactive waste processing improvement of PWR nuclear power plants; Melhorias no processamento de rejeitos liquidos radioativos de usinas nucleares PWR

Energy Technology Data Exchange (ETDEWEB)

Nery, Renata Wolter dos Reis; Martinez, Aquilino Senra; Monteiro, Jose Luiz Fontes [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear]. E-mail: wolter@eletronuclear.gov.br; monteiro@peq.coppe.ufrj.br; aquilinosenra@lmp.ufrj.br

2005-07-01

The study evaluate an inorganic ion exchange to process the low level liquid radwaste of PWR nuclear plants, so that the level of the radioactivity in the effluents and the solid waste produced during the treatment of these liquid radwaste can be reduced. The work compares two types of ion exchange materials, a strong acid cation exchange resin, that is the material typically used to remove radionuclides from PWR nuclear plants wastes, and a mordenite zeolite. These exchange material were used to remove cesium from a synthetic effluent containing only this ion and another effluent containing cesium and cobalt. The breakthrough curves of the zeolite and resin using a fix bed reactor were compared. The results demonstrated that the zeolite is more efficient than the resin in removing cesium from a solution containing cesium and cobalt. The results also showed that a bed combining zeolite and resin can process more volume of an effluent containing cesium and cobalt than a bed resin alone. (author)

Liquid radioactive waste processing improvement of PWR nuclear power plants

International Nuclear Information System (INIS)

Nery, Renata Wolter dos Reis; Martinez, Aquilino Senra; Monteiro, Jose Luiz Fontes

2005-01-01

The study evaluate an inorganic ion exchange to process the low level liquid radwaste of PWR nuclear plants, so that the level of the radioactivity in the effluents and the solid waste produced during the treatment of these liquid radwaste can be reduced. The work compares two types of ion exchange materials, a strong acid cation exchange resin, that is the material typically used to remove radionuclides from PWR nuclear plants wastes, and a mordenite zeolite. These exchange material were used to remove cesium from a synthetic effluent containing only this ion and another effluent containing cesium and cobalt. The breakthrough curves of the zeolite and resin using a fix bed reactor were compared. The results demonstrated that the zeolite is more efficient than the resin in removing cesium from a solution containing cesium and cobalt. The results also showed that a bed combining zeolite and resin can process more volume of an effluent containing cesium and cobalt than a bed resin alone. (author)

Thermochemically induced transformations in Al-smectites: A Spanish natural analogue of the bentonite barrier behaviour in a radwaste disposal

International Nuclear Information System (INIS)

Perez del Villar, L.; Delgado, A.; Reyes, E.; Pelayo, M.; Fernandez-Soler, J.M.; Cozar, J.S.; Tsige, M.; Quejido, A.J.

2005-01-01

The thermal effect induced by the Morron de Mateo volcanic dome (Cabo de Gata volcanic region, Spain) on the adjacent bentonitised tuffaceous beds has been studied as a natural analogue of the thermal behaviour of the bentonite-engineered barrier of a geological radwaste repository. These bentonites consist mainly of Fe-rich smectites and were formed in equilibrium with seawater at temperatures between 75 and 95 o C, according to the δ 18 O and δD values. In contrast, bentonites from other localities in the region consist mainly of Al-smectites, formed in equilibrium with meteoric water below 25 deg. C. This investigation is focussed on the detection of the chemical differences between smectites from proximal and distal zones to the dome, as well as to test whether the temperatures calculated based on the O and H isotopic values correspond to their formation or transformation. The initial hypothesis was that the chosen smectites could be formed under marine conditions, being later transformed and isotopically re-equilibrated as a result of the intrusion. To check this hypothesis, a detailed mineralogical, chemical, geochemical and isotopic study has been performed on the smectitised tuffaceous materials and the overlaying biocalcarenites outcropping near and far from the dome. The results show that distal smectites are dioctahedral Al-smectites, similar to those from other deposits in the region, while proximal smectites are Fe- and Mg-rich smectites, showing two evolutionary trends on a Fe-Mg-Al ternary diagram. Similar features are observed when their structural formulae are plotted on the muscovite-celadonite-pyrophylite diagram. Thus, they plot in the smectite domain with interlayer charge less than 1, which is mainly due to octahedral substitution for distal smectites, while for proximal ones it is caused by both octahedral and tetrahedral substitutions. In this ternary diagram, the domains of both proximal and distal smectites are partially overlapped. The

Synthesis and characterization of Sr2Ir1−xMxO4 (M=Ti, Fe, Co) solid solutions

International Nuclear Information System (INIS)

Gatimu, Alvin J.; Berthelot, Romain; Muir, Sean; Sleight, Arthur W.; Subramanian, M.A.

2012-01-01

The effects of Ti, Fe and Co substitutions for Ir on the structure and on the physical properties of Sr 2 IrO 4 are investigated. A complete solid solution Sr 2 Ir 1−x Ti x O 4 is obtained while both Fe and Co doping are relatively limited. In each case however, the c-axis cell parameter and the initial IrO 6 octahedra tilting decreases with substitution. Doping with Ti, Fe and Co results in a decrease of the magnetic susceptibility and in an increase in the paramagnetic effective moment for Co and Fe doped samples and a suppression of the weak ferromagnetic ordering observed for Sr 2 IrO 4 . - Graphical abstract: Solid solutions of Sr 2 Ir 1−x M x O 4 (M=Ti, Fe, Co) have been synthesized and characterized by powder X-ray diffraction, magnetism and electrical measurements. Changes in the a parameter and decreases in both the c-axis cell parameters and the initial IrO 6 octahedra tilting are found to be correlated. Highlights: ► Solid Solutions of Sr 2 Ir 1−x M x O 4 (M=Ti, Fe, Co) are synthesized. ► The Sr 2 Ir 1−x Ti x O 4 solid solution is complete while those of Fe and Co are relatively limited. ► The change in a cell parameter with substitution is much less than that of the c parameter. ► Decreased tilting and the smaller size of the M cation contrastingly affect the a parameter. ► Doping results in a suppression of the weak ferromagnetic ordering in Sr 2 IrO 4 .

Drug delivery properties of macroporous polystyrene solid foams.

Science.gov (United States)

Canal, Cristina; Aparicio, Rosa Maria; Vilchez, Alejandro; Esquena, Jordi; García-Celma, Maria José

2012-01-01

Polymeric porous foams have been evaluated as possible new pharmaceutical dosage forms. These materials were obtained by polymerization in the continuous phase of highly concentrated emulsions prepared by the phase inversion temperature method. Their porosity, specific surface and surface topography were characterized, and the incorporation and release of active principles was studied using ketoprofen as model lipophilic molecule. Solid foams with very high pore volume, mainly inside macropores, were obtained by this method. The pore morphology of the materials was characterized, and very rough topography was observed, which contributed to their nearly superhydrophobic properties. These solid foams could be used as delivery systems for active principles with pharmaceutical interest, and in the present work ketoprofen was used as a model lipophilic molecule. Drug incorporation and release was studied from solid foam disks, using different concentrations of the loading solutions, achieving a delayed release with short lag-time.

Site characterization data for Solid Waste Storage Area 6

International Nuclear Information System (INIS)

Boegly, W.J. Jr.

1984-12-01

Currently, the only operating shallow land burial site for low-level radioactive waste at the Oak Ridge National Laboratory (ORNL) is Solid Waste Storage Area No. 6 (SWSA-6). In 1984, the US Department of Energy (DOE) issued Order 5820.2, Radioactive Waste Management, which establishes policies and guidelines by which DOE manages its radioactive waste, waste by-products, and radioactively contaminated surplus facilities. The ORNL Operations Division has given high priority to characterization of SWSA-6 because of the need for continued operation under DOE 5820.2. The purpose of this report is to compile existing information on the geologic and hydrologic conditions in SWSA-6 for use in further studies related to assessing compliance with 5820.2. Burial operations in SWSA-6 began in 1969 on a limited scale, and full operation was initiated in 1973. Since that time, ca. 29,100 m 3 of low-level waste containing ca. 251,000 Ci of activity has been buried in SWSA-6. No transuranic waste has been disposed of in SWSA-6; rather this waste is retrievably stored in SWSA-5. Estimates of the remaining usable space in SWSA-6 vary; however, in 1982 sufficient useful land was reported for about 10 more years of operation. Analysis of the information available on SWSA-6 indicates that more information is required to evaluate the surface water hydrology, the geology at depths below the burial trenches, and the nature and extent of soils within the site. Also, a monitoring network will be required to allow detection of potential contaminant movement in groundwater. Although these are the most obvious needs, a number of specific measurements must be made to evaluate the spatial heterogeneity of the site and to provide background information for geohydrological modeling. Some indication of the nature of these measurements is included

Development and characterization of nifedipine-amino methacrylate copolymer solid dispersion powders with various adsorbents

Directory of Open Access Journals (Sweden)

Yotsanan Weerapol

2017-07-01

Full Text Available Solid dispersions of nifedipine (NDP, a poorly water-soluble drug, and amino methacrylate copolymer (AMCP with aid of adsorbent, that is, fumed silica, talcum, calcium carbonate, titanium dioxide, and mesoporous silica from rice husks (SRH, were prepared by solvent method. The physicochemical properties of solid dispersions, compared to their physical mixtures, were determined using powder X-ray diffractometry (PXRD and differential scanning calorimetry (DSC. The surface morphology of the prepared solid dispersions was examined by scanning electron microscopy (SEM. The dissolution of NDP from solid dispersions was compared to NDP powders. The effect of adsorbent type on NDP dissolution was also examined. The dissolution of NDP increased with the ratio of NDP:AMCP:adsorbent of 1:4:1 when compared to the other formulations. As indicated from PXRD patterns, DSC thermograms and SEM images, NDP was molecularly dispersed within polymer carrier or in an amorphous form, which confirmed the better dissolution of solid dispersions. Solid dispersions containing SRH provided the highest NDP dissolution, due to a porous nature of SRH, allowing dissolved drug to fill in the pores and consequently dissolve in the medium. The results suggested that solid dispersions containing adsorbents (SRH in particular demonstrated improved dissolution of poorly water-soluble drug when compared to NDP powder.

In situ evaluation of radwaste gamma activities

International Nuclear Information System (INIS)

Dulama, Cristian; Toma, Al.; Dobrin, R.; Pavelescu, Margarit

2003-01-01

There are certain limitations concerning the usage of standard source method for efficiency calibration of gamma-ray spectrometers measuring in extended geometry conditions. These limitations arise from the great diversity of forms and sizes of the objects which are to be measured during decommissioning and radioactive waste management activities. The INR - Pitesti operates a radioactive waste management facilities for both its own necessities and for providing external services. This facility is able to perform conditioning of liquid and solid wastes for interim storage disposal. During the conditioning operations there are certain stages when the radioactive measurement of the storage drums is demanded. We developed a gamma ray spectrometry equipment using a portable MCA Canberra INSPECTOR, a HPGe detector and an INR manufactured collimator. We are using a semiempirical method to calibrate the gamma ray spectrometer for such measurements. A program was written in Visual Basic language and includes a graphical interface for parameters input and data output. The input parameters are stored in text files, which can be loaded, modified or saved on disk as desired. The program was tested to establish the stability of MC simulation and the sensitivity to the input parameters. During the programming process it was possible to verify some code sequences and the results obtained showed that the model used was appropriate. To find out the optimal number of MC histories, which have to be modelled to obtain results of sufficient accuracy, the program was repeatedly run by changing only the number of histories. The relative deviation to the mean of the effective solid angle was calculated. The density of the source material as well as its composition can be changed by input. For comparison the efficiency calibration curves for sources materials having the same elemental composition but different densities ranging from 10 to 1000 kg/m 3 are drawn. The activities of the

CT Imaging Features in the Characterization of Non-Growing Solid Pulmonary Nodules in Non-Smokers

International Nuclear Information System (INIS)

Perandini, Simone; Soardi, Gian Alberto; Motton, Massimiliano; Augelli, Raffaele; Zantedeschi, Lisa; Montemezzi, Stefania

2016-01-01

A disappearing or persistent solid pulmonary nodule is a neglected clinical entity that still poses serious interpretative issues to date. Traditional knowledge deriving from previous reports suggests particular features, such as smooth edges or regular shape, to be significantly associated with benignity. A large number of benign nodules are reported among smokers in lung cancer screening programmes. The aim of this single-center retrospective study was to correlate specific imaging features to verify if traditional knowledge as well as more recent acquisitions regarding benign SPNs can be considered reliable in a current case series of nodules collected in a non-smoker cohort of patients. Fifty-three solid SPNs proven as non-growing during follow-up imaging were analyzed with regard to their imaging features at thin-section CT, their predicted malignancy risk according to three major risk assessment models, minimum density analysis and contrast enhanced-CT in the relative subgroups of nodules which underwent such tests. Eleven nodules disappeared during follow-up, 29 showed volume loss and 16 had a VDT of 1121 days or higher. There were 48 nodules located peripherally (85.71%). Evaluation of the enhancement after contrast media (n=29) showed mean enhancement ±SD of 25.72±35.03 HU, median of 18 HU, ranging from 0 to 190 HU. Minimum density assessment (n=30) showed mean minimum HU ±SD of −28.27±47.86 HU, median of −25 HU, ranging from −144 to 68 HU. Mean malignancy risk ±SD was 15.05±26.69% for the BIMC model, 17.22±19.00% for the Mayo Clinic model and 19.07±33.16% for the Gurney’s model. Our analysis suggests caution in using traditional knowledge when dealing with current small solid peripheral indeterminate SPNs and highlights how quantitative growth at follow-up should be the cornerstone of characterization

Physicochemical characterization of tacrolimus-loaded solid dispersion with sodium carboxylmethyl cellulose and sodium lauryl sulfate.

Science.gov (United States)

Park, Young-Joon; Ryu, Dong-Sung; Li, Dong Xun; Quan, Qi Zhe; Oh, Dong Hoon; Kim, Jong Oh; Seo, Youn Gee; Lee, Young-Im; Yong, Chul Soon; Woo, Jong Soo; Choi, Han-Gon

2009-06-01

To develop a novel tacrolimus-loaded solid dispersion with improved solubility, various solid dispersions were prepared with various ratios of water, sodium lauryl sulfate, citric acid and carboxylmethylcellulose-Na using spray drying technique. The physicochemical properties of solid dispersions were investigated using scanning electron microscopy, differential scanning calorimetery and powder X-ray diffraction. Furthermore, their solubility and dissolution were evaluated compared to drug powder. The solid dispersion at the tacrolimus/CMC-Na/sodium lauryl sulfate/citric acid ratio of 3/24/3/0.2 significantly improved the drug solubility and dissolution compared to powder. The scanning electron microscopy result suggested that carriers might be attached to the surface of drug in this solid dispersion. Unlike traditional solid dispersion systems, the crystal form of drug in this solid dispersion could not be converted to amorphous form, which was confirmed by the analysis of DSC and powder X-ray diffraction. Thus, the solid dispersion system with water, sodium lauryl sulfate, citric acid and CMC-Na should be a potential candidate for delivering a poorly water-soluble tacrolimus with enhanced solubility and no convertible crystalline.

The Stabilization of Amorphous Zopiclone in an Amorphous Solid Dispersion.

Science.gov (United States)

Milne, Marnus; Liebenberg, Wilna; Aucamp, Marique

2015-10-01

Zopiclone is a poorly soluble psychotherapeutic agent. The aim of this study was to prepare and characterize an amorphous form of zopiclone as well as the characterization and performance of a stable amorphous solid dispersion. The amorphous form was prepared by the well-known method of quench-cooling of the melt. The solid dispersion was prepared by a solvent evaporation method of zopiclone, polyvinylpyrrolidone-25 (PVP-25), and methanol, followed by freeze-drying. The physico-chemical properties and stability of amorphous zopiclone and the solid dispersion was studied using differential scanning calorimetry (DSC), infrared spectroscopy (FT-IR), thermogravimetric analysis (TGA), scanning electron microscopy (SEM), hot-stage microscopy (HSM), X-ray diffractometry (XRD), solubility, and dissolution studies. The zopiclone amorphous solid-state form was determined to be a fragile glass; it was concluded that the stability of the amorphous form is influenced by both temperature and water. Exposure of amorphous zopiclone to moisture results in rapid transformation of the amorphous form to the crystalline dihydrated form. In comparison, the amorphous solid dispersion proved to be more stable with increased aqueous solubility.

Solid pseudopapillary pancreas tumors. Often neglected

International Nuclear Information System (INIS)

Herrmann, K.A.; Reiser, M.F.; Zech, C.J.; Helmberger, T.; Bruns, C.

2008-01-01

Solid pseudopapillary tumors of the pancreas (SPTP) are rare tumors of the pancreas with low malignancy potential and a very good prognostic outcome after surgery. They typically occur in young women or adolescents and consist of solid, cystic and cystic-hemorrhagic components. Imaging findings in these tumors are characteristic and include a fibrotic capsule with a clear delineation and exhibit solid and cystic-hemorrhagic signal and density characteristics. Calcifications may be present in the periphery of the tumor. The tumor capsule shows contrast enhancement, the solid components in the periphery enhance in the early phase and gradually and inhomogeneously in late phases. MRI is superior to CT and other imaging modalities for characterization of SPTP. Awareness and knowledge of this tumor entity with an excellent prognosis is crucial to guide the patient towards effective, predominantly organ-sparing surgical treatment. (orig.) [de

Preparation and characterization of solid lipid nanoparticles containing cyclosporine by the emulsification-diffusion method

Directory of Open Access Journals (Sweden)

Zaida Urbán-Morlán

2010-08-01

Full Text Available Zaida Urbán-Morlán1, Adriana Ganem-Rondero1, Luz María Melgoza-Contreras2, José Juan Escobar-Chávez1,2, María Guadalupe Nava-Arzaluz1, David Quintanar-Guerrero11División de Estudios de Posgrado (Tecnología Farmacéutica, Facultad de Estudios Superiores Cuautitlán-Universidad Nacional Autónoma de México, Estado de México, México; 2Departamento de Sistemas Biológicos, Universidad Autónoma Metropolitana-Xochimilco, Calzada del Hueso, Colonia Villa Quietud, MéxicoAbstract: Solid lipid nanoparticles (SLNs have been used for carrying different therapeutic agents because they improve absorption and bioavailability. The aim of the study was to prepare lipidic nanoparticles containing cyclosporine (CyA by the emulsification-diffusion method and to study their physicochemical stability. Glyceryl behenate (Compritol® ATO 888 and lauroyl macrogolglycerides (Gelucire® 44/14 were used as carrier materials. Nanoparticles with good stability were obtained with Gelucire®, while it was difficult to obtain stable systems with Compritol®. Systems with Gelucire® were characterized by particle size, Z-potential, differential scanning calorimetry (DSC, scanning electron microscopy (SEM, entrapment efficiency and in vitro release. Particle size and Z-potential were evaluated for at least three months. With a high CyA content (≥60 mg in Gelucire® SLNs, variations in size were greater and particle size also increased over time in all batches; this effect may have been caused by a probable expulsion of the drug due to the lipid’s partial rearrangement. While the Z-potential decreased 10 mV after three months, this effect may be explained by the superficial properties of the drug that make the molecules to be preferably oriented at the solid-liquid interface, causing a change in the net charge of the particle. SEM confirmed size and shape of the nanoparticles. DSC studies evidenced that CyA affects the lipid structure by a mechanism still unknown

Preparation and evaluation of carvedilol-loaded solid lipid ...

African Journals Online (AJOL)

The SLNs were characterized in terms of entrapment efficiency, particle size, zeta potential, polydispersity index, cytotoxicity, solid state characterization and drug release. The stability of the formulations was investigated by monitoring their properties for a period of 3 months. Results: The mean size of the nanoparticles was ...

Characterization of solids deposited on the modular caustic-side solvent extraction unit (MCU) coalescer media removed in May and October 2014

Energy Technology Data Exchange (ETDEWEB)

Fondeur, F. F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-10-01

During routine maintenance, the coalescers utilized in the Modular Caustic-Side Solvent Extraction Unit (MCU) processing of Salt Batch 6 and a portion of Salt Batch 7 were sampled and submitted to the Savannah River National Laboratory (SRNL) for characterization, for the purpose of identifying solid phase constituents that may be accumulating in these coalescers. Specifically, two samples were received and characterized: A decontaminated salt solution (DSS) coalescer sample and a strip effluent (SE) coalescer sample. Aliquots of the samples were analyzed by XRD, Fourier Transform Infrared (FTIR) Spectroscopy, SEM, and EDS. Other aliquots of the samples were leached in acid solution, and the leachates were analyzed by ICP-AES. In addition, modeling was performed to provide a basis for comparison of the analytical results.

Integrated software system for low level waste management

International Nuclear Information System (INIS)

Worku, G.

1995-01-01

In the continually changing and uncertain world of low level waste management, many generators in the US are faced with the prospect of having to store their waste on site for the indefinite future. This consequently increases the set of tasks performed by the generators in the areas of packaging, characterizing, classifying, screening (if a set of acceptance criteria applies), and managing the inventory for the duration of onsite storage. When disposal sites become available, it is expected that the work will require re-evaluating the waste packages, including possible re-processing, re-packaging, or re-classifying in preparation for shipment for disposal under the regulatory requirements of the time. In this day and age, when there is wide use of computers and computer literacy is at high levels, an important waste management tool would be an integrated software system that aids waste management personnel in conducting these tasks quickly and accurately. It has become evident that such an integrated radwaste management software system offers great benefits to radwaste generators both in the US and other countries. This paper discusses one such approach to integrated radwaste management utilizing some globally accepted radiological assessment software applications

Synthesis, characterization and thermal expansion studies on thorium-praseodymium mixed oxide solid solutions

International Nuclear Information System (INIS)

Panneerselvam, G.; Antony, M.P.; Srinivasan, T.G.; Vasudeva Rao, P.R.

2010-01-01

Full text: Thorium-praseodymium mixed oxide solid solutions containing 15, 25, 40 and 55 mole percent of praseodymia were synthesized by mixing the solutions of thorium nitrate in water and praseodymium oxide (Pr 6 O 11 ) in conc. HNO 3 . Subsequently, their hydroxides were co-precipitated by the addition of aqueous ammonia. Further the precipitate was dried at 50 deg C, calcined at 600 deg C for 4 hours and sintered at 1200 deg C for 6 h in air. X-ray diffraction measurements were performed for phase identification and lattice parameter derivation. Single-phase fluorite structure was observed for all the compositions. Bulk and theoretical densities of solid solutions were also determined by immersion and X-ray techniques. Thermal expansion coefficients and percentage linear thermal expansion of the solid solutions were determined using high temperature X-ray diffraction technique in the temperature range 300 to 1700 K for the first time. The room temperature lattice constants estimated for above compositions are 0.5578, 0.5565, 0.5545 and 0.5526 nm, respectively. The mean linear thermal expansion coefficients for the solid solutions are 15.48 x 10 -6 K -1 , 18.35 x 10 -6 K -1 , 22.65 x 10 -6 K -1 and 26.95 x 10 -6 K -1 , respectively. The percentage linear thermal expansions in this temperature range are 1.68, 1.89, 2.21 and 2.51 respectively. It is seen that the solid solutions are stable up to 1700 K. It is also seen that the effect and nature of the dopant are the important parameters influencing the thermal expansion of the ThO 2 . The lattice parameter of the solid solutions exhibited a decreasing trend with respect to praseodymia addition. The percentage linear thermal expansion of the solid solutions increases steadily with increasing temperature

Ultrafiltration and Characterization of AW-101 Supernatant and Entrained Solids

International Nuclear Information System (INIS)

Brooks, K.P.; Bredt, P.R.; Golcar, G.R.; Hartley, S.A.; Urie, M.W.; Tingey, J.M.; Rappe, K.G.; Jagoda, L.K.

1999-01-01

The River Protection Project Waste Treatment Plant (RPP-WTP) (1996) flow sheet uses cross-flow filtration as the solid/liquid separation technique. Unlike traditional dead-end filtration, which has a declining rate caused by the growth of a filter cake on the surface of the filter medium, in cross-flow filtration, the filter cake is swept away by the fluid flowing across it. This filtration method is especially beneficial when there are very fine particles and when system simplicity is required. The objective of this work was to test cross-flow filtration using actual Envelope A Hanford tank waste. Similar to the Phase 1A study, they evaluated the permeability of an Envelope A feed through a single element filter as a function of transmembrane pressure, axial velocity, solids concentration, and time. In addition, the efficiency of back pulse and chemical cleaning on the filter performance was evaluated. The chemical and radiochemical composition of the filtrate and solids was measured to determine efficiency of the filtration process. This report describes the test apparatus, the experimental approach, the results of the tests, and the chemical and radiochemical analysis for supernatants taken from Hanford Tank AW-101. This report also provides a means of transmitting to British Nuclear Fuels, Limited (BNFL) the completed test instruction and raw filtration and analytical data

Molten metal technologies advance waste processing systems for liquid radioactive waste treatment for PWRs and BWRs

International Nuclear Information System (INIS)

Strand, Gary; Vance, Jene N.

1997-01-01

Molten Metal Technologies (MMT) has recently acquired a proprietary filtration process for specific use in radioactive liquid waste processing systems. The filtration system has been incorporated in to a PWR liquid radwaste system which is currently being designed for the ComEd Byron Nuclear Station. It has also been adopted as the prefiltration step up from of the two RO systems which were part of the VECTRA acquisition and which are currently installed in the ComEd Dresden and Lacily Nuclear Stations. The filtration process has been successfully pilot-tested at both Byron and Dresden and is currently being tested at LaSalle. The important features of the filtration process are the high removal efficiencies for particulates, including colloidal particles, and the low solid waste volume generation per gallon filtered which translates into very small annual solid waste volumes. This filtration process system has been coupled with the use of selective ion exchange media in the PWR processing system to reduce the solid waste volumes generated compared to the current processing methods and to reduce the curie quantities discharged to the environs. In the BWR processing system, this filtration method allows the coupling of an RO system to provide for recycling greater than 95% of the liquid radwaste back to the plant for reuse while significantly reducing the solid waste volumes and operating costs. This paper discusses the process system configurations for the MMT Advanced Waste Processing Systems for both PWRs and BWRs. In addition, the pilot test data and full-scale performance projections for the filtration system are discussed which demonstrate the important features of the filtration process

Assessment of LANL solid low-level mixed waste documentation

International Nuclear Information System (INIS)

Jennrich, E.A.; Lund, D.M.; Davis, K.D.; Hoevemeyer, S.S.

1991-04-01

DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section and the Chemical Waste Operations Section capabilities regarding preparation and maintenance of appropriate criteria, plans, and procedures. Additionally, a comparison is made which identifies areas where these documents are not presently in existence or being fully implemented. The documents being assessed in this report are: Solid Low-Level Mixed Waste Acceptance Criteria, Solid Low-Level Mixed Waste Characterization Plan, Solid Low-Level Mixed waste Certification Plan, Solid Low-Level Mixed Waste Acceptance Procedures, Solid Low-Level Mixed Waste characterization Procedures, Solid Low-Level Mixed Waste Certification Procedures, Solid Low-Level Mixed Waste Training Procedures, and Solid Low-Level Mixed Waste Recordkeeping Requirements. This report compares the current status of preparation and implementation, by the Radioactive Waste Operations Section and the Chemical Waste Operations Section, of these documents to the requirements of DOE 5820.2A,. 40 CFR 260 to 270, and to recommended practice. Chapters 2 through 9 of the report presents the results of the comparison in tabular form for each of the documents being assessed, followed by narrative discussion of all areas which are perceived to be unsatisfactory or out of compliance with respect to the availability and content of the documents. The final subpart of each of the following chapters provides recommendations where documentation practices may be improved to achieve compliance or to follow the recommended practice

Composition of municipal solid waste in Denmark

DEFF Research Database (Denmark)

Edjabou, Vincent Maklawe Essonanawe; Petersen, Claus; Scheutz, Charlotte

2014-01-01

Data for the composition of municipal solid waste is a critical basis for any assessment of waste technologies and waste management systems. The detailed quantification of waste fractions is absolutely needed for a better technological development of waste treatment. The current waste composition...... comparability to characterize municipal solid waste. This methodology was applied to residual waste collected from 1,442 households in three municipalities in Denmark. The main fractions contributing to the residual household waste were food waste and miscellaneous waste. Statistical analysis suggested...... of standardised and commonly accepted waste characterization methodologies, various approaches have been reported in literature. This limits both comparability and applicability of the results. The purpose of this study was to introduce a consistent methodology that reduces uncertainties and ensures data...

Characterization during storage and dissolution of Solid dispersions containing furosemide and hydroxypropyl methylcellulose

DEFF Research Database (Denmark)

Nielsen, Line Hagner; Rades, T.; Müllertz, A.

2013-01-01

Solid dispersions containing furosemide and various amounts of hydroxypropyl methylcellulose (HPMC) were prepared by spray drying to investigate if the physical stability of amorphous furosemide during storage and dissolution could be improved by formulating the drug as a solid dispersion. All...

Characterization of past and present solid waste streams from the Plutonium-Uranium Extraction Plant

International Nuclear Information System (INIS)

Pottmeyer, J.A.; Weyns, M.I.; Lorenzo, D.S.; Vejvoda, E.J.; Duncan, D.R.

1993-04-01

During the next two decades the transuranic wastes, now stored in the burial trenches and storage facilities at the Hanford Site, are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Over 7% of the transuranic waste to be retrieved for shipment to the Waste Isolation Pilot Plant has been generated at the Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this report is to characterize the radioactive solid wastes generated by PUREX using process knowledge, existing records, and oral history interviews. The PUREX Plant is currently operated by the Westinghouse Hanford Company for the US Department of Energy and is now in standby status while being prepared for permanent shutdown. The PUREX Plant is a collection of facilities that has been used primarily to separate plutonium for nuclear weapons from spent fuel that had been irradiated in the Hanford Site's defense reactors. Originally designed to reprocess aluminum-clad uranium fuel, the plant was modified to reprocess zirconium alloy clad fuel elements from the Hanford Site's N Reactor. PUREX has provided plutonium for research reactor development, safety programs, and defense. In addition, the PUREX was used to recover slightly enriched uranium for recycling into fuel for use in reactors that generate electricity and plutonium. Section 2.0 provides further details of the PUREX's physical plant and its operations. The PUREX Plant functions that generate solid waste are as follows: processing operations, laboratory analyses and supporting activities. The types and estimated quantities of waste resulting from these activities are discussed in detail

Long term thermo-hydro-mechanical interaction behavior study of the saturated, discontinuous granitic rock mass around the radwaste repository using a steady state flow algorithm

Energy Technology Data Exchange (ETDEWEB)

Kim, Jhin Wung; Bae, Dae Suk; Kang, Chul Hyung; Choi, Jong Won [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-02-01

The objective of the present study is to understand the long term (500 years) thermo-hydro-mechanical interaction behavior of the 500 m depth underground radwaste repository in the saturated, discontinuous granitic rock mass using a steady state flow algorithm. The numerical model includes a saturated granitic rock mass with joints around the repository and a 45 .deg. C fault passing through the tunnel roof-wall intersection, and a canister with PWR spent fuels surrounded by the compacted bentonite and mixed-bentonite. Barton-Bandis joint constitutive model from the UDEC code is used for the joints. For the hydraulic analysis, a steady state flow algorithm is used for the groundwater flow through the rock joints. For the thermal analysis, heat transfer is modeled as isotropic conduction and heat decays exponentially with time. The results show that the variations of the hydraulic aperture, hydraulic conductivity, normal stress, normal displacements, and shear displacements of the joints are high in the vicinity of the repository and stay fairly constant on the region away from the repository. 14 refs., 15 figs., 11 tabs. (Author)

Characterization and evaluation of sensory acceptability of ice creams incorporated with beta-carotene encapsulated in solid lipid microparticles

Directory of Open Access Journals (Sweden)

Juliana Gobbi de LIMA

Full Text Available Abstract The feasibility of incorporating beta-carotene-loaded solid lipid microparticles (BCSLM into vanilla ice creams was investigated, through the physico-chemical characterization and evaluation of sensory acceptability of the products products. The BCSLM were produced with palm stearin as the lipid phase, hydrolyzed soy protein isolate as the surfactant, and xanthan gum as the thickener. The results showed similar values of proximate composition, total soluble solids, pH, and overrun for all formulations. On the other hand, colorimetric evaluations showed that the ice cream produced with partial substitution of artificial additives by BCSLM containing alpha-tocopherol presented a more intense color, while in the product with non-encapsulated beta-carotene, a fast degradation of carotenoid was confirmed, highlighting the importance of the encapsulation techniques. The results of the sensorial analysis of the products were highly satisfactory and showed that the panelists preferred the ice creams produced with BCSLM containing alpha-tocopherol and with partial substitution of artificial additives by BCSLM containing alpha-tocopherol, confirming the feasibility of incorporating BCSLM into ice creams to reduce the application of artificial dyes to the product.

Characterization of solid wastes from kraft pulp industry for ceramic materials development purposes; Caracterizacao de residuos solidos da industria de celulose tipo kraft visando sua aplicacao no desenvolvimento de materiais ceramicos

Energy Technology Data Exchange (ETDEWEB)

Rodrigues, L.R.; Francisco, M.A.C.O.; Sagrillo, V.P.D.; Louzada, D.M.; Entringer, J.M.S. [Instituto Federal do Espirito Santo (IFES), Vitoria, ES (Brazil)

2016-07-01

The Kraft pulp industry generates a large amount of solid wastes. Due this large quantity, the target of this study is characterize inorganic solid wastes, dregs, grits and lime mud, from the step of reagents recovery of Kraft process, aiming evaluate the potentiality of their use as alternative raw material on development of ceramic materials. Initially, the wastes were dried and ground, then they were subjected to the following characterization techniques: pH analysis, particle size analysis, X ray fluorescence, X ray diffraction, differential thermal analysis and thermogravimetric analysis and scanning electron microscopy. According to the results, it may be concluded that these wastes could be used as raw material in production of red ceramic and luting materials. (author)

Development of orodispersible polymer films with focus on the solid state characterization of crystalline loperamide.

Science.gov (United States)

Woertz, Christina; Kleinebudde, Peter

2015-08-01

The formulation of active pharmaceutical ingredients (API) as orodispersible films is gaining interest among novel oral drug delivery systems due to their small size, enhanced flexibility and improved patient compliance. The aim of this work was the preparation and characterization of orodispersible films containing loperamide hydrochloride (LPH) as model drug. As loperamide hydrochloride is poorly soluble in water it was used in crystalline form with a loading of 2mg/6cm(2) film. Hydroxypropyl methylcellulose (HPMC) and different types of hydroxypropyl cellulose (HPC) in different concentrations were used as film forming polymers whereas arabic gum, xanthan gum and tragacanth served as thickening agents. Films were characterized with respect to the content uniformity, morphology, thermal behavior and crystallinity. Suspensions were investigated regarding their viscosity using a rotational rheometer and the crystal structure of the Active Pharmaceutical Ingredient (API) was analyzed using polarized light microscopy. The development of flexible, non-brittle and homogeneous films of LPH was feasible. Two polymorphic forms of LPH appeared in the film formulations dependent on the utilized polymer. While in presence of HPMC the original polymorphic form I remained stable in suspension and films, the polymorphic form II occurred in presence of HPC. Both polymorphic forms were prepared separately and a solid state characterization was performed. Polymorph I showed isometric crystals whereas polymorph II showed needle shaped crystals. Tragacanth was able to prevent the transformation to polymorph II, if it was dissolved first before HPC. When HPC was added first to the suspension, the conversion to form II occurred irreversibly also after further addition of tragacanth. Copyright © 2015 Elsevier B.V. All rights reserved.

Sintered Cathodes for All-Solid-State Structural Lithium-Ion Batteries

Science.gov (United States)

Huddleston, William; Dynys, Frederick; Sehirlioglu, Alp

2017-01-01

All-solid-state structural lithium ion batteries serve as both structural load-bearing components and as electrical energy storage devices to achieve system level weight savings in aerospace and other transportation applications. This multifunctional design goal is critical for the realization of next generation hybrid or all-electric propulsion systems. Additionally, transitioning to solid state technology improves upon battery safety from previous volatile architectures. This research established baseline solid state processing conditions and performance benchmarks for intercalation-type layered oxide materials for multifunctional application. Under consideration were lithium cobalt oxide and lithium nickel manganese cobalt oxide. Pertinent characteristics such as electrical conductivity, strength, chemical stability, and microstructure were characterized for future application in all-solid-state structural battery cathodes. The study includes characterization by XRD, ICP, SEM, ring-on-ring mechanical testing, and electrical impedance spectroscopy to elucidate optimal processing parameters, material characteristics, and multifunctional performance benchmarks. These findings provide initial conditions for implementing existing cathode materials in load bearing applications.

Characterization of solid UV cross-linked PEGDA for biological applications

KAUST Repository

Castro, David; Ingram, Patrick; Kodzius, Rimantas; Conchouso Gonzalez, David; Yoon, Euisik; Foulds, Ian G.

2013-01-01

This paper reports on solid UV cross-linked Poly(ethylene)-glycol-diacrylate (PEGDA) as a material for microfluidic devices for biological applications. We have evaluated biocompatibility of PEGDA through two separate means: 1) by examining cell

???????????? SolidWorks/SolidWorks Flow Simulation/SolidWorks Simulation ??? ?????????? ???????? ?? ????????????? ???

OpenAIRE

????????????, ?. ?.; ????????, ?. ?.; ?????, ?. ?.

2012-01-01

? ?????? ???????? ??????? ??????? ???????? ?? ???????????? ??????????? ????????? SolidWorks/SolidWorks Flow Simulation (COSMOSFloWorks)/SolidWorks Simulation ??? ?????????? ???????? ?? ????????????? ???. ??? ???????? ????????? ???????? ?????????? ?? ?????? ???????? ??????? ? ????????????? ?????? ? ????????????? ????????????? ?????????? ???????????? SolidWorks Flow Simulation (COSMOSFloWorks). ??? ???????????? ??????????? ????????????? ?????? ?? ????????? ??????????? ??????? ?? ??????????? ...

Low-level waste volume reduction--physicochemical systems

International Nuclear Information System (INIS)

Ferrigno, D.P.

1980-01-01

In some cases, volume reduction (VR) equipment may be called upon to reduce noncombustible liquid wastes to essentially dry salts and/or oxides. In other cases, it may be called upon to reduce combustible solids and liquids to ashes and innocuous gases. In brand terms, four kinds of processes are available to further reduce the volume of waste generated at nuclear facilities. These include high-solids evaporation, alternative evaporative designs, extruders/mixers, and calciner/incinerators. This paper discusses the following VR processes for radioactive wastes at nuclear facilities: evaporator/crystallizer; fluid bed dryer/incinerator; fluid bed calciner/incinerator; inert carrier radwaste processor; and molten glass incinerator

Waste Characterization: Approaches and Methods

DEFF Research Database (Denmark)

Lagerkvist, A.; Ecke, H.; Christensen, Thomas Højlund

2011-01-01

Characterization of solid waste is usually a difficult task because of the heterogeneity of the waste and its spatial as well as temporal variations. This makes waste characterization costly if good and reliable data with reasonable uncertainty is to be obtained. Therefore, a waste characterization...... is often narrowly defined to meet specific needs for information. This may however limit the general usefulness of the information gained, for example, if the specific purpose limited the characterization to a subset of variables. In general, data available in the solid waste area are limited and often...... related to individual treatment processes and waste products are dealt with in the following chapters: Characteristic data on residential waste (Chapter 2.2), commercial and institutional waste (Chapter 2.3), industrial waste (Chapter 2.4) and construction and demolition waste (Chapter 2...

Synthesis and Characterization of Tin (IV Tungstate Nanoparticles – A Solid Acid Catalyst

Directory of Open Access Journals (Sweden)

Manoj Sadanandan

2012-12-01

Full Text Available Tin (IV tungstate, a tetravalent metal acid salt was synthesized in the nanoform by chemical coprecipitation method using EDTA as capping agent. The material was found to be stable in mineral acids, bases and organic solvents except  in HF and aquaregia. The material was characterized using EDS, TG/DTA, FTIR, XRD, SEM, HRTEM and BET surface area measurement. The molecular formula of the compound is 2SnO2 3WO3.5H2O determined from elemental analysis using TG/DTA. Surface morphology and particle size were obtained using SEM and HRTEM. The surface area was found to be 205-225m2/g. The Na+ exchange capacity found to be 3.8 meq/g, indicates the presence of surface hydroxyl group and hence the presence of Bronsted acid sites. The catalytic activity of the material was tested by using esterification and oxidation as model reactions. For the esterification of different alcohols, the percentage yield was found to be high for n-alcohol compared to isomeric alcohols. Oxidation of benzyl alcohol gives benzaldehyde and benzoic acid as the only products. Copyright © 2012 by BCREC UNDIP. All rights reservedReceived: 12nd June 2012, Revised: 23rd July 2012, Accepted: 29th July 2012[How to Cite: S. Manoj, R. Beena, (2012. Synthesis and Characterization of tin(IV Tungstate Nanoparticles – A Solid Acid Catalyst. Bulletin of Chemical Reaction Engineering & Catalysis, 7 (2: 105-111. doi:10.9767/bcrec.7.2.3622.105-111] [How to Link / DOI: http://dx.doi.org/10.9767/bcrec.7.2.3622.105-111 ] | View in 

Characterization and migration of oil and solids in oily sludge during centrifugation.

Science.gov (United States)

Wang, Jun; Han, Xu; Huang, Qunxing; Ma, Zengyi; Chi, Yong; Yan, Jianhua

2018-05-01

The migration behaviors of oil, water and solids in sludge during centrifugation were elaborated. Size distribution, surface topography and lypohydrophilic properties were studied in detail. The average size of solids was 61 μm in original sludge, 31 μm in upper layer and 235 μm in bottom layer. The result shows that solvent is essential to separate oil phase into molecular light and weight fractions during centrifugation. With solvent/oil ratio increases from 1:2, 1:1, 2:1 to 5:1, molecular weight in upper layer decreases from 1044, 1043, 1020 to 846 combined with that in bottom layer increases. A model was proposed to calculate the oil residue content in solid phases after sedimentation. The findings of this paper provide information for optimizing the oil recovery and clean treatment.

Combinational approach using solid dispersion and semi-solid matrix technology to enhance in vitro dissolution of telmisartan

Directory of Open Access Journals (Sweden)

Syed Faisal Ali

2016-02-01

Full Text Available The present investigation was focused to formulate semi-solid capsules (SSCs of hydrophobic drug telmisartan (TLMS by encapsulating semi-solid matrix of its solid dispersion (SD in HPMC capsules. The combinational approach was used to reduce the lag time in drug release and improvise its dissolution. SDs of TLMS was prepared using hot fusion method by varying the combinations of Pluronic-F68, Gelucire 50/13 and Plasdone S630. A total of nine batches (SD1-SD9 were characterized for micromeritic properties, in vitro dissolution behavior and surface characterization. SD4 with 52.43% cumulative drug release (CDR in phosphate buffer, pH 7.4, in 120 min, t50% 44.2 min and DE30min 96.76% was selected for the development of semi-solid capsules. Differential scanning calorimetry of SD4 revealed molecular dispersion of TLMS in Pluronic-F68. SD4 was formulated into SSCs using Gelucire 44/14 and PEG 400 as semi-solid components and PEG 6000 as a suspending agent to achieve reduction in lag time for effective drug dissolution. SSC6 showed maximum in vitro drug dissolution 97.49 % in phosphate buffer, pH 7.4 with in 20 min that was almost a three folds reduction in the time required to achieve similar dissolution by SD. Thus, SSCs present an excellent approach to enhance in vitro dissolution as well as to reduce the lag time of dissolution for poorly water soluble drugs especially to those therapeutic classes that are intended for faster onset of action. Developed approach based on HPMC capsules provided a better alternative to target delivery of telmisartan to the vegetarian population.

Treatment of spent ion exchange resins IAEA research coordination programme

International Nuclear Information System (INIS)

Balu, K.; Bhatia, S.C.; Wattal, P.K.; Chanana, N.

1981-09-01

Spent ion-exchange resins arising from steam condensate systems, reactor coolant clean-up systems and rad-waste procession, are considered as a specific solid waste management problem. This is the second report on the product characterisation with respect to thermal properties, flammability, bio-organic degradation and leaching behaviours. All these studies are based on polyester-styrene polymer as a matrix for fixation of these spent Ix-resins. Choice of this matrix was dealt with in the first report. (author)

Thermotransport in interstitial solid solutions

International Nuclear Information System (INIS)

Fogel'son, R.L.

1982-01-01

On the basis of literature data the problem of thermotransport of impurities (H, N, O, C) in interstitial solid solutions is considered. It is shown that from experimental data on the thermotransport an important parameter of dissolved atoms can be found which characterizes atom state in these solutions-enthalpy of transport

Atomistic Modeling of the Fluid-Solid Interface in Simple Fluids

Science.gov (United States)

Hadjiconstantinou, Nicolas; Wang, Gerald

2017-11-01

Fluids can exhibit pronounced structuring effects near a solid boundary, typically manifested in a layered structure that has been extensively shown to directly affect transport across the interface. We present and discuss several results from molecular-mechanical modeling and molecular-dynamics (MD) simulations aimed at characterizing the structure of the first fluid layer directly adjacent to the solid. We identify a new dimensionless group - termed the Wall number - which characterizes the degree of fluid layering, by comparing the competing effects of wall-fluid interaction and thermal energy. We find that in the layering regime, several key features of the first layer layer - including its distance from the solid, its width, and its areal density - can be described using mean-field-energy arguments, as well as asymptotic analysis of the Nernst-Planck equation. For dense fluids, the areal density and the width of the first layer can be related to the bulk fluid density using a simple scaling relation. MD simulations show that these results are broadly applicable and robust to the presence of a second confining solid boundary, different choices of wall structure and thermalization, strengths of fluid-solid interaction, and wall geometries.

Solid State NMR Characterization of Complex Metal Hydrides systems for Hydrogen Storage Applications

Directory of Open Access Journals (Sweden)

Son-Jong Hwang

2011-12-01

Full Text Available Solid state NMR is widely applied in studies of solid state chemistries for hydrogen storage reactions. Use of 11B MAS NMR in studies of metal borohydrides (BH4 is mainly focused, revisiting the issue of dodecaborane formation and observation of 11B{1H} Nuclear Overhauser Effect.

Physical-Chemical Characterization of Solid Waste Generated in the Water Industry: Case Study of the Water Treatment Stations of the Metropolitan Region of Recife

Directory of Open Access Journals (Sweden)

Rosângela Gomes Tavares

2017-12-01

Full Text Available The objective of this research is to characterize the solid waste, commonly known as sludge, from the water treatment industry. Six main water treatment plants (Alto do Céu, Botafogo, Caixa d'água, Gurjaú, Suape and Tapacurá were selected from the Metropolitan Region of Recife, managed by Companhia Pernambucana de Saneamento. Nine samples were collected in the eleven month period in the discharge of the sludge from the decanters. These samples were characterized physico-chemically, based on the methodology of the Standard Methods for the Examination of Water and Wastewater (2012. The results indicated average humidity of 93%, average COD around 30 g/L and BOD of 4.5 g/L, indicating sludge of low biodegradability. The average values of total solids were 72 g/L, with 75% corresponding to fixed residues and 25% to volatiles. High concentrations of aluminum (1000 mg/L were observed, due to the use of aluminum sulphate as a coagulant, and iron, around 500 mg/L. This study assists the manager in the decision making of the sustainable management of the sludge, mainly in relation to the final disposal.

Solid-state NMR basic principles and practice

CERN Document Server

Apperley, David C; Hodgkinson, Paul

2014-01-01

Nuclear Magnetic Resonance (NMR) has proved to be a uniquely powerful and versatile tool for analyzing and characterizing chemicals and materials of all kinds. This book focuses on the latest developments and applications for "solid-state" NMR, which has found new uses from archaeology to crystallography to biomaterials and pharmaceutical science research. The book will provide materials engineers, analytical chemists, and physicists, in and out of lab, a survey of the techniques and the essential tools of solid-state NMR, together with a practical guide on applications. In this concise introduction to the growing field of solid-state nuclear magnetic resonance spectroscopy The reader will find: * Basic NMR concepts for solids, including guidance on the spin-1/2 nuclei concept * Coverage of the quantum mechanics aspects of solid state NMR and an introduction to the concept of quadrupolar nuclei * An understanding relaxation, exchange and quantitation in NMR * An analysis and interpretation of NMR data, with e...

Comparison of conventional and automated breast volume ultrasound in the description and characterization of solid breast masses based on BI-RADS features.

Science.gov (United States)

Kim, Hyunji; Cha, Joo Hee; Oh, Ha-Yeun; Kim, Hak Hee; Shin, Hee Jung; Chae, Eun Young

2014-07-01

To compare the performance of radiologists in the use of conventional ultrasound (US) and automated breast volume ultrasound (ABVU) for the characterization of benign and malignant solid breast masses based on breast imaging and reporting data system (BI-RADS) criteria. Conventional US and ABVU images were obtained in 87 patients with 106 solid breast masses (52 cancers, 54 benign lesions). Three experienced radiologists who were blinded to all examination results independently characterized the lesions and reported a BI-RADS assessment category and a level of suspicion of malignancy. The results were analyzed by calculation of Cohen's κ coefficient and by receiver operating characteristic (ROC) analysis. Assessment of the agreement of conventional US and ABVU indicated that the posterior echo feature was the most discordant feature of seven features (κ = 0.371 ± 0.225) and that orientation had the greatest agreement (κ = 0.608 ± 0.210). The final assessment showed substantial agreement (κ = 0.773 ± 0.104). The areas under the ROC curves (Az) for conventional US and ABVU were not statistically significant for each reader, but the mean Az values of conventional US and ABVU by multi-reader multi-case analysis were significantly different (conventional US 0.991, ABVU 0.963; 95 % CI -0.0471 to -0.0097). The means for sensitivity, specificity, positive predictive value, and negative predictive value of conventional US and ABVU did not differ significantly. There was substantial inter-observer agreement in the final assessment of solid breast masses by conventional US and ABVU. ROC analysis comparing the performance of conventional US and ABVU indicated a marginally significant difference in mean Az, but not in mean sensitivity, specificity, positive predictive value, or negative predictive value.

A solid tissue phantom for photon migration studies

International Nuclear Information System (INIS)

Cubeddu, Rinaldo; Pifferi, Antonio; Taroni, Paola; Torricelli, Alessandro; Valentini, Gianluca

1997-01-01

A solid tissue phantom made of agar, Intralipid and black ink is described and characterized. The preparation procedure is fast and easily implemented with standard laboratory equipment. An instrumentation for time-resolved transmittance measurements was used to determine the optical properties of the phantom. The absorption and the reduced scattering coefficients are linear with the ink and Intralipid concentrations, respectively. A systematic decrease of the reduced scattering coefficient dependent on the agar content is observed, but can easily be managed. The phantom is highly homogeneous and shows good repeatability among different preparations. Moreover, agar inclusions can be easily embedded in either solid or liquid matrixes, and no artefacts are caused by the solid - solid or solid - liquid interfaces. This allows one to produce reliable and realistic inhomogeneous phantoms with known optical properties, particularly interesting for studies on optical imaging through turbid media. (author)

Solid-State Division progress report for period ending March 31, 1983

International Nuclear Information System (INIS)

Green, P.H.; Watson, D.M.

1983-09-01

Progress and activities are reported on: theoretical solid-state physics (surfaces; electronic, vibrational, and magnetic properties; particle-solid interactions; laser annealing), surface and near-surface properties of solids (surface, plasma-material interactions, ion implantation and ion-beam mixing, pulsed-laser and thermal processing), defects in solids (radiation effects, fracture, impurities and defects, semiconductor physics and photovoltaic conversion), transport properties of solids (fast-ion conductors, superconductivity, mass and charge transport in materials), neutron scattering (small-angle scattering, lattice dynamics, magnetic properties, structure and instrumentation), and preparation and characterization of research materials (growth and preparative methods, nuclear waste forms, special materials)

Solid-State Division progress report for period ending March 31, 1983

Energy Technology Data Exchange (ETDEWEB)

Green, P.H.; Watson, D.M. (eds.)

1983-09-01

Progress and activities are reported on: theoretical solid-state physics (surfaces; electronic, vibrational, and magnetic properties; particle-solid interactions; laser annealing), surface and near-surface properties of solids (surface, plasma-material interactions, ion implantation and ion-beam mixing, pulsed-laser and thermal processing), defects in solids (radiation effects, fracture, impurities and defects, semiconductor physics and photovoltaic conversion), transport properties of solids (fast-ion conductors, superconductivity, mass and charge transport in materials), neutron scattering (small-angle scattering, lattice dynamics, magnetic properties, structure and instrumentation), and preparation and characterization of research materials (growth and preparative methods, nuclear waste forms, special materials). (DLC)

Characterization of the Vibrio cholerae extracellular matrix: a top-down solid-state NMR approach.

Science.gov (United States)

Reichhardt, Courtney; Fong, Jiunn C N; Yildiz, Fitnat; Cegelski, Lynette

2015-01-01

Bacterial biofilms are communities of bacterial cells surrounded by a self-secreted extracellular matrix. Biofilm formation by Vibrio cholerae, the human pathogen responsible for cholera, contributes to its environmental survival and infectivity. Important genetic and molecular requirements have been identified for V. cholerae biofilm formation, yet a compositional accounting of these parts in the intact biofilm or extracellular matrix has not been described. As insoluble and non-crystalline assemblies, determinations of biofilm composition pose a challenge to conventional biochemical and biophysical analyses. The V. cholerae extracellular matrix composition is particularly complex with several proteins, complex polysaccharides, and other biomolecules having been identified as matrix parts. We developed a new top-down solid-state NMR approach to spectroscopically assign and quantify the carbon pools of the intact V. cholerae extracellular matrix using ¹³C CPMAS and ¹³C{(¹⁵N}, ¹⁵N{³¹P}, and ¹³C{³¹P}REDOR. General sugar, lipid, and amino acid pools were first profiled and then further annotated and quantified as specific carbon types, including carbonyls, amides, glycyl carbons, and anomerics. In addition, ¹⁵N profiling revealed a large amine pool relative to amide contributions, reflecting the prevalence of molecular modifications with free amine groups. Our top-down approach could be implemented immediately to examine the extracellular matrix from mutant strains that might alter polysaccharide production or lipid release beyond the cell surface; or to monitor changes that may accompany environmental variations and stressors such as altered nutrient composition, oxidative stress or antibiotics. More generally, our analysis has demonstrated that solid-state NMR is a valuable tool to characterize complex biofilm systems. Copyright © 2014. Published by Elsevier B.V.

Evaluation of the Three Mile Island Unit 2 reactor building decontamination process

Energy Technology Data Exchange (ETDEWEB)

Dougherty, D.; Adams, J. W.

1983-08-01

Decontamination activities from the cleanup of the Three Mile Island Unit 2 Reactor Building are generating a variety of waste streams. Solid wastes being disposed of in commercial shallow land burial include trash and rubbish, ion-exchange resins (Epicor-II) and strippable coatings. The radwaste streams arising from cleanup activities currently under way are characterized and classified under the waste classification scheme of 10 CFR Part 61. It appears that much of the Epicor-II ion-exchange resin being disposed of in commerical land burial will be Class B and require stabilization if current radionuclide loading practices continue to be followed. Some of the trash and rubbish from the cleanup of the reactor building so far would be Class B. Strippable coatings being used at TMI-2 were tested for leachability of radionuclides and chelating agents, thermal stability, radiation stability, stability under immersion and biodegradability. Actual coating samples from reactor building decontamination testing were evaluated for radionuclide leaching and biodegradation.

Evaluation of the Three Mile Island Unit 2 reactor building decontamination process

International Nuclear Information System (INIS)

Dougherty, D.; Adams, J.W.

1983-08-01

Decontamination activities from the cleanup of the Three Mile Island Unit 2 Reactor Building are generating a variety of waste streams. Solid wastes being disposed of in commercial shallow land burial include trash and rubbish, ion-exchange resins (Epicor-II) and strippable coatings. The radwaste streams arising from cleanup activities currently under way are characterized and classified under the waste classification scheme of 10 CFR Part 61. It appears that much of the Epicor-II ion-exchange resin being disposed of in commerical land burial will be Class B and require stabilization if current radionuclide loading practices continue to be followed. Some of the trash and rubbish from the cleanup of the reactor building so far would be Class B. Strippable coatings being used at TMI-2 were tested for leachability of radionuclides and chelating agents, thermal stability, radiation stability, stability under immersion and biodegradability. Actual coating samples from reactor building decontamination testing were evaluated for radionuclide leaching and biodegradation

Thermal characterization of polymer matrix composites containing microencapsulated paraffin in solid or liquid state

International Nuclear Information System (INIS)

Sari-Bey, Sana; Fois, Magali; Krupa, Igor; Ibos, Laurent; Benyoucef, Boumédiène

2014-01-01

Highlights: • Thermal characterization of PCL/Micronal composites. • Melting enthalpy and heat capacity measured by DSC. • Interest: have measured thermal properties at different temperatures. • Thermophysical properties measurement temperatures chosen outside phase changes. • Characteristics useful to model composites heat transfer for LHTES applications. - Abstract: This work focuses on the study of heat transfer mechanisms in composites materials which may be used for Latent Heat Thermal Energy Storage applications. These composites contain phase change material (PCM) which can absorb and release energy during thermal cycling. PCM’s used here are paraffins microencapsulated in poly(methylmethacrylate); microencapsulation avoids the flow of paraffin when it is in the liquid state. Samples with different paraffin weight fractions and particles shape and distribution were studied in this work. Scanning Electron Microscopy and Differential Scanning Calorimetry were used to determine morphology and perform measurements of phase changes temperatures, enthalpies and heat capacity respectively. Further, a periodic method (DICO) allowed measuring thermal conductivity (λ) and diffusivity (a) of the composites at temperatures below and above of the paraffin phase change from crystalline solid to isotropic liquid

Characterization of dissolved solids in water resources of agricultural lands near Manila, Utah, 2004-05

Science.gov (United States)

Gerner, Steven J.; Spangler, L.E.; Kimball, B.A.; Naftz, D.L.

2006-01-01

Agricultural lands near Manila, Utah, have been identified as contributing dissolved solids to Flaming Gorge Reservoir. Concentrations of dissolved solids in water resources of agricultural lands near Manila, Utah, ranged from 35 to 7,410 milligrams per liter. The dissolved-solids load in seeps and drains in the study area that discharge to Flaming Gorge Reservoir ranged from less than 0.1 to 113 tons per day. The most substantial source of dissolved solids discharging from the study area to the reservoir was Birch Spring Draw. The mean daily dissolved-solids load near the mouth of Birch Spring Draw was 65 tons per day.The estimated annual dissolved-solids load imported to the study area by Sheep Creek and Peoples Canals is 1,330 and 13,200 tons, respectively. Daily dissolved-solid loads discharging to the reservoir from the study area, less the amount of dissolved solids imported by canals, for the period July 1, 2004, to June 30, 2005, ranged from 72 to 241 tons per day with a mean of 110 tons per day. The estimated annual dissolved-solids load discharging to the reservoir from the study area, less the amount of dissolved solids imported by canals, for the same period was 40,200 tons. Of this 40,200 tons of dissolved solids, about 9,000 tons may be from a regional source that is not associated with agricultural activities. The salt-loading factor is 3,670 milligrams per liter or about 5.0 tons of dissolved solids per acre-foot of deep percolation in Lucerne Valley and 1,620 milligrams per liter or 2.2 tons per acre-foot in South Valley.The variation of δ87Sr with strontium concentration indicates some general patterns that help to define a conceptual model of the processes affecting the concentration of strontium and the δ87Sr isotopic ratio in area waters. As excess irrigation water percolates through soils derived from Mancos Shale, the δ87Sr isotopic ratio (0.21 to 0.69 permil) approaches one that is typical of deep percolation from irrigation on Mancos

Structural diversity of solid dispersions of acetylsalicylic acid as seen by solid-state NMR.

Science.gov (United States)

Policianova, Olivia; Brus, Jiri; Hruby, Martin; Urbanova, Martina; Zhigunov, Alexander; Kredatusova, Jana; Kobera, Libor

2014-02-03

Solid dispersions of active pharmaceutical ingredients are of increasing interest due to their versatile use. In the present study polyvinylpyrrolidone (PVP), poly[N-(2-hydroxypropyl)-metacrylamide] (pHPMA), poly(2-ethyl-2-oxazoline) (PEOx), and polyethylene glycol (PEG), each in three Mw, were used to demonstrate structural diversity of solid dispersions. Acetylsalicylic acid (ASA) was used as a model drug. Four distinct types of the solid dispersions of ASA were created using a freeze-drying method: (i) crystalline solid dispersions containing nanocrystalline ASA in a crystalline PEG matrix; (ii) amorphous glass suspensions with large ASA crystallites embedded in amorphous pHPMA; (iii) solid solutions with molecularly dispersed ASA in rigid amorphous PVP; and (iv) nanoheterogeneous solid solutions/suspensions containing nanosized ASA clusters dispersed in a semiflexible matrix of PEOx. The obtained structural data confirmed that the type of solid dispersion can be primarily controlled by the chemical constitutions of the applied polymers, while the molecular weight of the polymers had no detectable impact. The molecular structure of the prepared dispersions was characterized using solid-state NMR, wide-angle X-ray scattering (WAXS), and differential scanning calorimetry (DSC). By applying various (1)H-(13)C and (1)H-(1)H correlation experiments combined with T1((1)H) and T1ρ((1)H) relaxation data, the extent of the molecular mixing was determined over a wide range of distances, from intimate intermolecular contacts (0.1-0.5 nm) up to the phase-separated nanodomains reaching ca. 500 nm. Hydrogen-bond interactions between ASA and polymers were probed by the analysis of (13)C and (15)N CP/MAS NMR spectra combined with the measurements of (1)H-(15)N dipolar profiles. Overall potentialities and limitations of individual experimental techniques were thoroughly evaluated.

Approved parallel methods for characterisation of solid carbon

International Nuclear Information System (INIS)

Fitzer, E.

1976-01-01

The contribution gives instructions for the work routine for 1) qualitative radiographic characterization of the microstructural order of solid carbon specimens, 2) X-ray determination of the mean interlattice plane distance anti c/2 of carbons, 3) determination of the helium density of carbons by means of the reference pycnometer, 4) determination of the specific surface area of carbon samples from nitrogen absorption. These instructions for the characterization of solid carbons are the first step towards a collection and comparison of the methods used in the participating countries. The international carbon groups (carbon societies) plan to supplement this collection for every international carbon conference. This collection will serve as a basis for the establishment of international working instructions. (orig./IHOE) [de

Reactive solid surface morphology variation via ionic diffusion.

Science.gov (United States)

Sun, Zhenchao; Zhou, Qiang; Fan, Liang-Shih

2012-08-14

In gas-solid reactions, one of the most important factors that determine the overall reaction rate is the solid morphology, which can be characterized by a combination of smooth, convex and concave structures. Generally, the solid surface structure varies in the course of reactions, which is classically noted as being attributed to one or more of the following three mechanisms: mechanical interaction, molar volume change, and sintering. Here we show that if a gas-solid reaction involves the outward ionic diffusion of a solid-phase reactant then this outward ionic diffusion could eventually smooth the surface with an initial concave and/or convex structure. Specifically, the concave surface is filled via a larger outward diffusing surface pointing to the concave valley, whereas the height of the convex surface decreases via a lower outward diffusion flux in the vertical direction. A quantitative 2-D continuum diffusion model is established to analyze these two morphological variation processes, which shows consistent results with the experiments. This surface morphology variation by solid-phase ionic diffusion serves to provide a fourth mechanism that supplements the traditionally acknowledged solid morphology variation or, in general, porosity variation mechanisms in gas-solid reactions.

Spectral time-domain induced polarization and magnetic surveying – an efficient tool for characterization of solid waste deposits in developing countries

DEFF Research Database (Denmark)

Wemegah, David Dotse; Fiandaca, Gianluca; Auken, Esben

Time-domain induced polarization (IP) and magnetic data were acquired to map and characterize the decommissioned, un-engineered, municipal solid waste deposit site of the Kwame Nkrumah University of Science and Technology (KNUST), located in the Kumasi Metropolis of Ghana. Thirteen induced...... polarization profiles 500-800 m long and twenty-six magnetic profiles 600-800 m long were acquired, and two drillings were carried out in order to help in the interpretation of the geophysical data. The study was carried out with the aim of determining the risk posed by the waste deposit to the quality...... for interpreting the polarization data. The chargeability, resistivity, and the normalized chargeability distributions, together with the magnetic results, aided in a full characterization of the site geology, the waste and the associated pollution plume. In particular, clear contrasts in resistivity...

Three-dimensional characterization of bacterial microcolonies on solid agar-based culture media.

Science.gov (United States)

Drazek, Laurent; Tournoud, Maud; Derepas, Frédéric; Guicherd, Maryse; Mahé, Pierre; Pinston, Frédéric; Veyrieras, Jean-Baptiste; Chatellier, Sonia

2015-02-01

For the last century, in vitro diagnostic process in microbiology has mainly relied on the growth of bacteria on the surface of a solid agar medium. Nevertheless, few studies focused in the past on the dynamics of microcolonies growth on agar surface before 8 to 10h of incubation. In this article, chromatic confocal microscopy has been applied to characterize the early development of a bacterial colony. This technology relies on a differential focusing depth of the white light. It allows one to fully measure the tridimensional shape of microcolonies more quickly than classical confocal microscopy but with the same spatial resolution. Placing the device in an incubator, the method was able to individually track colonies growing on an agar plate, and to follow the evolution of their surface or volume. Using an appropriate statistical modeling framework, for a given microorganism, the doubling time has been estimated for each individual colony, as well as its variability between colonies, both within and between agar plates. A proof of concept led on four bacterial strains of four distinct species demonstrated the feasibility and the interest of the approach. It showed in particular that doubling times derived from early tri-dimensional measurements on microcolonies differed from classical measurements in micro-dilutions based on optical diffusion. Such a precise characterization of the tri-dimensional shape of microcolonies in their late-lag to early-exponential phase could be beneficial in terms of in vitro diagnostics. Indeed, real-time monitoring of the biomass available in a colony could allow to run well established microbial identification workflows like, for instance, MALDI-TOF mass-spectrometry, as soon as a sufficient quantity of material is available, thereby reducing the time needed to provide a diagnostic. Moreover, as done for pre-identification of macro-colonies, morphological indicators such as three-dimensional growth profiles derived from

Research advances in adsorption treatment of cesium and cobalt in waste liquid of nuclear power plants by ion exchange resin

International Nuclear Information System (INIS)

Liu Dan; Wang Xin; Liu Jiean; Zhu Laiye; Chen Bin; Weng Minghui

2014-01-01

Liquid radwaste is unavoidably produced during the operation of nuclear power plants (NPP). With the development of China's nuclear power, much more attention will be paid to the impact of NPP construction on water environment. Radionuclides are the main targets for adsorption treatment of NPP liquid radwaste. Thereinto, cesium and cobalt are typical cationic ones. Currently, ion exchange process is widely used in liquid radwaste treatment system (WLS) of NPP, wherein resin plays a key role. The paper reviewed the research progress on adsorption of cesium and cobalt existed in NPP liquid radwaste using ion exchange resin. (authors)

Solid State Division progress report for period ending March 31, 1992

International Nuclear Information System (INIS)

Green, P.H.; Hinton, L.W.

1992-09-01

During this period, the division conducted a broad, interdisciplinary materials research program with emphasis on theoretical solid state physics, superconductivity, neutron scattering, synthesis and characterization of materials, ion beam and laser processing, and the structure of solids and surfaces. The High Flux Isotope Reactor was returned to full operation

Solid State Division progress report for period ending March 31, 1992

Energy Technology Data Exchange (ETDEWEB)

Green, P.H.; Hinton, L.W. (eds.)

1992-09-01

During this period, the division conducted a broad, interdisciplinary materials research program with emphasis on theoretical solid state physics, superconductivity, neutron scattering, synthesis and characterization of materials, ion beam and laser processing, and the structure of solids and surfaces. The High Flux Isotope Reactor was returned to full operation.

Synthesis, Characterization, and Optimization of Novel Solid Oxide Fuel Cell Anodes

Science.gov (United States)

Miller, Elizabeth C.

presents opportunities for the new kinds of ex situ and in situ experiments performed in this thesis. Ex situ experiments involved reducing powder samples at SOFC operating temperatures under hydrogen gas and characterizing them via electron microscopy and X-ray diffraction (XRD). For the in situ experiments, powders were heated, then reduced at temperature, and catalyst exsolution was observed in real-time. Pechini-synthesized cerium oxide substituted with 2-5 mol% Pd was studied using in situ X-ray heating experiments at Argonne National Laboratory's Advanced Photon Source. In these experiments, the powder was subjected to several cycles of reduction and oxidation at 800°C, and Pd metal formation was confirmed through the appearance of Pd peaks in the X-ray spectra. Next, Fe- and Ru-substituted lanthanum strontium chromite (LSCrFeRu14) synthesized by solid state reaction was characterized with ex situ and in situ microscopy. Transmission electron microscopy (TEM) in situ heating experiments were conducted to observe Ru nanoparticle evolution under the reducing conditions of the TEM vacuum chamber. LSCrFeRu14 was heated to 750°C and observed over ˜ 90 min at temperature during which time nanoparticle formation, coarsening, and di?usion were observed. Experiments on both materials sought to understand the conditions and timing of nanoparticle formation in the anode, which is not necessarily apparent from electrochemical data. Reducing the operating temperature of SOFCs from the current state-of-the-art range of 700-800°C to ≤ 650°C has many advantages, among them increased long-term stability, reduced balance of plant costs, fewer interconnect/seal material issues, and decreased start-up times. In order to maintain good performance at reduced temperature, these intermediate temperature SOFCs require new materials including highly active alternatives to micron-scale Ni-YSZ composite anodes. The present work focuses on the development of IT-SOFCs with Sr0.8La 0.2TiO3

Thermal characterization of metakaolin-based geopolymer

Czech Academy of Sciences Publication Activity Database

Samal, Sneha Manjaree; Thanh, N.P.; Marvalová, B.; Petrikova, I.

2017-01-01

Roč. 69, č. 12 (2017), s. 2480-2484 ISSN 1047-4838 Institutional support: RVO:68378271 Keywords : thermal * characterization * geopolymer Subject RIV: BM - Solid Matter Physics ; Magnetism OBOR OECD: Condensed matter physics (including formerly solid state physics, supercond.) Impact factor: 1.860, year: 2016

Study of solid chemical evolution in torrefaction of different biomasses through solid-state "1"3C cross-polarization/magic angle spinning NMR (nuclear magnetic resonance) and TGA (thermogravimetric analysis)

International Nuclear Information System (INIS)

Rodriguez Alonso, Elvira; Dupont, Capucine; Heux, Laurent; Da Silva Perez, Denilson; Commandre, Jean-Michel; Gourdon, Christophe

2016-01-01

The objective of this work is to compare mass loss and chemical evolution of the solid phase, versus time, during dynamic torrefaction of different types of biomass. For this purpose, two experiments, ThermoGravimetric Analysis and solid-state "1"3C Cross-Polarization/Magic Angle Spinning Nuclear Magnetic Resonance, were run on four representative biomasses. Overall mass loss and chemical evolution of the solid phase were followed, respectively, as a function of temperature and time. Thanks to this coupled information, it was shown that the knowledge of both solid mass loss and chemical evolution is necessary to characterize torrefaction severity. Moreover, biomasses containing higher proportions of xylan lost mass faster than those containing lower proportions. Lignin showed a protecting role towards cellulose, which would lead to a faster degradation of non-woody biomasses in comparison with woody biomasses. Three parameters would have an influence on solid chemical evolution during torrefaction: xylan content in hemicellulose, lignin content in biomass, and cellulose crystallinity. - Highlights: • Torrefaction of four biomasses was studied with TGA and solid-state NMR. • Both solid mass loss and chemical evolution characterize torrefaction severity. • Biomasses containing a higher proportion of xylan lose mass faster. • Lignin shows a stronger protecting role in degradation of woody biomasses. • Xylan, lignin and crystalline cellulose values influence solid chemical evolution.

Solid-phase microextraction/gas chromatography-mass spectrometry method optimization for characterization of surface adsorption forces of nanoparticles.

Science.gov (United States)

Omanovic-Miklicanin, Enisa; Valzacchi, Sandro; Simoneau, Catherine; Gilliland, Douglas; Rossi, Francois

2014-10-01

A complete characterization of the different physico-chemical properties of nanoparticles (NPs) is necessary for the evaluation of their impact on health and environment. Among these properties, the surface characterization of the nanomaterial is the least developed and in many cases limited to the measurement of surface composition and zetapotential. The biological surface adsorption index approach (BSAI) for characterization of surface adsorption properties of NPs has recently been introduced (Xia et al. Nat Nanotechnol 5:671-675, 2010; Xia et al. ACS Nano 5(11):9074-9081, 2011). The BSAI approach offers in principle the possibility to characterize the different interaction forces exerted between a NP's surface and an organic--and by extension biological--entity. The present work further develops the BSAI approach and optimizes a solid-phase microextraction gas chromatography-mass spectrometry (SPME/GC-MS) method which, as an outcome, gives a better-defined quantification of the adsorption properties on NPs. We investigated the various aspects of the SPME/GC-MS method, including kinetics of adsorption of probe compounds on SPME fiber, kinetic of adsorption of probe compounds on NP's surface, and optimization of NP's concentration. The optimized conditions were then tested on 33 probe compounds and on Au NPs (15 nm) and SiO2 NPs (50 nm). The procedure allowed the identification of three compounds adsorbed by silica NPs and nine compounds by Au NPs, with equilibrium times which varied between 30 min and 12 h. Adsorption coefficients of 4.66 ± 0.23 and 4.44 ± 0.26 were calculated for 1-methylnaphtalene and biphenyl, compared to literature values of 4.89 and 5.18, respectively. The results demonstrated that the detailed optimization of the SPME/GC-MS method under various conditions is a critical factor and a prerequisite to the application of the BSAI approach as a tool to characterize surface adsorption properties of NPs and therefore to draw any further

Characterization of a Green Solid Electric Propellant Microthruster for Small Spacecraft

Data.gov (United States)

National Aeronautics and Space Administration — The development of Solid Electric Propellants is an emerging topic of research with major implications in the field of space propulsion from the micro to macro...

Implementation of the Hungarian RW management project: Results and lessons

International Nuclear Information System (INIS)

Vigassy, J.; Czoch, I.; Ormai, P.

1995-01-01

In 1993, a National RW Management Project was launched to solve handling and disposal of LLW/ILW of the Paks Nuclear Power Plant and to elaborate a complex strategy for the management of radwastes from the NPP, including HLW, spent fuel and wastes from the decommissioning. It was intended to implement the project so as to have selected the possible site (or sites) for the LLW/ILW waste repository by 1996. This paper describes the first results of the nation-wide screening for suitable areas and the problems related to the comparative evaluation process to select potential sites for a surface or geological LLW/ILW disposal facility. International tenders were issued to find the most appropriate technology to reduce the quantity of liquid and solid radwaste in the Nuclear Power Plant. Their results will provide a better basis for planning the characteristics and quantity of radwaste. The applications revealed that supercompacting can be ordered as a service when the need arises, and thus it was possible to re-allocate the funding originally foreseen for the equipment to treat solid wastes. Great importance is attached in the Project to public acceptance and PR activity. An expert organization was selected in a two-phase bidding process, and it was decided that detailed exploration of a potential site will take place only if public acceptance is assured. The original program of the Hungarian RW Management Project was extended in 1994 to perform on-site underground investigations (with Canadian support) in a silt-stone formation. The first results confirm that this is a potential site for deep geological disposal of HLW. The financial and legal framework of the RW management is also to be solved. The new law on nuclear energy -- now in preparation -- will deal with that problem in one of its most important chapters, defining the responsibilities for RW management and the sources of funding

Evaluation of Waste-to-Energy Potential of Domestic Solid Wastes in ...

African Journals Online (AJOL)

ADOWIE PERE

waste in the metropolis ends up on illegal waste dumpsites. The aim of this paper was to investigate the waste-to-energy potentials of domestic solid wastes in Benin metropolis, Nigeria using a three-phase study plan - study of current waste management activities, characterization of domestic solid waste and determination ...

DNP-enhanced solid-state NMR spectroscopy of active pharmaceutical ingredients.

Science.gov (United States)

Zhao, Li; Pinon, Arthur C; Emsley, Lyndon; Rossini, Aaron J

2017-11-28

Solid-state NMR spectroscopy has become a valuable tool for the characterization of both pure and formulated active pharmaceutical ingredients (APIs). However, NMR generally suffers from poor sensitivity that often restricts NMR experiments to nuclei with favorable properties, concentrated samples, and acquisition of one-dimensional (1D) NMR spectra. Here, we review how dynamic nuclear polarization (DNP) can be applied to routinely enhance the sensitivity of solid-state NMR experiments by one to two orders of magnitude for both pure and formulated APIs. Sample preparation protocols for relayed DNP experiments and experiments on directly doped APIs are detailed. Numerical spin diffusion models illustrate the dependence of relayed DNP enhancements on the relaxation properties and particle size of the solids and can be used for particle size determination when the other factors are known. We then describe the advanced solid-state NMR experiments that have been enabled by DNP and how they provide unique insight into the molecular and macroscopic structure of APIs. For example, with large sensitivity gains provided by DNP, natural isotopic abundance, 13 C- 13 C double-quantum single-quantum homonuclear correlation NMR spectra of pure APIs can be routinely acquired. DNP also enables solid-state NMR experiments with unreceptive quadrupolar nuclei such as 2 H, 14 N, and 35 Cl that are commonly found in APIs. Applications of DNP-enhanced solid-state NMR spectroscopy for the molecular level characterization of low API load formulations such as commercial tablets and amorphous solid dispersions are described. Future perspectives for DNP-enhanced solid-state NMR experiments on APIs are briefly discussed. Copyright © 2017 John Wiley & Sons, Ltd.

New plant improves radwaste processing at the Tokai-2 BWR

International Nuclear Information System (INIS)

Anon.

1988-01-01

New plant for radiowaste processing at the Tokaj-2 NPP, put in operation in September, 1986, is described. The plant includes five systems providing processing of drianage water, solid waste combustion, decrease of volume and solidification of concentrated wastes, waste storage and flushing water processing. Pressed tablets represent the final product of the waste processing. New plant enables to reduce sufficiently the volume of radioactive wastes

State-of-the-art in analytical characterization of high purity solid ...

Indian Academy of Sciences (India)

Unknown

Laser nondispersive atomic fluorescence method with glow discharge cathode sputtering atomiser, may be used for ... The traditional arc and spark emission technique still ..... (without any chemical pretreatment) survey analysis of solids with ...

Solid-state electroanalytical characterization of the nonaqueous proton-conducting redox gel containing polyoxometallates

International Nuclear Information System (INIS)

Lewera, Adam; Zukowska, Grazyna; Miecznikowski, Krzysztof; Chojak, Malgorzata; Wieczorek, Wladyslaw; Kulesza, Pawel J.

2005-01-01

A novel polymetacrylate-based redox-conducting polymeric gel, into which Keggin-type polyoxometallate, phosphododecatungstic acid (H 3 PW 12 O 40 ), had been incorporated, was electrochemically characterized in the absence of external liquid supporting electrolyte using an ultramicrodisk-working electrode. The phosphotungstate component (15 wt.% of the gel block) was entrapped as the polar organic solvent solution within pores of the polymer matrix. H 3 PW 12 O 40 plays bifunctional role: it provides well-behaved redox centers and serves as strong acid (source of mobile protons). The solid-state voltammetric properties of the system are defined by the reversible one-electron transfers between phosphotungstate redox centers. The following parameters have been determined from the combination of potential step experiments performed in two limiting (radial and linear) diffusional regimes: the concentration of heteropolytungstate redox centers, 6 x 10 -2 mol dm -3 , and the apparent diffusion coefficient, 5 x 10 -7 cm 2 s -1 . The room temperature ionic (protonic) conductivity of the bulk gel was equal to 1.6 x 10 -3 S cm -1 . The charge propagation mechanism was found to be primarily controlled by physical diffusion of heteropolytungstate units within the gel pores rather than by electron hopping (self-exchange) between mixed-valence sites

Comparison of three different types of cilostazol-loaded solid dispersion: Physicochemical characterization and pharmacokinetics in rats.

Science.gov (United States)

Mustapha, Omer; Kim, Kyung Soo; Shafique, Shumaila; Kim, Dong Shik; Jin, Sung Giu; Seo, Youn Gee; Youn, Yu Seok; Oh, Kyung Taek; Yong, Chul Soon; Kim, Jong Oh; Choi, Han-Gon

2017-06-01

The aim of this research was to compare three different types of cilostazol-loaded solid dispersion system including solvent-evaporated, solvent-wetted and surface-attached solid dispersion. The effect of polymers and surfactants on the aqueous solubility of cilostazol was investigated, leading to the selection of polyvinylpyrrolidone (PVP) and sodium lauryl sulphate (SLS). Employing a spray-drying technique, numerous surface-attached, solvent-evaporated and solvent-wetted solid dispersions were prepared with various amounts PVP and SLS using water, 90% ethanol and acetone, respectively. Their physicochemical properties, solubility, dissolution and oral bioavailability in rats were assessed compared to the drug powder. Among each solid dispersion system tested, the surface-attached, solvent-evaporated and solvent-wetted solid dispersions composed of cilostazol, PVP and SLS at weight ratios of 3.0 : 0.75 : 1.5, 3.0 : 3.0 : 1.5 and 3.0 : 3.0 : 1.5, respectively, provided the highest drug solubility and dissolution. The solvent-evaporated solid dispersion gave homogeneous and very small spherical particles, in which the drug was changed to an amorphous state. In the solvent-wetted solid dispersion, the amorphous drug was attached to the polymer surface. Conversely, in the surface-attached solid dispersion, the carriers were adhered onto the surface of the unchanged crystalline drug. The solubility, dissolution and oral bioavailability were significantly increased in the order of solvent-evaporated>solvent-wetted>surface-attached>drug powder. Thus, the type of solid dispersion considerably affected the physicochemical properties, aqueous solubility and oral bioavailability. Furthermore, the cilostazol-loaded solvent-evaporated solid dispersion with the highest oral bioavailability would be actively recommended as a practical oral pharmaceutical product. Copyright © 2017 Elsevier B.V. All rights reserved.

Mydriatics release from solid and semi-solid ophthalmic formulations using different in vitro methods.

Science.gov (United States)

Pescina, Silvia; Macaluso, Claudio; Gioia, Gloria Antonia; Padula, Cristina; Santi, Patrizia; Nicoli, Sara

2017-09-01

The aim of the present paper was the development of semi-solid (hydrogels) and solid (film) ophthalmic formulations for the controlled release of two mydriatics: phenylephrine and tropicamide. The formulations - based on polyvinylalcohol and hyaluronic acid - were characterized, and release studies were performed with three different in vitro set-ups, i.e. Franz-type diffusion cell, vial method and inclined plane; for comparison, a solution and a commercial insert, both clinically used to induce mydriasis, were evaluated. Both gels and film allowed for a controlled release of drugs, appearing a useful alternative for mydriatics administration. However, the release kinetic was significantly influenced by the method used, highlighting the need for optimization and standardization of in vitro models for the evaluation of drug release from ophthalmic dosage forms.

Synthesis, Characterization and Conductivity Study of Poly(vinyl 4-HYDROXY-3-METHOXY Benzal) and its Sodio Salt in Solid State

Science.gov (United States)

Borah, P.; Hussain, S.; Dutta, A.

Among the various ion-conducting materials, polymer salt complexes are of current interest due to their possible application as solid electrolyte as well as their physical nature in advanced high-energy electrochemical devices such as batteries, fuel cells, electrochromic display devices, photo electro-chemical solar cells52-55 etc. The main advantages of polymeric electrolytes are their mechanical properties, ease of fabrication of thin films of desired sizes and their ability to form proper electrode-electrolyte contact. Polymer electrolyte usually consists of a polymer and a salt and is considered to be solid solutions in which the polymer functions as solvent. In the present paper the synthesis, characterization and the conductivity study of the polymer poly (vinyl 4-hydroxy-3-methoxy benzal) (PV-HMB) and its sodio salt (PV-HMB-Na) have been reported. The polymer was prepared by carrying out homogenous acetalization between the prepolymer poly vinylalcohol (PVA) and 4-hydroxy-3-methoxy benzaldehyde (vanilline). PVA was dissolved in dimethyl formamide (DMF) and lithium chloride (LiCl) system i.e., in non-aqueous medium. The sodio salt was prepared by alkalization. The polymer and its salt were characterized by IR, 1H NMR and DSC. Frequency and temperature dependence of ac conductivity has been studied to learn about the electrical conduction behaviour in this material. The electrical conductivity of the new polymeric salt was found to be in the range 10-4 to 10-6 Scm-1. There is about 103 to 104 fold increase in the conductivity of the new polymer salt. Apparent activation energy of the polymer and its salt were found to be 0.139 and 0.08998 ev respectively.

Fabricating and Characterizing the Microfluidic Solid Phase Extraction Module Coupling with Integrated ESI Emitters

Directory of Open Access Journals (Sweden)

Hangbin Tang

2018-05-01

Full Text Available Microfluidic chips coupling with mass spectrometry (MS will be of great significance to the development of relevant instruments involving chemical and bio-chemical analysis, drug detection, food and environmental applications and so on. In our previous works, we proposed two types of microfluidic electrospray ionization (ESI chip coupling with MS: the two-phase flow focusing (FF ESI microfluidic chip and the corner-integrated ESI emitter, respectively. However the pretreatment module integrated with these ESI emitters is still a challenging problem. In this paper, we concentrated on integrating the solid phase micro-extraction (SPME module with our previous proposed on-chip ESI emitters; the fabrication processes of such SPME module are fully compatible with our previous proposed ESI emitters based on the multi-layer soft lithography. We optimized the structure of the integrated chip and characterized its performance using standard samples. Furthermore, we verified its abilities of salt removal, extraction of multiple analytes and separation through on-chip elution using mimic biological urine spiked with different drugs. The results indicated that our proposed integrated module with ESI emitters is practical and effective for real biological sample pretreatment and MS detection.

Solid state laser technology - A NASA perspective

Science.gov (United States)

Allario, F.

1985-01-01

NASA's program for developing solid-state laser technology and applying it to the Space Shuttle and Space Platform is discussed. Solid-state lasers are required to fulfill the Earth Observation System's requirements. The role of the Office of Aeronautics and Space Technology in developing a NASA tunable solid-state laser program is described. The major goals of the program involve developing a solid-state pump laser in the green, using AlGaAs array technology, pumping a Nd:YAG/SLAB crystal or glass, and fabricating a lidar system, with either a CO2 laser at 10.6 microns or a Nd:YAG laser at 1.06 microns, to measure tropospheric winds to an accuracy of + or - 1 m/s and a vertical resolution of 1 km. The procedures to be followed in order to visualize this technology plan include: (1) material development and characterization, (2) laser development, and (3) implementation of the lasers.

Fabrication and characterization of solid oxide cells for energy conversion and storage

Science.gov (United States)

Yang, Chenghao

2011-12-01

There has been an increasing interest in clean and renewable energy generation for highlighted energy and environmental concerns. Solid oxide cells (SOCs) have been considered as one of the promising technologies, since they can be operated efficiently both in electrolysis mode by generating hydrogen through steam electrolysis and fuel cell mode by electrochemically combining fuel with oxidant. The present work is devoted to performing a fundamental study of SOC in both fuel cell mode for power generation and electrolysis mode for fuel production. The research work on SOCs that can be operated reversibly for power generation and fuel production has been conducted in the following six projects: (1) High performance solid oxide electrolysis cell (SOEC) Fabrication of novel structured SOEC oxygen electrode with the conventional and commercial solid oxide fuel cell materials by screen-printing and infiltration fabrication methods. The microstructure, electrochemical properties and durability of SOECs has been investigated. It was found that the LSM infiltrated cell has an area specific resistance (ASR) of 0.20 Ω cm2 at 900°C at open circuit voltage with 50% absolute humidity (AH), which is relatively lower than that of the cell with LSM-YSZ oxygen electrode made by a conventional mixing method. Electrolysis cell with LSM infiltrated oxygen electrode has demonstrated stable performance under electrolysis operation with 0.33 A/cm2 and 50 vol.% AH at 800°C. (2) Advanced performance high temperature micro-tubular solid oxide fuel cell (MT-SOFC) Phase-inversion, dip-coating, high temperature co-sintering process and impregnation method were used to fabricate micro-tubular solid oxide fuel cell. The micro-structure of the micro-tubular fuel cell will be investigated and the power output and thermal robustness has been evaluated. High performance and rapid start-up behavior have been achieved, indicates that the MT-SOFC developed in this work can be a promising technology

Antimony smelting process generating solid wastes and dust: characterization and leaching behaviors.

Science.gov (United States)

Guo, Xuejun; Wang, Kunpeng; He, Mengchang; Liu, Ziwei; Yang, Hailin; Li, Sisi

2014-07-01

A large amount of solid waste has been produced by the antimony smelting process in the "World Capital of Antimony", Xikuangshan area in China. This study comprehensively investigated the physical and chemical characteristics of the various solid wastes, as well as the leaching behavior of the solid wastes, which included water-quenched slag, arsenic-alkali residue, desulfurized slag and blast furnace dust. These four types of waste were enriched in a variety of heavy metals and metalloids and more specifically with As and Sb levels up to 8.6 × 10⁴ and 3.16×10⁵ mg/kg, respectively, in arsenic-alkali residue. For desulfurized slag and water-quenched slag, the leaching concentration of Sb significantly exceeded the acceptable limits during the leaching tests using the toxicity characteristic leaching procedure and the synthetic precipitation leaching procedure. In addition, As leaching in arsenic-alkali residue was extraordinarily hazardous, being three orders of magnitude higher than the regulatory level of As. According to the results of the extraction tests, all the tested wastes were classified as hazardous waste. Copyright © 2014. Published by Elsevier B.V.

Interim site characterization report and ground-water monitoring program for the Hanford site solid waste landfill

International Nuclear Information System (INIS)

Fruland, R.M.; Hagan, R.A.; Cline, C.S.; Bates, D.J.; Evans, J.C.; Aaberg, R.L.

1989-07-01

Federal and state regulations governing the operation of landfills require utilization of ground-water monitoring systems to determine whether or not landfill operations impact ground water at the point of compliance (ground water beneath the perimeter of the facility). A detection-level ground-water monitoring system was designed, installed, and initiated at the Hanford Site Solid Waste Landfill (SWL). Chlorinated hydrocarbons were detected at the beginning of the ground-water monitoring program and continue to be detected more than 1 year later. The most probable source of the chlorinated hydrocarbons is washwater discharged to the SWL between 1985 and 1987. This is an interim report and includes data from the characterization work that was performed during well installation in 1987, such as field observations, sediment studies, and geophysical logging results, and data from analyses of ground-water samples collected in 1987 and 1988, such as field parameter measurements and chemical analyses. 38 refs., 27 figs., 8 tabs

Microbiological characterization and specific methanogenic activity of anaerobe sludges used in urban solid waste treatment

International Nuclear Information System (INIS)

Sandoval Lozano, Claudia Johanna; Vergara Mendoza, Marisol; Carreno de Arango, Mariela; Castillo Monroy, Edgar Fernando

2009-01-01

This study presents the microbiological characterization of the anaerobic sludge used in a two-stage anaerobic reactor for the treatment of organic fraction of urban solid waste (OFUSW). This treatment is one alternative for reducing solid waste in landfills at the same time producing a biogas (CH 4 and CO 2 ) and an effluent that can be used as biofertilizer. The system was inoculated with sludge from a wastewater treatment plant (WWTP) (Rio Frio Plant in Bucaramanga-Colombia) and a methanogenic anaerobic digester for the treatment of pig manure (Mesa de los Santos in Santander). Bacterial populations were evaluated by counting groups related to oxygen sensitivity, while metabolic groups were determined by most probable number (MPN) technique. Specific methanogenic activity (SMA) for acetate, formate, methanol and ethanol substrates was also determined. In the acidogenic reactor (R1), volatile fatty acids (VFA) reached values of 25,000 mg L -1 and a concentration of CO 2 of 90%. In this reactor, the fermentative population was predominant (10 5 -10 6 MPN mL -1 ). The acetogenic population was (10 5 MPN mL -1 ) and the sulphate-reducing population was (10 4 -10 5 MPN mL -1 ). In the methanogenic reactor (R2), levels of CH 4 (70%) were higher than CO 2 (25%), whereas the VFA values were lower than 4000 mg L -1 . Substrate competition between sulphate-reducing (10 4 -10 5 MPN mL -1 ) and methanogenic bacteria (10 5 MPN mL -1 ) was not detected. From the SMA results obtained, acetoclastic (2.39 g COD-CH 4 g -1 VSS -1 day -1 ) and hydrogenophilic (0.94 g COD-CH 4 g -1 VSS -1 day -1 ) transformations as possible metabolic pathways used by methanogenic bacteria is suggested from the SMA results obtained. Methanotrix sp., Methanosarcina sp., Methanoccocus sp. and Methanobacterium sp. were identified

Characterization of Two Distinct Amorphous Forms of Valsartan by Solid-State NMR.

Science.gov (United States)

Skotnicki, Marcin; Apperley, David C; Aguilar, Juan A; Milanowski, Bartłomiej; Pyda, Marek; Hodgkinson, Paul

2016-01-04

Valsartan (VAL) is an antihypertensive drug marketed in an amorphous form. Amorphous materials can have different physicochemical properties depending on preparation method, thermal history, etc., but the nature of such materials is difficult to study by diffraction techniques. This study characterizes two different amorphous forms of valsartan (AR and AM) using solid-state NMR (SSNMR) as a primary investigation tool, supported by solution-state NMR, FT-IR, TMDSC, and dissolution tests. The two forms are found to be clearly distinct, with a significantly higher level of structural arrangement in the AR form, as observed in (13)C, (15)N, and (1)H SSNMR. (13)C and (15)N NMR indicates that the fully amorphous material (AM) contains an approximately equal ratio of cis-trans conformers about the amide bond, whereas the AR form exists mainly as one conformer, with minor conformational "defects". (1)H ultrafast MAS NMR shows significant differences in the hydrogen bonding involving the tetrazole and acid hydrogens between the two materials, while (15)N NMR shows that both forms exist as a 1,2,3,4-tetrazole tautomer. NMR relaxation times show subtle differences in local and bulk molecular mobility, which can be connected with the glass transition, the stability of the glassy material, and its response to aging. Counterintuitively the fully amorphous material is found to have a significantly lower dissolution rate than the apparently more ordered AR material.

Development, Characterization and Evaluation of Solid Lipid Nanoparticles as a potential Anticancer Drug Delivery System

Science.gov (United States)

Patel, Meghavi

Solid lipid nanoparticles (SLNs) consist of spherical solid lipid particles in the nanometer size range, which are dispersed in water or in an aqueous surfactant solution. SLN technology represents a promising new approach to deliver hydrophilic as well as lipophilic drugs. The commercialization of SLN technology remains limited despite numerous efforts from researchers. The purpose of this research was to advance SLN preparation methodology by investigating the feasibility of preparing glyceryl monostearate (GMS) nanoparticles by using three preparation methods namely microemulsion technique, magnetic stirring technique and temperature modulated solidification technique of which the latter two were developed in our laboratory. An anticancer drug 5-fluorouracil was incorporated in the SLNs prepared via the temperature modulated solidification process. Optimization of the magnetic stirring process was performed to evaluate how the physicochemical properties of the SLN was influenced by systematically varying process parameters including concentration of the lipid, concentration of the surfactant, type of surfactant, time of stirring and temperature of storage. The results demonstrated 1:2 GMS to tween 80 ratio, 150 ml dispersion medium and 45 min stirring at 4000 RPM speed provided an optimum formulation via the temperature modulated solidification process. SLN dispersions were lyophilized to stabilize the solid lipid nanoparticles and the lyophilizates exhibited good redispersibility. The SLNs were characterized by particle size analysis via dynamic light scattering (DLS), zeta potential, transmission electron microscopy (TEM), differential scanning calorimetry (DSC), drug encapsulation efficiency and in vitro drug release studies. Particle size of SLN dispersion prepared via the three preparation techniques was approximately 66 nm and that of redispersed lyophilizates was below 500 nm. TEM images showed spherical to oval particles that were less dense in the core

Characteristics of soils and saprolite in Solid Waste Storage Area 6

International Nuclear Information System (INIS)

Ammons, J.T.; Phillips, D.H.; Timpson, M.E.

1987-01-01

Solid Waste Storage Area 6 (SWSA-6) is one of the disposal sites for solid low-level radioactive waste at Oak Ridge National Laboratory. Soils and saprolites from the site were characterized to provide base line information to initiate assessment for remedial actions and closure plans. Physical, chemical, mineralogical, and engineering analyses were conducted on soil and saprolite samples

Sampling and Characterization of 618-2 Anomalous Material

International Nuclear Information System (INIS)

Zacharias, A.E.

2006-01-01

This as low as reasonably achievable (ALARA) Level II review documents radiological engineering and administrative controls necessary for the sampling and characterization of anomalous materials discovered during the remediation of the 618-2 solid waste burial ground. The goals of these engineering and administrative controls are to keep personnel exposure ALARA, control contamination levels, and minimize potential for airborne contamination. Excavation of the 618-2 Burial Ground has produced many items of anomalous waste. Prior to temporary packaging and/or storage, these items have been characterized in the field to identify radiological and industrial safety conditions. Further sampling and characterization of these items, as well as those remaining from an excavated combination safe, is the subject of this ALARA Level II review. An ALARA in-progress review will also be performed prior to sampling and characterization of 618-2 anomalous materials offering risks of differing natures. General categories of anomalies requiring further characterization include the following: (1) Containers of unknown liquids and/or solids and powders (excluding transuranics); (2) Drums containing unknown liquids and/or solids; (3) Metal containers with unknown contents; and (4) Known or suspected transuranic material.

Characterisation and modelling of blended cements and their application to radioactive waste immobilisation

International Nuclear Information System (INIS)

Glasser, F.P.; Atkins, M.; Kindness, A.

1991-01-01

Various aspects of the chemistry of cements, including blends with FA and BFS, pertinent to the immobilization of radioactive waste are described. The methodology and development of a model for predicting the solid and liquid phase composition in aged cement blends are given. Experimental work, backed up by thermodynamic calculations (where possible), has given valuable insight into some of the important interactions between selected (active and inactive) radwaste components and cements. The effects of elevated pressure and temperature on blended cement are also investigated. (author)

Development of high temperature mechanical rig for characterizing the viscoplastic properties of alloys used in solid oxide cells

DEFF Research Database (Denmark)

Tadesse Molla, Tesfaye; Greco, Fabio; Kwok, Kawai

2018-01-01

Analyzing the thermo-mechanical reliability of solid oxide cell (SOC) stack requires precise measurement of the mechanical properties of the different components in the stack at operating conditions of the SOC. It is challenging to precisely characterize the time dependent deformational properties...... temperature and in controlled atmosphere. The methodology uses a mechanical loading rig designed to apply variable as well as constant loads on samples within a gas-tight high temperature furnace. In addition, a unique remotely installed length measuring setup involving laser micrometer is used to monitor...... deformations in the sample. Application of the methodology is exemplified by measurement of stress relaxation, creep and constant strain rate behaviors of a high temperature alloy used in the construction of SOC metallic interconnects at different temperatures. Furthermore, measurements using the proposed...

Preparation, characterization, and optimization of altretamine-loaded solid lipid nanoparticles using Box-Behnken design and response surface methodology.

Science.gov (United States)

Gidwani, Bina; Vyas, Amber

2016-01-01

The objective of the present study was to prepare solid lipid nanoparticles (SLNs) of altretamine (ALT) by the hot homogenization and ultrasonication method. The study was conducted using the Box-Behnken design (BBD), with a 3(3) design and a total of 17 experimental runs, performed in combination with response surface methodology (RSM). The SLNs were evaluated for mean particle size, entrapment efficiency, and drug-loading. The optimized formulation, with a desirability factor of 0.92, was selected and characterized. In vitro release studies showed a biphasic release pattern from the SLNs for up to 24 h. The results of % EE (93.21 ± 1.5), %DL (1.15 ± 0.6), and mean diameter of (100.6 ± 2.1) nm, were very close to the predicted values.

Solid-state syntheses and single-crystal characterizations of three tetravalent thorium and uranium silicates

International Nuclear Information System (INIS)

Jin, Geng Bang; Soderholm, L.

2015-01-01

Colorless crystals of ThSiO 4 (huttonite) (1) and (Ca 0.5 Na 0.5 ) 2 NaThSi 8 O 20 (2) have been synthesized by the solid-state reactions of ThO 2 , CaSiO 3 , and Na 2 WO 4 at 1073 K. Green crystals of (Ca 0.5 Na 0.5 ) 2 NaUSi 8 O 20 (3) have been synthesized by the solid-state reactions of UO 2 , CaSiO 3 , and Na 2 WO 4 at 1003 K. All three compounds have been characterized by single-crystal X-ray diffraction. Compound 1 adopts a monazite-type three-dimensional condensed structure, which is built from edge- and corner-shared ThO 9 polyhedra and SiO 4 tetrahedra. Compounds 2 and 3 are isostructural and they crystallize in a steacyite-type structure. The structure consists of discrete pseudocubic [Si 8 O 20 ] 8− polyanions, which are connected by An 4+ cations into a three-dimensional framework. Each An atom coordinates to eight monodentate [Si 8 O 20 ] 8− moieties in a square antiprismatic geometry. Na + and Ca 2+ ions reside in the void within the framework. Raman spectra of 1, 2, and 3 were collected on single crystal samples. 1 displays more complex vibrational bands than thorite. Raman spectra of 2 and 3 are analogous with most of vibrational bands located at almost the same regions. - Graphical abstract: A Raman spectrum and crystal structures of (Ca 0.5 Na 0.5 ) 2 NaAnSi 8 O 20 (An=Th, U), which contain pseudocubic [Si 8 O 20 ] 8− polyanions and eight-coordinate An 4+ cations. - Highlights: • Single crystal growth of three tetravalent actinide silicates from melts. • Single-crystal structures and Raman spectra of (Ca 0.5 Na 0.5 ) 2 NaAnSi 8 O 20 (An=Th, U). • First report of Raman spectrum of huttonite on single crystal samples