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Sample records for radiochemical processing laboratory

  1. Radiochemical Processing Laboratory (RPL)

    Data.gov (United States)

    Federal Laboratory Consortium — The Radiochemical Processing Laboratory (RPL)�is a scientific facility funded by DOE to create and implement innovative processes for environmental clean-up and...

  2. Guiding Principles for Sustainable Existing Buildings: Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Pope, Jason E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-11-11

    In 2006, the United States (U.S.) Department of Energy (DOE) signed the Federal Leadership in High Performance and Sustainable Buildings Memorandum of Understanding (MOU), along with 21 other agencies. Pacific Northwest National Laboratory (PNNL) is exceeding this requirement and, currently, about 25 percent of its buildings are High Performance and Sustainable Buildings. The pages that follow document the Guiding Principles conformance effort for the Radiochemical Processing Laboratory (RPL) at PNNL. The RPL effort is part of continued progress toward a building inventory that is 100 percent compliant with the Guiding Principles.

  3. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    International Nuclear Information System (INIS)

    Shields, K.D.; Ballinger, M.Y.

    1999-03-01

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities

  4. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

  5. Design of the Laboratory-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Lumetta, Gregg J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Meier, David E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Tingey, Joel M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Casella, Amanda J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Delegard, Calvin H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Edwards, Matthew K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Orton, Robert D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Rapko, Brian M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Smart, John E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-05-01

    This report describes a design for a laboratory-scale capability to produce plutonium oxide (PuO2) for use in identifying and validating nuclear forensics signatures associated with plutonium production, as well as for use as exercise and reference materials. This capability will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including PuO2 dissolution, purification of the Pu by ion exchange, precipitation, and re-conversion to PuO2 by calcination.

  6. Improved monitoring procedure for Iodine -131 in radiochemical process laboratory

    International Nuclear Information System (INIS)

    Singh, Pratap; Yadav, R.K.B.; Anilkumar, S.; Gopalakrishnan, R.K.; Chakraborty, S.

    2016-01-01

    Radiation Hazard Control Unit at Isotope wing provides radiological safety support and advises for safe processing and production of radiopharmaceuticals. Tellurium Oxide (TeO 2 ), irradiated in a nuclear reactor, is processed in a process laboratory for separating 131 I using dry distillation technique. The workplace environment is being assessed for airborne radioactivity using installed Static Air Samplers (SASs). SASs contains two filter media (glass fibre and charcoal impregnated paper) to collect airborne 131 I radioactivity and laboratory air sampled at 50 litres per minutes (lpm). Personal Air Sampler (PAS) consists of three types of filters viz. a glass fibre, charcoal impregnated paper and cartridges containing activated charcoal granules. Three combinations were studied at a sampling rate of 5 lpm

  7. Conceptual Design for the Pilot-Scale Plutonium Oxide Processing Unit in the Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Lumetta, Gregg J.; Meier, David E.; Tingey, Joel M.; Casella, Amanda J.; Delegard, Calvin H.; Edwards, Matthew K.; Jones, Susan A.; Rapko, Brian M.

    2014-08-05

    This report describes a conceptual design for a pilot-scale capability to produce plutonium oxide for use as exercise and reference materials, and for use in identifying and validating nuclear forensics signatures associated with plutonium production. This capability is referred to as the Pilot-scale Plutonium oxide Processing Unit (P3U), and it will be located in the Radiochemical Processing Laboratory at the Pacific Northwest National Laboratory. The key unit operations are described, including plutonium dioxide (PuO2) dissolution, purification of the Pu by ion exchange, precipitation, and conversion to oxide by calcination.

  8. Rapid radiochemical procedures for a process support laboratory

    International Nuclear Information System (INIS)

    Beals, D.M.

    1998-01-01

    An on-site mobile laboratory has been installed near a groundwater treatment facility, and rapid analytical procedures have been deployed for determining sample activity in the process support laboratory. The required analyses to support the remediation project include gross alpha/, gross nonvolatile beta, 90 Sr, 99 Tc, 137 Cs and total Ra (226 + 228). The present mission of the Savannah River Site (SRS), a US Department of Energy nuclear production facility, is one of nuclear waste stabilization and of environmental restoration and remediation. Because of previous practices of disposing low-level radioactive waste to seepage basins, some of the groundwater under the SRS has become contaminated with radioactive species. A water treatment facility has been installed to remediate the groundwater below the old F and H areas' seepage basins. Groundwater is pumped from the contaminated aquifer through a series of filtration, ion exchange, and reverse osmosis steps and when cleaned is reinjected back into the aquifer. Samples are pulled from various points in the treatment facility to ensure that the process is working as designed. In order to minimize turnaround time for these analyses, a process control station (i.e., a mobile on-site laboratory) has been installed at the F area water treatment unit, and rapid radioanalytical procedures have been deployed

  9. Thorium base fuels reprocessing at the L.P.R. (Radiochemical Processes Laboratory) experimental plant

    International Nuclear Information System (INIS)

    Almagro, J.C.; Dupetit, G.A.; Deandreis, R.A.

    1987-01-01

    The availability of the LPR (Radiochemical Processes Laboratory) plant offers the possibility to demonstrate and create the necessary technological basis for thorium fuels reprocessing. To this purpose, the solvents extraction technique is used, employing TBP (at 30%) as solvent. The process is named THOREX, a one-cycle acid, which permits an adequate separation of Th 232 and U 233 components and fission products. For thorium oxide elements dissolution, the 'chopp-leach' process (installed at LPR) is used, employing a NO 3 H 13N, 0.05M FH and 0.1M Al (NO 3 ) 3 , as solvent. To adapt the pilot plant to the flow-sheet requirements proposed, minor modifications must be carried out in the interconnection of the existing decanting mixers. The input of the plant has been calculated by Origin Code modified for irradiations in reactors of the HWR type. (Author)

  10. Placement of the radiochemical processing plant at Oak Ridge National Laboratory into a safe standby condition

    International Nuclear Information System (INIS)

    Holladay, D.W.; Bopp, C.D.; Farmer, A.J.; Johnson, J.K.; Miller, C.H.; Powers, B.A.; Collins, E.D.

    1986-01-01

    Extensive upgrade, cleanup, and decontamination efforts are being conducted for appropriate areas in the Radiochemical Processing Plant (RPP) with the goal of achieving safe standby condition by the end of FY 1989. The ventilation system must maintain containment thus, it is being upgraded via demolition and replacement of marginally adequate ductwork, fans, and control systems. Areas that are being decontaminated and stripped of various services (e.g., piping, ductwork, and process tanks) include hot cells, makeup rooms, and pipe tunnels. Operating equipment that is being decontaminated includes glove boxes and hoods. Replacement of the ventilation system and removal of equipment from pipe tunnels, cells, and makeup rooms are accomplished by contact labor by workers using proper attire, safety rules, and shielding, Removal of contaminated ductwork and piping is conducted with containment enclosures that are strategically located at breakpoints, and methods of separation are chosen to conform with health physics requirements. The methods of cutting contaminated piping and ductwork include portable reciprocating saws, pipe cutters, burning, and plasma torch. Specially designed containment enclosures will be used to prevent the spread of radioactive contamination while maintaining adequate ventilation

  11. Placement of the radiochemical processing plant at Oak Ridge National Laboratory into a safe standby condition

    International Nuclear Information System (INIS)

    Holladay, D.W.; Bopp, C.D.; Farmer, A.J.; Johnson, J.K.; Miller, C.H.; Powers, B.A.; Collins, E.D.

    1986-01-01

    Extensive upgrade, cleanup, and decontamination efforts are being conducted for appropriate areas in the Radiochemical Processing Plant (RPP) with the goal of achieving ''safe standby'' condition by the end of FY 1989. The ventilation system must maintain containment; thus, it is being upgraded via demolition and replacement of marginally adequate ductwork, fans, and control systems. Areas that are being decontaminated and stripped of various services (e.g., piping, ductwork, and process tanks) include hot cells, makeup rooms, and pipe tunnels. Operating equipment that is being decontaminated includes glove boxes and hoods. Replacement of the ventilation system and removal of equipment from pipe tunnels, cells, and makeup rooms are accomplished by contact labor by workers using proper attire, safety rules, and shielding. Removal of contaminated ductwork and piping is conducted with containment enclosures that are strategically located at breakpoints, and methods of separation are chosen to conform with health physics requirements. The methods of cutting contaminated piping and ductwork include portable reciprocating saws, pipe cutters, burning, and plasma torch. Specially designed containment enclosures will be used to prevent the spread of radioactive contamination while maintaining adequate ventilation. 6 figs

  12. The use of robots for automation in the radiochemical laboratory

    International Nuclear Information System (INIS)

    Huddleston, J.

    1988-01-01

    The use of robotic systems for automated processes such as overnight operations, procedures involving radiation hazards in radiochemical laboratories is discussed. Particular reference is made to their use in analytical problems. Their flexibility is emphasised. (U.K.)

  13. Description of project for pretreatment and storage of wastes of L.P.R. (Radiochemical Processes Laboratory)

    International Nuclear Information System (INIS)

    Doval, J.C.F.; Mehlich, A.M.; Quilici, D.F.

    1987-01-01

    The aim of the project is to allow the start up and operation of LPR (Radiochemical Processes Laboratory) as part of the intended activities in the plant. In this paper, the pretreatment and storage of liquid wastes generated at the LPR are described. The pretreatment section will be set up inside the shielded cells already existent in the LPR, where a previous concentration through the evaporation of liquid wastes will take place. The storage section has to be constructed on purpose in order to temporarily store the concentrates. The cells of transference and preconditioning of solid wastes are also described. These cells will be mounted inside the building, allowing the handling of radioactive solids generated as effluents during the reprocessing plan. In the description, the use of non conventional materials for the boiler making and the construction of cells is specially mentioned. (Author)

  14. Radiochemicals

    International Nuclear Information System (INIS)

    1980-01-01

    In this catalogue those radioactive chemicals for research are listed which are produced by the Radiochemical Centre Amersham and our laboratories at Brunswick. The dates given for each product can understandably only be limited within the framework of such a catalogue. Additional dates and references to application technique can be obtained from us any time. Our programme is continually updated by new products. If a compound not listed in the catalogue should be required we ask for inquiry. Our working team for special syntheses will try to produce it according to our possibilities and our requirements. (orig.) [de

  15. Automated radiochemical processing for clinical PET

    International Nuclear Information System (INIS)

    Padgett, H.C.; Schmidt, D.G.; Bida, G.T.; Wieland, B.W.; Pekrul, E.; Kingsbury, W.G.

    1991-01-01

    With the recent emergence of positron emission tomography (PET) as a viable clinical tool, there is a need for a convenient, cost-effective source of the positron emitter-labeled radiotracers labeled with carbon-11, nitrogen-13, oxygen-15, and fluorine-18. These short-lived radioisotopes are accelerator produced and thus, require a cyclotron and radiochemistry processing instrumentation that can be operated 3 in a clinical environment by competant technicians. The basic goal is to ensure safety and reliability while setting new standards for economy and ease of operation. The Siemens Radioisotope Delivery System (RDS 112) is a fully automated system dedicated to the production and delivery of positron-emitter labeled precursors and radiochemicals required to support a clinical PET imaging program. Thus, the entire RDS can be thought of as an automated radiochemical processing apparatus

  16. Statistical processing of technological and radiochemical data

    International Nuclear Information System (INIS)

    Lahodova, Zdena; Vonkova, Kateřina

    2011-01-01

    The project described in this article had two goals. The main goal was to compare technological and radiochemical data from two units of nuclear power plant. The other goal was to check the collection, organization and interpretation of routinely measured data. Monitoring of analytical and radiochemical data is a very valuable source of knowledge for some processes in the primary circuit. Exploratory analysis of one-dimensional data was performed to estimate location and variability and to find extreme values, data trends, distribution, autocorrelation etc. This process allowed for the cleaning and completion of raw data. Then multiple analyses such as multiple comparisons, multiple correlation, variance analysis, and so on were performed. Measured data was organized into a data matrix. The results and graphs such as Box plots, Mahalanobis distance, Biplot, Correlation, and Trend graphs are presented in this article as statistical analysis tools. Tables of data were replaced with graphs because graphs condense large amounts of information into easy-to-understand formats. The significant conclusion of this work is that the collection and comprehension of data is a very substantial part of statistical processing. With well-prepared and well-understood data, its accurate evaluation is possible. Cooperation between the technicians who collect data and the statistician who processes it is also very important. (author)

  17. Decontamination and decommission of a radiochemical laboratory building complex

    International Nuclear Information System (INIS)

    Zoubek, Norbert

    2008-01-01

    Full text: Handling of unsealed radioactive substances for research and development purposes in chemical or pharmaceutical industries or research centres as well as production of radioactive substances (e.g. for applications in nuclear medicine or industry) requires operation of special radiochemical laboratories. In general, operation of radiochemical laboratories is strongly regulated by the government and national authorities. The operator needs a permit related to radiological protection. In general, technical requirements for such facilities are very high. To ensure high safety standards with respect to the employees and the environment, several radiological protection measures have to be taken. These measures (for example special shielding or ventilation and waste water systems) depend on various factors, e.g. activity in use, kind of nuclides, chemical properties and volatility of substances. In order to close-down such radiochemical laboratories some radiological protection measures have to be maintained to ensure protection of both humans and the environment induced by possible residual contaminations within the facility including technical inventory. However, a later reuse of the facility as a non-radioactive facility requires removal of all radioactive contamination with respect to national regulation. Resulting radioactive wastes have to be disposed of under control of competent authorities. Based on the experience of a decontamination and decommission project for a former radiochemical laboratory complex, the main steps necessary to release such a facility are discussed. Analytical aspects of initial conditions, necessary organisational structures within the project, resources needed estimation and exploration of the radiological situation in the laboratory, elaboration of a measuring strategy and decontamination methods as well as different waste disposal routes in relation to different waste types are reported. (author)

  18. The design of a new radiochemical laboratory complex

    International Nuclear Information System (INIS)

    Lewis, A.G.

    1984-01-01

    A brief account is given of the history and scope of Amersham International plc in the manufacture of radiopharmaceuticals and other labelled organic compounds, and radioactive sources. Extra facilities were needed and a new site was found, and contracts placed for new radiochemical laboratories. The two new laboratories, which are described in some detail, are intended as follows: (a) a Medical Products building for the production of a range of diagnostic kits for use in the treatment of thyroid and other disorders, the main isotope used being iodine-125; and (b) the Chemical Products building, for the development and manufacture of a wide range of organic compounds, which are labelled with either tritium or carbon-14. Particular emphasis is given to the description of the air conditioning and ventilation systems, the open work benches, and the special ventilated enclosures, and the drainage system. Planning for maximum flexibility is also stressed. (U.K.)

  19. Radiochemical verification and validation in the environmental data collection process

    International Nuclear Information System (INIS)

    Rosano-Reece, D.; Bottrell, D.; Bath, R.J.

    1994-01-01

    A credible and cost effective environmental data collection process should produce analytical data which meets regulatory and program specific requirements. Analytical data, which support the sampling and analysis activities at hazardous waste sites, undergo verification and independent validation before the data are submitted to regulators. Understanding the difference between verification and validation and their respective roles in the sampling and analysis process is critical to the effectiveness of a program. Verification is deciding whether the measurement data obtained are what was requested. The verification process determines whether all the requirements were met. Validation is more complicated than verification. It attempts to assess the impacts on data use, especially when requirements are not met. Validation becomes part of the decision-making process. Radiochemical data consists of a sample result with an associated error. Therefore, radiochemical validation is different and more quantitative than is currently possible for the validation of hazardous chemical data. Radiochemical data include both results and uncertainty that can be statistically compared to identify significance of differences in a more technically defensible manner. Radiochemical validation makes decisions about analyte identification, detection, and uncertainty for a batch of data. The process focuses on the variability of the data in the context of the decision to be made. The objectives of this paper are to present radiochemical verification and validation for environmental data and to distinguish the differences between the two operations

  20. Low temperature radio-chemical energy conversion processes

    International Nuclear Information System (INIS)

    Gomberg, H.J.

    1986-01-01

    This patent describes a radio-chemical method of converting radiated energy into chemical energy form comprising the steps of: (a) establishing a starting chemical compound in the liquid phase that chemically reacts endothermically to radiation and heat energy to produce a gaseous and a solid constituent of the compound, (b) irradiating the compound in its liquid phase free of solvents to chemically release therefrom in response to the radiation the gaseous and solid constituents, (c) physically separating the solid and gaseous phase constituents from the liquid, and (d) chemically processing the constituents to recover therefrom energy stored therein by the irradiation step (b)

  1. Remote sampling of process fluids in radiochemical plants

    International Nuclear Information System (INIS)

    Sengar, P.B.; Bhattacharya, R.; Ozarde, P. D.; Rana, D.S.

    1990-01-01

    Sampling of process fluids, continuous or periodic, is an essential requirement in any chemical process plant, so as to keep a control on process variables. In a radiochemical plant the task of taking and conveying the samples is a very tricky affair. This is due to the fact that neither the vessels/equipment containing radioactive effluents can be approached for manual sampling nor sampled fluids can be handled directly. The problems become more accute with higher levels of radioactivity. As such, inovative systems have to be devised to obtain and handle the raioactive samples employing remote operations. The remote sampling system developed in this Division has some of the unique features such as taking only requisite amount of samples in microlitre range, practically maintenance free design, avoidence of excess radioactive fluids coming out of process systems, etc. The paper describes in detail the design of remote sampling system and compares the same with existing systems. The design efforts are towards simplicity in operation, obtaining homogenised representative samples and highly economical on man-rem expenditure. The performance of a prototype system has also been evaluated. (author). 3 refs

  2. RAPID AUTOMATED RADIOCHEMICAL ANALYZER FOR DETERMINATION OF TARGETED RADIONUCLIDES IN NUCLEAR PROCESS STREAMS

    International Nuclear Information System (INIS)

    O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Egorov, Oleg; Devol, Timothy A.

    2008-01-01

    Some industrial process-scale plants require the monitoring of specific radionuclides as an indication of the composition of their feed streams or as indicators of plant performance. In this process environment, radiochemical measurements must be fast, accurate, and reliable. Manual sampling, sample preparation, and analysis of process fluids are highly precise and accurate, but tend to be expensive and slow. Scientists at Pacific Northwest National Laboratory (PNNL) have assembled and characterized a fully automated prototype Process Monitor instrument which was originally designed to rapidly measure Tc-99 in the effluent streams of the Waste Treatment Plant at Hanford, WA. The system is capable of a variety of tasks: extraction of a precise volume of sample, sample digestion/analyte redox adjustment, column-based chemical separations, flow-through radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results can be immediately calculated and electronically reported. It is capable of performing a complete analytical cycle in less than 15 minutes. The system is highly modular and can be adapted to a variety of sample types and analytical requirements. It exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs

  3. Hanford Environmental Restoration data validation process for chemical and radiochemical analyses

    International Nuclear Information System (INIS)

    Adams, M.R.; Bechtold, R.A.; Clark, D.E.; Angelos, K.M.; Winter, S.M.

    1993-10-01

    Detailed procedures for validation of chemical and radiochemical data are used to assure consistent application of validation principles and support a uniform database of quality environmental data. During application of these procedures, it was determined that laboratory data packages were frequently missing certain types of documentation causing subsequent delays in meeting critical milestones in the completion of validation activities. A quality improvement team was assembled to address the problems caused by missing documentation and streamline the entire process. The result was the development of a separate data package verification procedure and revisions to the data validation procedures. This has resulted in a system whereby deficient data packages are immediately identified and corrected prior to validation and revised validation procedures which more closely match the common analytical reporting practices of laboratory service vendors

  4. Radiochemical procedures

    International Nuclear Information System (INIS)

    Lyon, W.S.

    1982-01-01

    The modern counting instrumentation has largely obviated the need for separation processes in the radiochemical analysis but problems in low-level radioactivity measurement, environmental-type analyses, and special situations caused in the last years a renaissance of the need for separation techniques. Most of the radiochemical procedures, based on the classic works of the Manhattan Project chemists of the 1940's, were published in the National Nuclear Energy Series (NNES). Improvements such as new solvent extraction and ion exchange separations have been added to these methods throughout the years. Recently the Los Alamos Group have reissued their collected Radiochemical Procedures containing a short summary and review of basic inorganic chemistry - 'Chemistry of the Elements on the Basis of Electronic Configuration'. (A.L.)

  5. Elementary computation of radiation doses and shieldings for radiochemical laboratories; Calculo Elemental de dosis y blindajes para laboratorios radioquimicos

    Energy Technology Data Exchange (ETDEWEB)

    Jimeno de Osso, F

    1971-07-01

    Simple procedures for the calculation of radiation exposition, half thickness, shield thickness, etc. are described and equations and graphs are included for those gamma-emitting radionuclides, that are more often used in radiochemical laboratories. Application is made of these procedures to three radionuclides, bromine-82, sodium-24 and cobalt-60 which cover a rather wl.de energy range; theoretical results are compared with those obtained from experimental measurements. (Author) 23 refs.

  6. Analysis of accidents at the LPR (Radiochemical Processes Laboratory)

    International Nuclear Information System (INIS)

    Kaufmann, F.; Boutet, L.I.

    1987-01-01

    Accidents are defined as not planned events that may result in the emission of significative quantities of radioactive materials to the environment. The pilot plant has been specifically designed to prevent this type of accidents but there still exists the possibility that one or more accidents can be produced during the plant life. In a first phase, the emission of radionuclides to the environment were evaluated for 13 credible accidents. In a second phase, by means of the calculation program SEDA, specially adapted to this purpose, the critical doses of critical group were calculated for each accident. Due to the small capacity of the pilot plant and the long cooling period of treated fuel, it is concluded that the radiological consequences for the external environment are of very small magnitude. In this way, without need of developing complex fault- or event-trees, it is shown that any of the accidents falls into the non acceptable zone of Farmer diagram. (Author)

  7. Fuels Processing Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — NETL’s Fuels Processing Laboratory in Morgantown, WV, provides researchers with the equipment they need to thoroughly explore the catalytic issues associated with...

  8. Radiochemical procedures and techniques

    International Nuclear Information System (INIS)

    Flynn, K.

    1975-04-01

    A summary is presented of the radiochemical procedures and techniques currently in use by the Chemistry Division Nuclear Chemistry Group at Argonne National Laboratory for the analysis of radioactive samples. (U.S.)

  9. Hydrologic conditions and distribution of selected radiochemical and chemical constituents in water, Snake River Plain aquifer, Idaho National Engineering Laboratory, Idaho, 1989 through 1991

    International Nuclear Information System (INIS)

    Bartholomay, R.C.; Orr, B.R.; Liszewski, M.J.; Jensen, R.G.

    1995-08-01

    Radiochemical and chemical wastewater discharged since 1952 to infiltration ponds and disposal wells at the Idaho National Engineering Laboratory (INEL) has affected water quality in the Snake River Plain aquifer. The U.S. Geological Survey, in cooperation with the U.S. Department of Energy, maintains a continuous monitoring network at the INEL to determine hydrologic trends and to delineate the movement of radiochemical and chemical wastes in the aquifer. This report presents an analysis of water-level and water-quality data collected from the Snake River Plain aquifer during 1989-91. Water in the eastern Snake River Plain aquifer moves principally through fractures and interflow zones in basalt, generally flows southwestward, and eventually discharges at springs along the Snake River. The aquifer is recharged principally from irrigation water, infiltration of streamflow, and ground-water inflow from adjoining mountain drainage basins. Water levels in wells throughout the INEL generally declined during 1989-91 due to drought. Detectable concentrations of radiochemical constituents in water samples from wells in the Snake River Plain aquifer at the INEL decreased or remained constant during 1989-91. Decreased concentrations are attributed to reduced rates of radioactive-waste disposal, sorption processes, radioactive decay, and changes in waste-disposal practices. Detectable concentrations of chemical constituents in water from the Snake River Plain aquifer at the INEL were variable during 1989-91. Sodium and chloride concentrations in the southern part of the INEL increased slightly during 1989-91 because of increased waste-disposal rates and a lack of recharge from the Big Lost River. Plumes of 1,1,1-trichloroethane have developed near the Idaho Chemical Processing Plant and the Radioactive Waste Management Complex as a result of waste disposal practices

  10. Radiochemical guidelines and process specifications for reactor shutdown: the EDF strategy

    International Nuclear Information System (INIS)

    Mole, D.; Wintergerst, M.; Meylogan, Th.; Rocher, A.; Sagot, M.J.; Bonelli, V.; Bonnefon, J.; Dupont, B.

    2012-09-01

    Changes to French nuclear regulations made in June 2006 [1.] have made it necessary for EDF to modify its ruling principles. These modifications required the restructuring of radiochemical guidelines to better reflect their impact on nuclear safety, the environment and radioprotection. In accordance with these aims, a new authoritative document has been produced. This ruling document identifies all parameters with a potential impact on nuclear safety, radiological releases to the environment and personnel dose rates. These diagnostic and control parameters have been identified for a reactor in production and for a reactor during shutdown. For parameters related to a reactor in production, some indicators are used to evaluate impacts on availability, radioprotection and the environment during shutdown and on outage and to anticipate mitigation ways. On the other side, several parameters related to the stages of shutdown were also directly evaluated in order to minimize the impacts. This paper describes the EDF methodology used to establish operational documents: radiochemical guidelines and process specifications, and includes the following: - description of monitored parameters and their associated areas of risk; - justification of target values, frequencies of inspection and the required actions for the monitored parameters. The sizing methodology is based on theoretical studies and on EDF operational experience analysis. By implementing in the operational and technical specifications requirements linked to nuclear safety, radioprotection and environment respect, EDF will benefit from an improved compromise between these areas as well as an increased focus. (authors)

  11. Hydrologic conditions and distribution of selected radiochemical and chemical constituents in water, Snake River Plain aquifer, Idaho National Engineering Laboratory, Idaho, 1992 through 1995

    International Nuclear Information System (INIS)

    Bartholomay, R.C.; Tucker, B.J.; Ackerman, D.J.; Liszewski, M.J.

    1997-04-01

    Radiochemical and chemical wastewater discharged since 1952 to infiltration ponds and disposal wells at the Idaho National Engineering Laboratory (INEL) has affected water quality in the Snake River Plain aquifer. The US Geological Survey, in cooperation with the US Department of Energy, maintains a monitoring network at the INEL to determine hydrologic trends and to delineate the movement of radiochemical and chemical wastes in the aquifer. This report presents an analysis of water-level and water-quality data collected from the Snake River Plain aquifer during 1992--95

  12. Obtention process of phosphorus 32 starting from commercial sulfur and design and construction of the radiochemical separation prototype

    International Nuclear Information System (INIS)

    Duarte A, C.; Alanis M, J.; Gutierrez R, C.

    2002-01-01

    In this work an obtention process of phosphorus 32 ( 32 P) in orthophosphoric acid form (H 3 32 PO 4 ) is described starting from commercial sulfur. Also the design and construction of the experimental prototype used in the radiochemical separation and their results in three tests carried out is reported. (Author)

  13. Process innovation laboratory

    DEFF Research Database (Denmark)

    Møller, Charles

    2007-01-01

    to create a new methodology for developing and exploring process models and applications. The paper outlines the process innovation laboratory as a new approach to BPI. The process innovation laboratory is a comprehensive framework and a collaborative workspace for experimenting with process models....... The process innovation laboratory facilitates innovation by using an integrated action learning approach to process modelling in a controlled environment. The study is based on design science and the paper also discusses the implications to EIS research and practice......Most organizations today are required not only to operate effective business processes but also to allow for changing business conditions at an increasing rate. Today nearly every business relies on their enterprise information systems (EIS) for process integration and future generations of EIS...

  14. Radiochemical Facility Laboratory (RFL). Description of the installation and reprogramming of its objectives

    International Nuclear Information System (INIS)

    Bonini, Alberto; Dominguez, C.; Dell'Occhio, Leonor A.; Stankevicius, Alejandro

    1999-01-01

    A description is made of a laboratory that will be used to characterize radioactive wastes, to study the burnup of fuel elements, to make isotopic analysis by mass spectroscopy and to recover fissile materials from the production of fission 99 Mo. The equipment and the ventilation system are also described. (author)

  15. Radiochemical and chemical constituents in water from selected wells and springs from the southern boundary of the Idaho National Laboratory to the Hagerman Area, Idaho, 2003

    Science.gov (United States)

    Rattray, Gordon W.; Wehnke, Amy J.; Hall, L. Flint; Campbell, Linford J.

    2005-01-01

    The U.S. Geological Survey and the Idaho Department of Water Resources, in cooperation with the U.S. Department of Energy, sampled water from 14 sites as part of an ongoing study to monitor the water quality of the eastern Snake River Plain aquifer between the southern boundary of the Idaho National Laboratory (INL) and the Burley-Twin Falls-Hagerman area. The State of Idaho, Department of Environmental Quality, Division of INL Oversight and Radiation Control cosampled with the U.S. Geological Survey and the Idaho Department of Water Resources and their analytical results are included in this report. The samples were collected from four domestic wells, two dairy wells, two springs, four irrigation wells, one observation well, and one stock well and analyzed for selected radiochemical and chemical constituents. Two quality-assurance samples, sequential replicates, also were collected and analyzed. None of the concentrations of radiochemical or organic-chemical constituents exceeded the maximum contaminant levels for drinking water established by the U.S. Environmental Protection Agency. However, the concentration of one inorganic-chemical constituent, nitrate (as nitrogen), in water from site MV-43 was 20 milligrams per liter which exceeded the maximum contaminant level for that constituent. Of the radiochemical and chemical concentrations analyzed for in the replicate-sample pairs, 267 of the 270 pairs (with 95 percent confidence) were statistically equivalent.

  16. Radiochemical methods

    International Nuclear Information System (INIS)

    Geary, W.J.

    1986-01-01

    This little volume is one of an extended series of basic textbooks on analytical chemistry produced by the Analytical Chemistry by Open Learning project in the UK. Prefatory sections explain its mission, and how to use the Open Learning format. Seventeen specific sections organized into five chaptrs begin with a general discussion of nuclear properties, types, and laws of nuclear decay and proceeds to specific discussions of three published papers (reproduced in their entirety) giving examples of radiochemical methods which were discussed in the previous chapter. Each section begins with an overview, contains one or more practical problems (called self-assessment questions or SAQ's), and concludes with a summary and a list of objectives for the student. Following the main body are answers to the SAQ's, and several tables of physical constants, SI prefixes, etc. A periodic table graces the inside back cover

  17. Rapid Radiochemical Methods for Asphalt Paving Material ...

    Science.gov (United States)

    Technical Brief Validated rapid radiochemical methods for alpha and beta emitters in solid matrices that are commonly encountered in urban environments were previously unavailable for public use by responding laboratories. A lack of tested rapid methods would delay the quick determination of contamination levels and the assessment of acceptable site-specific exposure levels. Of special concern are matrices with rough and porous surfaces, which allow the movement of radioactive material deep into the building material making it difficult to detect. This research focuses on methods that address preparation, radiochemical separation, and analysis of asphalt paving materials and asphalt roofing shingles. These matrices, common to outdoor environments, challenge the capability and capacity of very experienced radiochemistry laboratories. Generally, routine sample preparation and dissolution techniques produce liquid samples (representative of the original sample material) that can be processed using available radiochemical methods. The asphalt materials are especially difficult because they do not readily lend themselves to these routine sample preparation and dissolution techniques. The HSRP and ORIA coordinate radiological reference laboratory priorities and activities in conjunction with HSRP’s Partner Process. As part of the collaboration, the HSRP worked with ORIA to publish rapid radioanalytical methods for selected radionuclides in building material matrice

  18. Polymer Processing and Characterization Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The purpose is to process and evaluate polymers for use in nonlinear optical, conductive and structural Air Force applications. Primary capabilities are extrusion of...

  19. Thermal theory of autowave processes in low-temperature solid-phase radiochemical reactions

    International Nuclear Information System (INIS)

    Barelko, V.V.; Barkalov, I.M.; Vaganov, D.A.; Zanin, A.M.; Kiryukhin, D.P.

    1982-01-01

    A new phenomenon in radiation cryochemistry concerning the class of autowave processes was previously discovered. It was observed in halogenation and hydrohalogenation of hydrocarbons and consisted of spontaneous, laminar propagation of a chemical transformation wave based on a frozen mixture of reagents previously irradiated with 60 Co γ-rays. The effect of the positive inverse correlation between the chemical conversion and brittle fracture of a solid sample of reagents is the phenomenological basis of the phenomenon; formation of fractures triggers a reactive process which takes place on their active surface (or in the layer adjacent to it), and the chemical reaction, in turn, stimulates the subsequent development of the process of decomposition. As a result, a single brittle fracture and chemical conversion wave which moves along the solid sample arises. Different mechanisms of generation of fracture surfaces under the effect of the reaction are possible. A difference in the densities of the initial reagents and the products of the reaction could be one of the causes of brittle fracture, and the thermal stresses induced by the exothermicity of the chemical processes could be another cause. The present work concerns the analysis of the features of the wave process which occurs based on the second, thermal mechanism. The analysis was conducted within the framework of a phenomenological approach which does not require specific definition of the nature of the chemical activation of the system during its brittle fracture

  20. Radiochemical characterization and environmental radiological impact in tin and lead processing from cassiterite

    International Nuclear Information System (INIS)

    Garcia, Marcia Aparecida Antico

    2009-01-01

    The tin and lead industry located in Pirapora do Bom Jesus in the state of Sao Paulo, Brazil, is responsible for the production of about 7000 ton year-1 of tin and 350 ton year-1 of lead. The raw material used in this facility is cassiterite, which presents in its composition concentrations of natural radionuclides from the uranium and thorium series up to 660 kBq kg -1 and 450 kBq kg -1 , respectively. The smelting and refining processes may lead to concentrations of these radionuclides, mainly in the precipitated dust and in slag. In the operational process, intermediate refining and final slag are obtained and are stored in piles in open air. It is estimated that the amount of waste stored is about 600000 ton. This work aims to study the environmental radiological impact of the operation of this facility and to establish its Environmental Radiological Monitoring Program. In order to accomplish this task the content of radioactivity was determined in the raw material, products, byproducts, residue, deposition pond and exhausting systems. Although in the raw material the radionuclides from the uranium and thorium series are almost in equilibrium, during the processing this equilibrium is disrupted and the radionuclides migrate according to their chemical properties. Concentrations up to 31 kBq kg -1 for 238 U, 69 kBq kg -1 for 226 Ra, 2.5 kBq kg -1 for 210 Pb, 130 kBq kg -1 for 232 Th and 120 kBq kg -1 for 228 Ra were obtained in the slag. The environmental radiological impact was established by measuring the radionuclides in the critical compartments that is the ones that may cause exposure to the public. If the residue pile is considered, the critical pathways are the internal exposition from the dust inhalation and the water ingestion, due to re suspension and dispersion of the pile dust and groundwater contamination, respectively; and external exposure due to immersion in the radioactive cloud and soil contamination. For the emission of gaseous and particulate

  1. 11th radiochemical conference

    International Nuclear Information System (INIS)

    Prasil, Z.

    1987-01-01

    The conference met in four sesions which discussed: Separation methods, Radioanalytical methods, Labelled compounds and Miscellaneous. The first session discussed extraction methods, ion exchange and chromatographic separation of radioisotopes. The second session heard papers on the application of these methods, e.g., in geochemistry, on the use of radioactive tracers in radiochemical analysis and the use of activation analysis in the determination of trace elements. The third session heard papers on the preparation of labelled organic compounds with isotopes 3 H, 14 C, radioiodine and 32 P, on the preparation of RIA kits and on the chemistry and radiopharmacology of technetium compounds. The other contributions which could not be heard in any of the three sessions discussed, e.g., the preparation of elements on the cyclotron and microtron, the production of a new 99m Tc-generator, the participation of the IAEA in processing low- and medium-level radioactive wastes, etc. (E.S.)

  2. Radiochemical and Chemical Constituents in Water from Selected Wells and Springs from the Southern Boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman Area, Idaho, 1997

    Energy Technology Data Exchange (ETDEWEB)

    R. C. Bartholomay (USGS); L. M. Williams (USGS); L. J. Campbell (Idaho Department of Water Resources)

    1998-12-01

    The U.S. Geological Survey and the Idaho Department of Water Resources, in cooperation with the U.S. Department of Energy, sampled 18 sites as part of the fourth round of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman area. Water samples were collected and analyzed for selected radiochemical and chemical constituents. The samples were collected from seven domestic wells, six irrigation wells, two springs, one dairy well, one observation well, and one stock well. Two quality-assurance samples also were collected and analyzed. None of the radiochemical or chemical constituents exceeded the established maximum contaminant levels for drinking water. Many of the radionuclide- and inorganic-constituent concentrations were greater than their respective reporting levels.

  3. Radiochemical and Chemical Constituents in Water from Selected Wells and Springs from the Southern Boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman Area, Idaho, 1998

    Energy Technology Data Exchange (ETDEWEB)

    R. C. Bartholomay; B. V. Twining (USGS); L. J. Campbell (Idaho Department of Water Resources)

    1999-06-01

    The U.S. Geological Survey and the Idaho Department of Water Resources, in cooperation with the U.S. Department of Energy, sampled 18 sites as part of the fourth round of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman area. The samples were analyzed for selected radiochemical and chemical constituents. The samples were collected from 2 domestic wells, 12 irrigation wells, 2 stock wells, 1 spring, and 1 public supply well. Two quality-assurance samples also were collected and analyzed. None of the reported radiochemical or chemical constituent concentrations exceeded the established maximum contaminant levels for drinking water. Many of the radionuclide- and inorganic-constituent concentrations were greater than the respective reporting levels. Most of the organic-constituent concentrations were less than the reporting levels.

  4. An update of the distribution of selected radiochemical and chemical constituents in perched ground water, Idaho National Laboratory, Idaho, Emphasis 1999-2001

    Science.gov (United States)

    Davis, Linda C.

    2006-01-01

    Radiochemical and chemical wastes generated at facilities at the Idaho National Laboratory (INL) were discharged since 1952 to infiltration ponds at the Reactor Technology Complex (RTC) (known as the Test Reactor Area [TRA] until 2005), and the Idaho Nuclear Technology and Engineering Center (INTEC) and buried at the Radioactive Waste Management Complex (RWMC). Disposal of wastewater to infiltration ponds and infiltration of surface water at waste burial sites resulted in formation of perched ground water in basalts and in sedimentary interbeds above the Snake River Plain aquifer. Perched ground water is an integral part of the pathway for waste-constituent migration to the aquifer. The U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, maintains ground-water monitoring networks at the INL to determine hydrologic trends, and to monitor the movement of radiochemical and chemical constituents in wastewater discharged from facilities to both perched ground water and the aquifer. This report presents an analysis of water-quality and water-level data collected from wells completed in perched ground water at the INL during 1999-2001, and summarizes historical disposal data and water-level-and water-quality trends. At the RTC, tritium, strontium-90, cesium-137, dissolved chromium, chloride, sodium, and sulfate were monitored in shallow and deep perched ground water. In shallow perched ground water, no tritium was detected above the reporting level. In deep perched ground water, tritium concentrations generally decreased or varied randomly during 1999-2001. During October 2001, tritium concentrations ranged from less than the reporting level to 39.4?1.4 picocuries per milliliter (pCi/mL). Reportable concentrations of tritium during July-October 2001 were smaller than the reported concentrations measured during July-December 1998. Tritium concentrations in water from wells at the RTC were likely affected by: well's distance from the

  5. The Laboratory for Advanced Materials Processing

    Data.gov (United States)

    Federal Laboratory Consortium — The Laboratory for Advanced Materials Processing - LAMP - is a clean-room research facility run and operated by Pr. Gary Rubloff's group. Research activities focus...

  6. Data Processing and Programming Applied to an Environmental Radioactivity Laboratory

    International Nuclear Information System (INIS)

    Trinidad, J. A.; Gasco, C.; Palacios, M. A.

    2009-01-01

    This report is the original research work presented for the attainment of the author master degree and its main objective has been the resolution -by means of friendly programming- of some of the observed problems in the environmental radioactivity laboratory belonging to the Department of Radiological Surveillance and Environmental Radioactivity from CIEMAT. The software has been developed in Visual Basic for applications in Excel files and it solves by macro orders three of the detected problems: a) calculation of characteristic limits for the measurements of the beta total and beta rest activity concentrations according to standards MARLAP, ISO and UNE and the comparison of the three results b) Pb-210 and Po-210 decontamination factor determination in the ultra-low level Am-241 analysis in air samples by alpha spectrometry and c) comparison of two analytical techniques for measuring Pb-210 in air ( direct-by gamma spectrometry- and indirect -by radiochemical separation and alpha spectrometry). The organization processes of the different excel files implied in the subroutines, calculations and required formulae are explained graphically for its comprehension. The advantage of using this kind of programmes is based on their versatility and the ease for obtaining data that lately are required by tables that can be modified as time goes by and the laboratory gets more data with the special applications for describing a method (Pb-210 decontamination factors for americium analysis in air) or comparing temporal series of Pb-210 data analysed by different methods (Pb-210 in air). (Author)

  7. On-Line Monitoring for Process Control and Safeguarding of Radiochemical Streams at Spent Fuel Reprocessing Plants

    International Nuclear Information System (INIS)

    Bryan, S.; Levitskaia, T.; Casella, A.

    2015-01-01

    The International Atomic Energy Agency (IAEA) has established international safe- guards standards for fissionable material at spent nuclear fuel reprocessing plants to ensure that significant quantities of weapons-grade nuclear material are not diverted from these facilities. Currently, methods to verify material control and accountancy (MC&A) at these facilities require time-consuming and resource-intensive destructive assay (DA). Leveraging new on-line non-destructive assay (NDA) techniques in conjunction with the traditional and highly precise DA methods may provide a more timely, cost-effective and resource-efficient means for MC&A verification at such facilities. Pacific Northwest National Laboratory (PNNL) is developing on-line NDA process monitoring technologies, including a spectroscopy-based monitoring system, to potentially reduce the time and re- source burden associated with current techniques. The spectroscopic monitor continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major cold flowsheet chemicals using ultra-violet and visible, near infrared and Raman spectroscopy. This paper will provide an overview of the methods and report our on-going efforts to develop and demonstrate the technologies. Our ability to identify material intentionally diverted from a liquid-liquid solvent extraction contactor system was successfully tested using on-line process monitoring as a means to detect the amount of material diverted. A chemical diversion, and detection of that diversion, from a solvent extraction scheme was demonstrated using a centrifugal contactor system operating with the PUREX flowsheet. A portion of the feed from a counter-current extraction system was diverted while a continuous extraction experiment was underway. The amount observed to be diverted by on-line spectroscopic process monitoring was in excellent agreement with values based from the known mass of

  8. Safety assessment for TA-48 radiochemical operations

    International Nuclear Information System (INIS)

    1994-08-01

    The purpose of this report is to document an assessment performed to evaluate the safety of the radiochemical operations conducted at the Los Alamos National Laboratory operations area designated as TA-48. This Safety Assessment for the TA-48 radiochemical operations was prepared to fulfill the requirements of US Department of Energy (DOE) Order 5481.1B, ''Safety Analysis and Review System.'' The area designated as TA-48 is operated by the Chemical Science and Technology (CST) Division and is involved with radiochemical operations associated with nuclear weapons testing, evaluation of samples collected from a variety of environmental sources, and nuclear medicine activities. This report documents a systematic evaluation of the hazards associated with the radiochemical operations that are conducted at TA-48. The accident analyses are limited to evaluation of the expected consequences associated with a few bounding accident scenarios that are selected as part of the hazard analysis. Section 2 of this report presents an executive summary and conclusions, Section 3 presents pertinent information concerning the TA-48 site and surrounding area, Section 4 presents a description of the TA-48 radiochemical operations, and Section 5 presents a description of the individual facilities. Section 6 of the report presents an evaluation of the hazards that are associated with the TA-48 operations and Section 7 presents a detailed analysis of selected accident scenarios

  9. Radiochemical and Chemical Constituents in Water from Selected Wells and Springs from the Southern Boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman Area, Idaho, 2002

    Science.gov (United States)

    Rattray, Gordon W.; Campbell, Linford J.

    2004-01-01

    The U.S. Geological Survey, Idaho Department of Water Resources, and the State of Idaho INEEL Oversight Program, in cooperation with the U.S. Department of Energy, sampled water from 17 sites as part of the sixth round of a long-term project to monitor water quality of the eastern Snake River Plain aquifer from the southern boundary of the Idaho National Engineering and Environmental Laboratory to the Hagerman area. The samples were collected from eight irrigation wells, three domestic wells, one stock well, one dairy well, one commercial well, one observation well, and two springs and analyzed for selected radiochemical and chemical constituents. One quality-assurance sample, a sequential replicate, also was collected and analyzed. Many of the radionuclide and inorganic-constituent concentrations were greater than the reporting levels and most of the organic-constituent concentrations were less than the reporting levels. However, none of the reported radiochemical- or chemical-constituent concentrations exceeded the maximum contaminant levels for drinking water established by the U.S. Environmental Protection Agency. Statistical evaluation of the replicate sample pair indicated that, with 95 percent confidence, 132 of the 135 constituent concentrations of the replicate pair were equivalent.

  10. Obtention process of phosphorus 32 starting from commercial sulfur and design and construction of the radiochemical separation prototype; Proceso de obtencion de fosforo-32 a partir de azufre comercial y diseno y construccion del prototipo de separacion radioquimica

    Energy Technology Data Exchange (ETDEWEB)

    Duarte A, C.; Alanis M, J.; Gutierrez R, C. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    In this work an obtention process of phosphorus 32 ({sup 32} P) in orthophosphoric acid form (H{sub 3}{sup 32}PO{sub 4}) is described starting from commercial sulfur. Also the design and construction of the experimental prototype used in the radiochemical separation and their results in three tests carried out is reported. (Author)

  11. Radiochemical solar neutrino experiments

    International Nuclear Information System (INIS)

    Rich, R.; Spiro, M.

    1993-01-01

    This review covers the three presently running radiochemical solar neutrino experiments, namely the Chlorine, SAGE, and GALLEX experiments. The focus of the review is on a discussion of statistical consistency checks of the available data. The chlorine radiochemical experiment is conceptually simple and shows no strong indication of any statistical anomalies. It still forms the basis of the solar neutrino problem. Each of the two gallium experiments show internal statistical consistency. SAGE's recent preliminary results are consistent with the published GALLEX results. If this convergence is confirmed by a more definitive analysis, this would suggest that the combined result of the two gallium experiments, SAGE and GALLEX, be used for comparisons with theoretical expectations. 5 refs., 15 figs

  12. Radiochemical Solar Neutrino Experiments - Successful and Otherwise

    International Nuclear Information System (INIS)

    Hahn, R.L.

    2008-01-01

    Over the years, several different radiochemical systems have been proposed as solar neutrino detectors. Of these, two achieved operating status and obtained important results that helped to define the current field of neutrino physics: the first solar-neutrino experiment, the Chlorine Detector ( 37 Cl) that was developed by chemist Raymond Davis and colleagues at the Homestake Mine, and the subsequent Gallium ( 71 Ga) Detectors that were operated by (a) the SAGE collaboration at the Baksan Laboratory and (b) the GALLEX/GNO collaborations at the Gran Sasso National Laboratory. These experiments have been extensively discussed in the literature and in many previous International Neutrino Conferences. In this paper, I present important updates to the results from SAGE and GALLEX/GNO. I also review the principles of the radiochemical detectors and briefly describe several different detectors that have been proposed. In light of the well-known successes that have been subsequently obtained by real-time neutrino detectors such as Kamiokande, Super-Kamiokande, SNO, and KamLAND, I do not anticipate that any new radiochemical neutrino detectors will be built. At present, only SAGE is still operating; the Chlorine and GNO radiochemical detectors have been decommissioned and dismantled

  13. Radiochemical solar neutrino experiments, 'successful and otherwise'

    International Nuclear Information System (INIS)

    Hahn, Richard L

    2008-01-01

    Over the years, several different radiochemical systems have been proposed as solar neutrino detectors. Of these, two achieved operating status and obtained important results that helped to define the current field of neutrino physics: the first solar-neutrino experiment, the Chlorine Detector ( 37 Cl) that was developed by chemist Raymond Davis and colleagues at the Homestake Mine, and the subsequent Gallium ( 71 Ga) Detectors that were operated by (a) the SAGE collaboration at the Baksan Laboratory and (b) the GALLEX/GNO collaborations at the Gran Sasso National Laboratory. These experiments have been extensively discussed in the literature and in many previous International Neutrino Conferences. In this paper, I present important updates to the results from SAGE and GALLEX/GNO. I also review the principles of the radiochemical detectors and briefly describe several different detectors that have been proposed. In light of the well-known successes that have been subsequently obtained by real-time neutrino detectors such as Kamiokande, Super-Kamiokande, SNO, and KamLAND, I do not anticipate that any new radiochemical neutrino detectors will be built. At present, only SAGE is still operating; the Chlorine and GNO radiochemical detectors have been decommissioned and dismantled.

  14. Methods and Production of Cementation Materials for Immobilisation into Waste Form. Research of Cementation Processes for Specific Liquid Radioactive Waste Streams of Radiochemical Plants

    International Nuclear Information System (INIS)

    Sukhanov, L.P.

    2013-01-01

    In the near future Russian Federation is planning to use industrial cementation facilities at two radiochemical combines - PA 'Mayak' and Mountain Chemical Combine. Scope of the research within the IAEA CRP contact No. 14176 included the development of cementation processes for specfic liquid radioactive waste streams that are present in these enterprisers. The research on cementation of liquid waste from spent nuclear fuel reprocessing at PA 'Mayak' allowed obtaining experimental data characterizing the technological process and basic characteristics of the produced cement compounds (e.g. mechanical strength, water resistance, frost resistance, flowability, etc.) immobilizing different streams of waste (e.g. hydrated-salt sludges, filter material pulps, mixture of hydrated salt slurries and filter material pulps, tritium liquid waste). Determined optimum technological parameters will allow industrial scale production of cement compound with required quality and higher flowability that is necessary for providing uniform filling of compartments of storage facilities at these sites. The research has been also carried out for the development of cementation technology for immobilization of pulps from storage tanks of Mountain Chemical Combine radiochemical plant. Cementation of such pulps is a difficult technological task because pulps are of complex chemical composition (e.g. hydroxides of manganese, iron, nickel, etc., as well as silicon oxide) and a relatively high activity. The research of cementation process selection for these pulps included studies of the impact of sorbing additive type and content on cement compounds leachability, flowability, impact of cement compound age to its mechanical strength, heat generation of cement compounds and others. The research results obtained allowed testing of cementation facility with a pulse type mixer on the full-scale. Use of such mixer for pulp cementation makes possible to prepare a homogeneous cement compound with the

  15. Methods for training radiochemical technicians at ORNL

    International Nuclear Information System (INIS)

    Parrott, J.R.; Nicol, R.G.

    The training of personnel to carry out radiochemical operations at ORNL is a formidable and recurrent task since programs are constantly shifting. It is essential that provisions be made for the routine retraining of these personnel if they are to make effective contributions on a continuing basis. Training methods are described that have emerged as a result of thirty years experience in a variety of radiochemical pilot-plant programs. Emphasis is placed on training programs for technicians for the 233 U Processing Facility since essentially all aspects of radiochemical operations are encountered in this facility. These programs have included operations performed in glove boxes, hot-cell manipulator work handling high-neutron-emitting isotopes, and the entire spectrum of remote solvent extraction operations. (U.S.)

  16. Process waste assessment for the Radiography Laboratory

    International Nuclear Information System (INIS)

    Phillips, N.M.

    1994-07-01

    This Process Waste Assessment was conducted to evaluate the Radiography Laboratory, located in Building 923. It documents the processes, identifies the hazardous chemical waste streams generated by these processes, recommends possible ways to minimize waste, and serves as a reference for future assessments of this facility. The Radiography Laboratory provides film radiography or radioscopy (electronic imaging) of weapon and nonweapon components. The Radiography Laboratory has six x-ray machines and one gamma ray source. It also has several other sealed beta- and gamma-ray isotope sources of low microcurie (μCi) activity. The photochemical processes generate most of the Radiography Laboratory's routinely generated hazardous waste, and most of that is generated by the DuPont film processor. Because the DuPont film processor generates the most photochemical waste, it was selected for an estimated material balance

  17. Radiochemicals in biomedical research

    International Nuclear Information System (INIS)

    Evans, E.A.; Oldham, K.G.

    1988-01-01

    This volume describes the role of radiochemicals in biomedical research, as tracers in the development of new drugs, their interaction and function with receptor proteins, with the kinetics of binding of hormone - receptor interactions, and their use in cancer research and clinical oncology. The book also aims to identify future trends in this research, the main objective of which is to provide information leading to improvements in the quality of life, and to give readers a basic understanding of the development of new drugs, how they function in relation to receptor proteins and lead to a better understanding of the diagnosis and treatment of cancers. (author)

  18. Handling of Ammonium Nitrate Mother-Liquid Radiochemical Production - 13089

    International Nuclear Information System (INIS)

    Zherebtsov, Alexander; Dvoeglazov, Konstantine; Volk, Vladimir; Zagumenov, Vladimir; Zverev, Dmitriy; Tinin, Vasiliy; Kozyrev, Anatoly; Shamin, Dladimir; Tvilenev, Konstantin

    2013-01-01

    The aim of the work is to develop a basic technology of decomposition of ammonium nitrate stock solutions produced in radiochemical enterprises engaged in the reprocessing of irradiated nuclear fuel and fabrication of fresh fuel. It was necessary to work out how to conduct a one-step thermal decomposition of ammonium nitrate, select and test the catalysts for this process and to prepare proposals for recycling condensation. Necessary accessories were added to a laboratory equipment installation decomposition of ammonium nitrate. It is tested several types of reducing agents and two types of catalyst to neutralize the nitrogen oxides. It is conducted testing of modes of the process to produce condensation, suitable for use in the conversion of a new technological scheme of production. It is studied the structure of the catalysts before and after their use in a laboratory setting. It is tested the selected catalyst in the optimal range for 48 hours of continuous operation. (authors)

  19. Defense Waste Processing Facility prototypic analytical laboratory

    International Nuclear Information System (INIS)

    Policke, T.A.; Bryant, M.F.; Spencer, R.B.

    1991-01-01

    The Defense Waste Processing Technology (DWPT) Analytical Laboratory is a relatively new laboratory facility at the Savannah River Site (SRS). It is a non-regulated, non-radioactive laboratory whose mission is to support research and development (R ampersand D) and waste treatment operations by providing analytical and experimental services in a way that is safe, efficient, and produces quality results in a timely manner so that R ampersand D personnel can provide quality technical data and operations personnel can efficiently operate waste treatment facilities. The modules are sample receiving, chromatography I, chromatography II, wet chemistry and carbon, sample preparation, and spectroscopy

  20. Radiochemical synthesis of etomoxir

    Energy Technology Data Exchange (ETDEWEB)

    Abbas, Hafiz G. [Institute of Nuclear Medicine and Oncology (INMOL), New Campus Road, Lahore (Pakistan); Yunus, M. [University of the Punjab, New Campus Road, Lahore (Pakistan); Feinendegen, Ludwig E., E-mail: feinendegen@gmx.ne [Department of Nuclear Medicine, Heinrich-Heine University Duesseldorf, Wannental 45, 88131 Lindau (Germany)

    2011-02-15

    Sodium 2-{l_brace}6-(4-chlorophenoxy)hexyl{r_brace}oxirane-2-carboxylate (Etomoxir) inhibits transport of fatty acids via the carnitine shuttle into mitochondria of muscle cells and prevents long chain fatty acids from providing energy through {beta}-oxidation especially for muscle contraction. The objective of this synthesis is to develop a method for radioiodination of Etomoxir in order to explore its potential in diagnostic metabolic studies and molecular imaging. Thus, a method is described for the radiochemical synthesis and purification of ethyl 2-{l_brace}6-(4-[{sup 131}I]iodophenoxy)hexyl{r_brace}oxirane-2-carboxylate (3) and 2-{l_brace}6-(4-[{sup 131}I]iodo-phenoxy)hexyl{r_brace}oxirane-2-carboxylic acid (4). For the synthesis of these new agents, ethyl 2-{l_brace}6-(4-bromophenoxy)hexyl{r_brace}oxirane-2-carboxylate (1) and 2-{l_brace}6-(4-bromophenoxy)hexyl{r_brace}oxirane-2-carboxylic acid (2) were refluxed with [{sup 131}I]NaI in the presence of anhydrous acetone at a temperature of 80 {sup o}C and 90 {sup o}C for a period of 3-4 hours, respectively. The method of radiolabeling, based on the nucleophilic exchange reaction, resulted in a radiochemical yield of 43% and 67% for compounds 3 and 4, respectively. This paper reports on the labeling of etomoxir with radioiodine as {sup 124}I labeled etomoxir may be of great importance in molecular imaging.

  1. The publication lapse of papers in Radiochemical and Radioanalytical Letters

    International Nuclear Information System (INIS)

    Braun, T.; Nagydiosi-Kocsis, Gy.

    1982-01-01

    The time needed for passing through journal editorial and publication processing has been examined for the papers published in Radiochemical and Radioanalytical Letters for the years 1969-1981. (author)

  2. Collected radiochemical and geochemical procedures

    Energy Technology Data Exchange (ETDEWEB)

    Kleinberg, J [comp.

    1990-05-01

    This revision of LA-1721, 4th Ed., Collected Radiochemical Procedures, reflects the activities of two groups in the Isotope and Nuclear Chemistry Division of the Los Alamos National Laboratory: INC-11, Nuclear and radiochemistry; and INC-7, Isotope Geochemistry. The procedures fall into five categories: I. Separation of Radionuclides from Uranium, Fission-Product Solutions, and Nuclear Debris; II. Separation of Products from Irradiated Targets; III. Preparation of Samples for Mass Spectrometric Analysis; IV. Dissolution Procedures; and V. Geochemical Procedures. With one exception, the first category of procedures is ordered by the positions of the elements in the Periodic Table, with separate parts on the Representative Elements (the A groups); the d-Transition Elements (the B groups and the Transition Triads); and the Lanthanides (Rare Earths) and Actinides (the 4f- and 5f-Transition Elements). The members of Group IIIB-- scandium, yttrium, and lanthanum--are included with the lanthanides, elements they resemble closely in chemistry and with which they occur in nature. The procedures dealing with the isolation of products from irradiated targets are arranged by target element.

  3. Evaluation of radiochemical data usability

    International Nuclear Information System (INIS)

    Paar, J.G.; Porterfield, D.R.

    1997-04-01

    This procedure provides a framework for implementation of radiochemical data verification and validation for environmental remediation activities. It has been developed through participation of many individuals currently involved in analytical radiochemistry, radiochemical validation, and validation program development throughout the DOE complex. It should be regarded as a guidance to use in developing an implementable radiochemical validation strategy. This procedure provides specifications for developing and implementing a radiochemical validation methodology flexible enough to allow evaluation of data useability for project-specific Data Quality Objectives (DQO). Data produced by analytical methods for which this procedure provides limited guidance are classified as open-quotes non-routineclose quotes radionuclides and methods, and analyses by these methods may necessitate adoption of modified criteria from this procedure

  4. Chemical and Radiochemical Constituents in Water from Wells in the Vicinity of the Naval Reactors Facility, Idaho National Engineering and Environmental Laboratory, Idaho, 1997-98

    Energy Technology Data Exchange (ETDEWEB)

    R. C. Bartholomay; L. L. Knobel; B. J. Tucker; B. V. Twining (USGS)

    2000-06-01

    The US Geological Survey, in response to a request from the U.S Department of Energy's Pittsburgh Naval Reactors Office, Idaho Branch Office, sampled water from 13 wells during 1997-98 as part of a long-term project to monitor water quality of the Snake River Plain aquifer in the vicinity of the Naval Reactors Facility, Idaho National Engineering and Environmental Laboratory, Idaho. Water samples were analyzed for naturally occurring constituents and man-made contaminants. A total of 91 samples were collected from the 13 monitoring wells. The routine samples contained detectable concentrations of total cations and dissolved anions, and nitrite plus nitrate as nitrogen. Most of the samples also had detectable concentrations of gross alpha- and gross beta-particle radioactivity and tritium. Fourteen quality-assurance samples were also collected and analyzed; seven were field-blank samples, and seven were replicate samples. Most of the field blank samples contained less than detectable concentrations of target constituents; however some blank samples did contain detectable concentrations of calcium, magnesium, barium, copper, manganese, nickel, zinc, nitrite plus nitrate, total organic halogens, tritium, and selected volatile organic compounds.

  5. Proficiency test on determination of radioactivity concentration of 137Cs and 90Ssr in food and environmental samples for Polish radiochemical laboratories

    International Nuclear Information System (INIS)

    Polkowska-Motrenko, H.; Sypula, M.; Sadowska-Bratek, M.; Fuks, L.

    2007-01-01

    Proficiency testing (PT) on the determination of radioactivity concentration of 137 Cs and 0S r in samples of drinking and surface waters, wheat flour and sand was organized in 2006 by the Institute of Nuclear Chemistry and Technology (INCT). The PT was conducted on the request of the National Atomic Energy Agency, Poland (PAA) and financed by the NAEA President. Report presents statistical evaluation of results obtained by the participants. The PT was provided in accordance with ISO/IEC Guide 43-1:1997. Samples were prepared by spiking the appropriate raw materials separately with known amounts of the certified standard solutions of 137 Cs and 0S r. Ten laboratories from Poland and one from Hungary took part in the PT. The participants were asked to choose which samples they were willing to analyze. the results provided by the participants were statistically evaluated by means of z and zeta-scores in accordance with ISO 13528:2005 and IUPAC protocol. They were evaluated also using the evaluation criteria for trueness and precision usually applied by the International Atomic Energy Agency (IAEA). (authors) [pl

  6. Radiochemical and instrumental neutron activation analysis - recent trends

    International Nuclear Information System (INIS)

    Dams, R.

    1990-01-01

    Recent trends of radiochemical and instrumental neutron activation analysis are discussed. Novel developments include the application of cyclic and pulsed activation, better energy resolution with hyperpure germanium detectors, and use of pulse processing systems allowing extremely high count rates of very short-lived isotopes. Further development is anticipated in the field of speciation in biological and environmental studies. Radiochemical methods have led to accurate determinations at the ng/g level. A promising future is expected for neutron activation techniques. (orig.)

  7. Correlation between basalt flows and radiochemical and chemical constituents in selected wells in the southwestern part of the Idaho National Laboratory, Idaho

    Science.gov (United States)

    Bartholomay, Roy C.; Hodges, Mary K. V.; Champion, Duane E.

    2017-12-21

    Wastewater discharged to wells and ponds and wastes buried in shallow pits and trenches at facilities at the Idaho National Laboratory (INL) have contributed contaminants to the eastern Snake River Plain (ESRP) aquifer in the southwestern part of the INL. This report describes the correlation between subsurface stratigraphy in the southwestern part of the INL with information on the presence or absence of wastewater constituents to better understand how flow pathways in the aquifer control the movement of wastewater discharged at INL facilities. Paleomagnetic inclination was used to identify subsurface basalt flows based on similar inclination measurements, polarity, and stratigraphic position. Tritium concentrations, along with other chemical information for wells where tritium concentrations were lacking, were used as an indicator of which wells were influenced by wastewater disposal.The basalt lava flows in the upper 150 feet of the ESRP aquifer where wastewater was discharged at the Idaho Nuclear Technology and Engineering Center (INTEC) consisted of the Central Facilities Area (CFA) Buried Vent flow and the AEC Butte flow. At the Advanced Test Reactor (ATR) Complex, where wastewater would presumably pond on the surface of the water table, the CFA Buried Vent flow probably occurs as the primary stratigraphic unit present; however, AEC Butte flow also could be present at some of the locations. At the Radioactive Waste Management Complex (RWMC), where contamination from buried wastes would presumably move down through the unsaturated zone and pond on the surface of the water table, the CFA Buried Vent; Late Basal Brunhes; or Early Basal Brunhes basalt flows are the flow unit at or near the water table in different cores.In the wells closer to where wastewater disposal occurred at INTEC and the ATR-Complex, almost all the wells show wastewater influence in the upper part of the ESRP aquifer and wastewater is present in both the CFA Buried Vent flow and AEC Butte

  8. Fifty years of radiochemical tracers

    International Nuclear Information System (INIS)

    Evans, E.A.

    1992-01-01

    During the past 50 years radiochemical tracers, usually in the form of isotopically labelled organic compounds, have been essential tools to further advance our knowledge at the frontiers of a great variety of scientific developments in the life sciences. This plenary lecture reviews necessarily selected highlights in the synthesis and applications of such radiochemical tracers. Included are examples where important advances, made possible by using radiochemicals, have contributed to improving the quality of life on this planet. The principal radioisotopes involved, 14 C, 3 H, 35 S, 32 P, 125 I, are all relatively safe to handle and are commercially available at maximum theoretical specific activity (carrier free). The compounds labeled with these radioisotopes are used in many fields of research which include biosynthesis and biotechnology studies, cell biology, drug metabolism, clinical research and environmental applications, and are briefly reviewed. (author). 55 refs

  9. Business Process Innovation using the Process Innovation Laboratory

    DEFF Research Database (Denmark)

    Møller, Charles

    for practical applications has not been identified. The aim of this paper is to establish a conceptual framework for business process innovation in the supply chain based on advanced enterprise systems. The main approach to business process innovation in this context is to create a new methodology for exploring...... process models and patterns of applications. The paper thus presents a new concept for business process innovation called the process innovation laboratory a.k.a. the ?-Lab. The ?-Lab is a comprehensive framework for BPI using advanced enterprise systems. The ?-Lab is a collaborative workspace...... for experimenting with process models and an explorative approach to study integrated modeling in a controlled environment. The ?-Lab facilitates innovation by using an integrated action learning approach to process modeling including contemporary technological, organizational and business perspectives....

  10. Software Engineering Laboratory (SEL) cleanroom process model

    Science.gov (United States)

    Green, Scott; Basili, Victor; Godfrey, Sally; Mcgarry, Frank; Pajerski, Rose; Waligora, Sharon

    1991-01-01

    The Software Engineering Laboratory (SEL) cleanroom process model is described. The term 'cleanroom' originates in the integrated circuit (IC) production process, where IC's are assembled in dust free 'clean rooms' to prevent the destructive effects of dust. When applying the clean room methodology to the development of software systems, the primary focus is on software defect prevention rather than defect removal. The model is based on data and analysis from previous cleanroom efforts within the SEL and is tailored to serve as a guideline in applying the methodology to future production software efforts. The phases that are part of the process model life cycle from the delivery of requirements to the start of acceptance testing are described. For each defined phase, a set of specific activities is discussed, and the appropriate data flow is described. Pertinent managerial issues, key similarities and differences between the SEL's cleanroom process model and the standard development approach used on SEL projects, and significant lessons learned from prior cleanroom projects are presented. It is intended that the process model described here will be further tailored as additional SEL cleanroom projects are analyzed.

  11. Radiochemical analysis for nuclear waste management in decommissioning

    International Nuclear Information System (INIS)

    Hou, X.

    2010-07-01

    The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

  12. Radiochemical analysis for nuclear waste management in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Hou, X. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy. Radiation Research Div., Roskilde (Denmark))

    2010-07-15

    The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

  13. Artificial intelligence in the materials processing laboratory

    Science.gov (United States)

    Workman, Gary L.; Kaukler, William F.

    1990-01-01

    Materials science and engineering provides a vast arena for applications of artificial intelligence. Advanced materials research is an area in which challenging requirements confront the researcher, from the drawing board through production and into service. Advanced techniques results in the development of new materials for specialized applications. Hand-in-hand with these new materials are also requirements for state-of-the-art inspection methods to determine the integrity or fitness for service of structures fabricated from these materials. Two problems of current interest to the Materials Processing Laboratory at UAH are an expert system to assist in eddy current inspection of graphite epoxy components for aerospace and an expert system to assist in the design of superalloys for high temperature applications. Each project requires a different approach to reach the defined goals. Results to date are described for the eddy current analysis, but only the original concepts and approaches considered are given for the expert system to design superalloys.

  14. Determination of radiochemical purity using gas chromatography

    International Nuclear Information System (INIS)

    1975-01-01

    The concepts of chromatography, gas chromatography, activity, radiochemical impurity are defined; the procedure of the application of gas chromatography for detecting radiochemical purity of substances is standardized. (E.F.)

  15. Processing laboratory of radio sterilized biological tissues

    International Nuclear Information System (INIS)

    Aguirre H, Paulina; Zarate S, Herman; Silva R, Samy; Hitschfeld, Mario

    2005-01-01

    The nuclear development applications have also reached those areas related to health. The risk of getting contagious illnesses through applying biological tissues has been one of the paramount worries to be solved since infectious illnesses might be provoked by virus, fungis or bacterias coming from donors or whether they have been introduced by means of intermediate stages before the use of these tissues. Therefore it has been concluded that the tissue allografts must be sterilized. The sterilization of medical products has been one of the main applications of the ionizing radiations and that it is why the International Organization of Atomic Energy began in the 70s promoting works related to the biological tissue sterilization and pharmaceutical products. The development of different tissue preservation methods has made possible the creation of tissue banks in different countries, to deal with long-term preservation. In our country, a project was launched in 1998, 'Establishment of a Tissue Bank in Latino america', this project was supported by the OIEA through the project INT/ 6/ 049, and was the starting of the actual Processing Laboratory of Radioesterilized Biological Tissues (LPTR), leaded by the Chilean Nuclear Energy Commission (CCHEN). This first organization is part of a number of entities compounding the Tissue Bank in Chile, organizations such as the Transplantation Promotion Corporation hospitals and the LPTR. The working system is carried out by means of the interaction between the hospitals and the laboratory. The medical professionals perform the procuring of tissues in the hospitals, then send them to the LPTR where they are processed and sterilized with ionizing radiation. The cycle ends up with the tissues return released to the hospitals, where they are used, and then the result information is sent to the LPTR as a form of feedback. Up to now, human skin has been processed (64 donors), amniotic membranes (35 donors) and pig skin (175 portions

  16. Hanford radiochemical site decommissioning demonstration program

    International Nuclear Information System (INIS)

    Nelson, D.C.

    1971-01-01

    A program is proposed for the innovation, development, and demonstration of technologies necessary to decommission the Hanford radiochemical plant area to the extent that the sites can have unrestricted public access. The five tasks selected for development and demonstration of restoration techniques were restoration of a burial ground, decommissioning of a separations plant, restoration of a separations plant waste interim storage tank farm, restoration of a liquid disposal area, and disposal of large contaminated equipment. Process development requirements are tabulated and discussed. A proposed schedule and estimated costs are given

  17. An overview of the status of radiochemical analysis in Hungary

    International Nuclear Information System (INIS)

    Solymosi, J.; Toth, G.

    1994-01-01

    This overview covers the following activities at radioanalytical laboratories in Hungary: tracer techniques and their applications; some important new results; radioimmunoassay; x-ray emission analysis and x-ray fluorescence analysis, Moessbauer-spectroscopy and their applications in various fields of science and technology; neutron activation analysis; radiochemical analysis for nuclear power plant applications activities in various laboratories; nuclear environmental analysis (radioanalytical methods for the investigation of contamination by nuclear facilities). (N.T.) 1 fig.; 7 tabs

  18. Pinellas Plant facts. [Products, processes, laboratory facilities

    Energy Technology Data Exchange (ETDEWEB)

    1986-09-01

    This plant was built in 1956 in response to a need for the manufacture of neutron generators, a principal component in nuclear weapons. The neutron generators consist of a miniaturized linear ion accelerator assembled with the pulsed electrical power supplies required for its operation. The ion accelerator, or neutron tube, requires ultra clean, high vacuum technology: hermetic seals between glass, ceramic, glass-ceramic, and metal materials: plus high voltage generation and measurement technology. The existence of these capabilities at the Pinellas Plant has led directly to the assignment of the lightning arrester connector, specialty capacitor, vacuum switch, and crystal resonator. Active and reserve batteries and the radioisotopically-powered thermoelectric generator draw on the materials measurement and controls technologies which are required to ensure neutron generator life. A product development and production capability in alumina ceramics, cermet (electrical) feedthroughs, and glass ceramics has become a specialty of the plant; the laboratories monitor the materials and processes used by the plant's commercial suppliers of ferroelectric ceramics. In addition to the manufacturing facility, a production development capability is maintained at the Pinellas Plant.

  19. ESOL facility for the generation and radiochemical separation of short half-life fission products

    International Nuclear Information System (INIS)

    Gehrke, R.J.; Meikrantz, D.H.; Baker, J.D.; Anderl, R.A.; Novick, V.J.; Greenwood, R.C.

    1988-01-01

    A facility has been developed at the Idaho National Engineering Laboratory (INEL) for the generation and rapid radiochemical separation of short half-life mixed fission products. This facility, referred to as the Idaho Elemental Separation On Line (ESOL), consists of electro-plated sources of spontaneously fissioning 252 Cf with a helium jet transport arrangement to continuously deliver short half-life, mixed fission products to the radiochemistry laboratory for rapid, computer controlled, radiochemical separations. 18 refs., 13 figs

  20. Radiochemical stability of radiopharmaceutical preparations

    International Nuclear Information System (INIS)

    Martins, Patricia de A.; Silva, Jose L. da; Ramos, Marcelo P.S.; Oliveira, Ideli M. de; Felgueiras, Carlos F.; Herrerias, Rosana; Zapparoli Junior, Carlos L.; Mengatti, Jair; Fukumori, Neuza T.O.; Matsuda, Margareth M.N.

    2011-01-01

    The 'in vitro' stability studies of the radiopharmaceutical preparations are an essential requirement for routine practice in nuclear medicine and are an important parameter for evaluating the quality, safety and efficacy required for the sanitary registration of pharmaceutical products. Several countries have published guidelines for the evaluation of pharmaceutical stability. In Brazil, the stability studies should be conducted according to the Guide for Conducting Stability Studies published in the Resolution-RE n. 1, of 29th July 2005. There are also for radiopharmaceutical products, two specific resolutions: RDC-63 regulates the Good Manufacturing Practices for Radiopharmaceuticals and RDC-64 provides the Registration of Radiopharmaceuticals, both published on the 18th December 2009. The radiopharmaceutical stability is defined as the time during which the radioisotope can be safely used for the intended purpose. The radiochemical stability can be affected by a variety of factors, including storage temperature, amount of radioactivity, radioactive concentration, presence or absence of antioxidants or other stabilizing agents. The radiochemical stability studies must be established under controlled conditions determined by the effective use of the product. The aim of this work was to evaluate the radiochemical stability of labeled molecules with 131 I, 123 I, 153 Sm, 18 F, 51 Cr, 177 Lu and 111 In as well as 67 Ga and 201 Tl radiopharmaceuticals. Radiochemical purity was evaluated after production and in the validity period, with the maximum activity and in the recommended storage conditions. The analyses were carried out by thin-layer silica gel plate, paper chromatography and gel chromatography. The experimental results showed to be in accordance with the specified limits for all the analysed products. (author)

  1. Cleanout and decontamination of radiochemical hot cells

    International Nuclear Information System (INIS)

    Surma, J.E.; Holton, L.K. Jr.; Katayama, Y.B.; Gose, J.E.; Haun, F.E.; Dierks, R.D.

    1990-01-01

    The Pacific Northwest Laboratory is developing and employing advanced remote and contact technologies in cleaning out and decontaminating six radiochemical hot cells at Hanford under the Department of Energy's Surplus Facilities Management Program. The program is using a series of remote and contact decontamination techniques to reduce costs and to significantly lower radiation doses to workers. Refurbishment of the cover blocks above the air lock trench reduced radiation exposure in the air lock and cleanout and decontamination of an analytical cell achieved a reduction in radioactive contamination. Nuclear Regulatory Commission-approved Type B burial boxes are also being used to reduce waste disposal costs and radiation doses. PNL is currently decommissioning its pilot-scale radioactive liquid-fed ceramic melter. Special tools have been developed and are being used to accomplish the world's first such effort. 4 refs., 5 figs

  2. Data processing software for purex plant process control laboratory

    International Nuclear Information System (INIS)

    Kansara, V.P.; Achuthan, P.V.; Sridhar, S.; Ramanujam, A.; Dhumwad, R.K.

    1990-01-01

    A software has been developed at the Fuel Reprocessing Division, Trombay to meet the data processing needs of the Control Laboratory of a reprocessing plant. During the normal plant operations contents of over one hundred process tanks have to be sampled and analysed for regular monitoring. In order to speed up the computation and the reporting of results as well as to obtain the process performance data over a period of time a software has been developed. The package has been sucessfully demonstrated and implemented at the Plutonium Plant, Trombay. This has been in continuous use since May 1987 with highly satisfactory performance. The software is a totally menu-driven package which can be used by the laboratory analysts with a few hours of training. The features include data validation involving source tank identification, the nature of the sample, the range of expected results, any duplication in sample numbering etc. Audio indication of deviations from the expected input or output values are given with an option to override in case of abnormal samples. The progress of analysis can be obtained for a given sample at any given time. Incorporated in the software is the help menu for quick reference of analytical protocol to be followed for a given tank/method. The computations for the determinations are carried out after obtaining input values on a screen-form. Th e results can be displayed on the monitor or obtained in the form of a hard copy i n any desired format. (author). 17 figs., 2 refs

  3. Standardization of equations for radiochemical calculations

    International Nuclear Information System (INIS)

    Danahy, R.J.; Dugan, T.A.; Tomlinson, F.K.; Jones, H.W.

    1994-01-01

    In mid 1993, the Fernald Environmental Restoration Management Corporation (FERMCO), with USEPA approval implemented a project quality assurance plan containing performance-based specifications for radiochemical sample analyses conducted in support of the Fernald site remediation activities. FERMCO's initial approach to acquiring performance-based radioanalytical services was to provide limited guidance regarding equations for computation of the quantities required in each analysis report. It became evident that there was a significant divergence of opinion on how to compute some very basic radiochemical quantities. The use of a standardized set of equations was needed in order to ensure comparability of data from different laboratories. In a remediation project of this magnitude, use of multiple laboratories is a virtual necessity. Consequently comparability of data becomes an extremely important issue. A critical issue in the Remedial Investigation/Feasibility Study (RI/FS) phase of the dean up project is to avoid the occurrence of excessive false positive sample results. Such results could lead to unnecessary clean up and significant additional cost. This paper describes the specific formulas FERMCO is currently using to define such quantities as net sample count rate, sample radionuclide concentration, radiometric tracer and gravimetric carrier recovery. Equations have also been produced to define the uncertainty in each of the above quantities. Equations for the Total Propagated Uncertainty (TPU) and for a sample-specific Minimum Detectable Concentration (MDC) have also been specified. Generalized equations have been reformulated to address the specific conditions which apply to the analysis of FERMCO samples. In particular, FERMCO requires results which have been corrected for the radioactivity in the blank while in other instances, sample results without blank correction are required

  4. Frictional heating processes during laboratory earthquakes

    Science.gov (United States)

    Aubry, J.; Passelegue, F. X.; Deldicque, D.; Lahfid, A.; Girault, F.; Pinquier, Y.; Escartin, J.; Schubnel, A.

    2017-12-01

    Frictional heating during seismic slip plays a crucial role in the dynamic of earthquakes because it controls fault weakening. This study proposes (i) to image frictional heating combining an in-situ carbon thermometer and Raman microspectrometric mapping, (ii) to combine these observations with fault surface roughness and heat production, (iii) to estimate the mechanical energy dissipated during laboratory earthquakes. Laboratory earthquakes were performed in a triaxial oil loading press, at 45, 90 and 180 MPa of confining pressure by using saw-cut samples of Westerly granite. Initial topography of the fault surface was +/- 30 microns. We use a carbon layer as a local temperature tracer on the fault plane and a type K thermocouple to measure temperature approximately 6mm away from the fault surface. The thermocouple measures the bulk temperature of the fault plane while the in-situ carbon thermometer images the temperature production heterogeneity at the micro-scale. Raman microspectrometry on amorphous carbon patch allowed mapping the temperature heterogeneities on the fault surface after sliding overlaid over a few micrometers to the final fault roughness. The maximum temperature achieved during laboratory earthquakes remains high for all experiments but generally increases with the confining pressure. In addition, the melted surface of fault during seismic slip increases drastically with confining pressure. While melting is systematically observed, the strength drop increases with confining pressure. These results suggest that the dynamic friction coefficient is a function of the area of the fault melted during stick-slip. Using the thermocouple, we inverted the heat dissipated during each event. We show that for rough faults under low confining pressure, less than 20% of the total mechanical work is dissipated into heat. The ratio of frictional heating vs. total mechanical work decreases with cumulated slip (i.e. number of events), and decreases with

  5. Photochemical process of laboratory uranium wastes recovery

    International Nuclear Information System (INIS)

    Borges, O.N.; Barros, M.P. de.

    1984-01-01

    A method for uranium extraction in presence of various aquometallic ions, based on selective photo-reduction of uranium is studied. Some economical advantages in relation with others conventional processes are analysed. (M.J.C.) [pt

  6. Laboratory simulations of lunar darkening processes

    Science.gov (United States)

    Hapke, B.

    1993-01-01

    It was clear long before the Apollo missions that a darkening process occurs on the moon. However, its nature remains controversial and elusive. Current evidence implies that the darkening is associated with, and is probably caused by, submicroscopic metallic iron in the regolith. Questions discussed at the workshop include: (1) under what conditions will impact vitrification produce a dark glass; (2) what is the role of the submicroscopic metallic Fe (SMFe) in the lunar darkening process; (3) how is the SMFe produced; (4) is there a significant component of the regolith that has been deposited from a vapor, if so, what form is it in, and how can it be recognized, what are its effects on the chemistry of the regolith; (5) how do the processes of impact vitrification, vaporization, sputtering, and SMFe production vary as a function of distance from the sun and location in planetary magnetospheres; and (6) what other processes might affect optical properties. Ices have lower melting and boiling temperatures and sputtering yields several orders of magnitude larger than silicates. Hence, analogous processes will occur to an even greater extent on satellites of the outer planets, and these questions are relevant to those bodies as well.

  7. Controlling Laboratory Processes From A Personal Computer

    Science.gov (United States)

    Will, H.; Mackin, M. A.

    1991-01-01

    Computer program provides natural-language process control from IBM PC or compatible computer. Sets up process-control system that either runs without operator or run by workers who have limited programming skills. Includes three smaller programs. Two of them, written in FORTRAN 77, record data and control research processes. Third program, written in Pascal, generates FORTRAN subroutines used by other two programs to identify user commands with device-driving routines written by user. Also includes set of input data allowing user to define user commands to be executed by computer. Requires personal computer operating under MS-DOS with suitable hardware interfaces to all controlled devices. Also requires FORTRAN 77 compiler and device drivers written by user.

  8. Northern Marshall Islands Radiological Survey: a quality-control program for a radiochemical analyses

    International Nuclear Information System (INIS)

    Jennings, C.D.; Mount, M.E.

    1983-08-01

    More than 16,000 radiochemical analyses were performed on about 5400 samples of soils, vegetation, animals, fish, invertebrates, and water to establish amounts of 90 Sr, 137 Cs, 241 Am, and plutonium isotopes in the Northern Marshall Islands. Three laboratories were contracted by Lawrence Livermore National Laboratory to perform the radiochemical analyses: Environmental Analysis Laboratory (EAL), Richmond, California; Eberline Instrument Corporation (EIC), Albuquerque, New Mexico; and Laboratory of Radiation Ecology (LRE), University of Washington, Seattle, Washington. The analytical precision and accuracy were monitored by regularly including duplicate samples and natural matrix standards in each group of about 100 samples analyzed. Based on the duplicates and standards, over 83% of the radiochemical analyses in this survey were acceptable - 97% of the analyses by EAL, 45% of the analyses by EIC, and 98% of the analyses by LRE

  9. Sandia Laboratories technical capabilities: materials and processes

    International Nuclear Information System (INIS)

    Lundergan, C.D.; Mead, P.L.

    1977-08-01

    Materials and process activities have emphasized the balance between research and development necessary to provide materials compatible with the extreme environments and performance requirements associated with nuclear ordnance. Specific technical areas which have continuing emphasis include metallurgy, composites, surface characterization and thin films, polymers, ceramics, and high-temperature characterization. Complete processing and fabrication facilities assure the capability for early evaluation and use of tailored materials. Efforts are focused on material applications involving structural and electronic materials, thermal and electrical insulation, radiation shields, and shock mitigation. Key elements in these efforts are functionability, reliability, and longevity. This interdisciplinary approach to scientific materials engineering results from the recognition that many disciplines are required to understand, characterize, and apply materials, and from the fact that material design is an essential element in meeting the objectives of quality, functionality, and life. In effect, the responsibility of a materials group extends beyond the development of a material into the understanding and description of its behavior in the extreme environments to which it will be subjected

  10. Virtual and Remote Laboratories in Process of Control Education

    Directory of Open Access Journals (Sweden)

    Martin Kalúz

    2012-02-01

    Full Text Available This paper describes the progress in the development of virtual and remote laboratories at Department of Information Engineering and Process Control, FCFT STU in Bratislava. Article is the overview of technical solutions used for online education purposes. These comprise software technologies, most commonly used in virtual and remote laboratory design at our department, as MATLAB Web Server, Java, C/C++, and Adobe Flash. We have created virtual laboratories as online Web applications, which provide features of mathematical computing and simulations of technological plants. We also describe a technology of remote control laboratory with a real experimental device.

  11. High-Frequency Microwave Processing of Materials Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: Conducts research on high-frequency microwave processing of materials using a highpower, continuous-wave (CW), 83-GHz, quasi-optical beam system for rapid,...

  12. Process Waste Assessment for the Plotting and Digitizing Support Laboratory

    International Nuclear Information System (INIS)

    Phillips, N.M.

    1994-04-01

    This Process Waste Assessment was conducted to evaluate the Plotting and Digitizing Support Laboratory, located in Building 913, Room 157. It documents the processes, identifies the hazardous chemical waste streams generated by these processes, recommends possible ways to minimize waste, and serves as a reference for future assessments of this facility

  13. Radiochemical analysis of chlorine-36

    International Nuclear Information System (INIS)

    Rodriguez, M.; Pina, G.; Lara, E.

    2006-01-01

    The radioactive chlorine isotope, 36 Cl, decays with a half-life of 3x10 5 years by emitting a beta particle (98 %) and by electron capture. The aim of this paper is to propose a radiochemical separation method of 36 Cl from the other beta-gamma emitters present in low and medium radioactive wastes such as spent ion exchange resins and evaporator concentrates, that arise from Nuclear Power Plants and particularly in the wastes that come from decommissioning activities of graphite reactors, in order to provide data for 36 Cl inventory calculations. The separation method proposed is based on an oxidation technique where chlorine is trapped by NaOH. 36 Cl beta emissions are measured by liquid scintillation counting by the dual label technique in order to avoid the contamination produced by 14 C which is also trapped by NaOH and which is the main contaminant present in graphite samples. The sensitivity of this method is sufficient to achieve the needed thresholds for the radiological characterization of the radioactive materials to which this method can be applied. (author)

  14. Radiochemical purity determination by paper chromatography 2

    International Nuclear Information System (INIS)

    1975-01-01

    The standard relates to the determination of radiochemical impurities in labelled compounds using paper chromatography. The basic terms are given as is the description of procedure and evaluation of chromatograms. (E.S.)

  15. Radiochemistry and radiochemical separations. A current bibliography

    International Nuclear Information System (INIS)

    Bujdoso, E.

    1999-01-01

    A current bibliography for years 1993-1996 with 159 references was compiled on radiochemistry and radiochemical separations based on the INIS Atomindex. The references are arranged in alphabetical order of first authors. (N.T.)

  16. Automated Radioanalytical Chemistry: Applications For The Laboratory And Industrial Process Monitoring

    International Nuclear Information System (INIS)

    O'Hara, Matthew J.; Farawila, Anne F.; Grate, Jay W.

    2009-01-01

    The identification and quantification of targeted α- and β-emitting radionuclides via destructive analysis in complex radioactive liquid matrices is highly challenging. Analyses are typically accomplished at on- or off-site laboratories through laborious sample preparation steps and extensive chemical separations followed by analysis using a variety of detection methodologies (e.g., liquid scintillation, alpha energy spectroscopy, mass spectrometry). Analytical results may take days or weeks to report. When an industrial-scale plant requires periodic or continuous monitoring of radionuclides as an indication of the composition of its feed stream, diversion of safeguarded nuclides, or of plant operational conditions (for example), radiochemical measurements should be rapid, but not at the expense of precision and accuracy. Scientists at Pacific Northwest National Laboratory have developed and characterized a host of automated radioanalytical systems designed to perform reproducible and rapid radioanalytical processes. Platforms have been assembled for (1) automation and acceleration of sample analysis in the laboratory and (2) automated monitors for monitoring industrial scale nuclear processes on-line with near-real time results. These methods have been applied to the analysis of environmental-level actinides and fission products to high-level nuclear process fluids. Systems have been designed to integrate a number of discrete sample handling steps, including sample pretreatment (e.g., digestion and valence state adjustment) and chemical separations. The systems have either utilized on-line analyte detection or have collected the purified analyte fractions for off-line measurement applications. One PNNL system of particular note is a fully automated prototype on-line radioanalytical system designed for the Waste Treatment Plant at Hanford, WA, USA. This system demonstrated nearly continuous destructive analysis of the soft β-emitting radionuclide 99Tc in nuclear

  17. Present status of radiochemical double β decay study (238U)

    International Nuclear Information System (INIS)

    Chevallier, A.; Chevallier, J.; Escoubes, B.; Schulz, N.; Sens, J.C.; Madic, C.; Maillard, C.

    1989-01-01

    The reasons for which the 238 U is a suitable candidate for the β β decay processes are explained. The strategy adopted for the radiochemical separation of the 234 U is given. A chemical system based on extraction chromatography is applied. The Pu IV breakthrough curves obtained at 40C during 238 Pu/ 238 U separation cycles are presented. A short description of the chromatographic facility is given. The solution adopted for the low background α spectrometer is explained

  18. International intercalibration as a method for control of radiochemical analyses

    International Nuclear Information System (INIS)

    Angelova, A.; Totseva, R.; Karaivanova, R.; Dandulova, Z.; Botsova, L.

    1994-01-01

    The participation of the Radioecology Section at the National Centre for Radiology and Radiation Protection (NCRRP) in the International Interlaboratory Comparison of radiochemical analyses organized by WHO is reported. The method of evaluating accuracy of the results from inter calibrations concerning radionuclide determination of environmental samples is outlined. The data from analysis of cesium 137, strontium 90 and radium 226 in milk, sediments, soil and seaweed made by 21 laboratories are presented. They show a good accuracy values of the results from NCRRP. 1 tab. 2 figs., 6 refs

  19. Radiochemical measurement of mass transport in sodium

    International Nuclear Information System (INIS)

    Cooper, M.H.; Chiang, S.H.

    1976-01-01

    Mass transport processes in the sodium coolant of Liquid Metal Fast Breeder Reactors (LMFBRs) are significant in determining rates of corrosion and deposition of radioactive nuclides from the fuel cladding, deposition and cold trapping of fission products from defect or failed fuel, carbon and nitrogen redistribution in the containment materials, and removal of impurities by cold trapping or hot trapping. Mass transport between rotating, concentric cylinders in molten sodium has been investigated using a unique radiochemical method. Long-lived (33 year) cesium-137, dissolved in the sodium, decays radioactively emitting a beta to barium-137m, which decays with a short half-life (2.6 minutes) emitting a gamma. Cesium is weakly adsorbed and remains in solution, while the barium is strongly adsorbed on the stainless steel surfaces. Hence, by measuring the barium-137m activity on movable stainless steel surfaces, one can calculate the mass transport to that surface. Mass transfer coefficients in sodium measured by this method are in agreement with published heat transfer correlations when the effect of the volumetric mass source is taken into account. Hence, heat transfer correlations can be confidently utilized by analogy in estimating mass transfer in liquid-metal systems

  20. Radiochemical separation of cadmium-109

    International Nuclear Information System (INIS)

    Egamediev, S.; Mukhtarov, A.; Nurbaeva, D.; Rakhmanov, A.

    2006-01-01

    Full text: Cadmium-109 has a half-life of 461.9 days and decays by electron capture to 109 Ag with the emission of 88 keV γ-ray (3.79%) along with the characteristic X-ray from the K level of Ag, with energy of 22.5 keV. This radionuclide has found widespread use as a photon source in x-ray fluorescence analysis devices employed in industry for numerous applications such as the direct determination of gold in ores, the analysis of metals and identification of steels. Other applications range from its use as an electron source for measurement of densities of air-pollution samples, to tracer studies in mushrooms and mice and rats. In the nuclear medicine field there is growing interest in employing 109 Cd in a 109 Cd/ 109mA g generator, as an alternative to other biomedical generators of ultra short-lived gamma emitters. There are several methods for the production of 109 Cd in literature: 1. Bombardment of silver cyclotron target via 109 Ag(d,2n) 109 Cd reaction with 16 MeV deuterons. 2. Bombardment of natural silver target via 109 Ag(p,n) 109 Cd reaction with 14 MeV protons. 3. Proton bombardment of natural indium target with 96 MeV protons. 4. Irradiation of enriched 107 Ag target in high-flux nuclear reactor at neutron flux 2x10 15 n·cm -2 ·s -1 via 107 Ag(n,γ) 108 Ag → 108 Cd (n,γ) 109 Cd reaction. 5. Irradiation of enriched 108 Cd target in nuclear reactor at neutron flux 1x10 14 n·cm -2 ·s -1 via 108 Cd (n,γ) 109 Cd reaction. The production of 109 Cd with proton beam via 109 Ag(p,n) 109 Cd reaction is ideal for the cyclotron U-150, since it is not required the change of the regime for the machine functioning. Because of its relatively long half-life the time required for separation is also not an important factor, but its use as an X-ray source requires a very high radiochemical purity. In the present work we studied two methods for separation of 109 Cd from model solution of silver targets. First method is based on precipitation of silver as

  1. Data Processing and Programming Applied to an Environmental Radioactivity Laboratory; Desarrollo Informatico Aplicado a un Laboratorio de Radiactividad Ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Trinidad, J.A.; Gasco, C.; Palacios, M.A.

    2009-07-01

    This report is the original research work presented for the attainment of the author master degree and its main objective has been the resolution -by means of friendly programming- of some of the observed problems in the environmental radioactivity laboratory belonging to the Department of Radiological Surveillance and Environmental Radioactivity from CIEMAT. The software has been developed in Visual Basic for applications in Excel files and it solves by macro orders three of the detected problems: a) calculation of characteristic limits for the measurements of the beta total and beta rest activity concentrations according to standards MARLAP, ISO and UNE and the comparison of the three results b) Pb-210 and Po-210 decontamination factor determination in the ultra-low level Am-241 analysis in air samples by alpha spectrometry and c) comparison of two analytical techniques for measuring Pb-210 in air ( direct-by gamma spectrometry- and indirect -by radiochemical separation and alpha spectrometry). The organization processes of the different excel files implied in the subroutines, calculations and required formulae are explained graphically for its comprehension. The advantage of using this kind of programmes is based on their versatility and the ease for obtaining data that lately are required by tables that can be modified as time goes by and the laboratory gets more data with the special applications for describing a method (Pb-210 decontamination factors for americium analysis in air) or comparing temporal series of Pb-210 data analysed by different methods (Pb-210 in air). (Author)

  2. Testing a Constrained MPC Controller in a Process Control Laboratory

    Science.gov (United States)

    Ricardez-Sandoval, Luis A.; Blankespoor, Wesley; Budman, Hector M.

    2010-01-01

    This paper describes an experiment performed by the fourth year chemical engineering students in the process control laboratory at the University of Waterloo. The objective of this experiment is to test the capabilities of a constrained Model Predictive Controller (MPC) to control the operation of a Double Pipe Heat Exchanger (DPHE) in real time.…

  3. Waste management study: Process development at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    1984-12-01

    This report presents the results of an evaluation of the present Toxic Waste Control Operations at the Lawrence Livermore National Laboratory, evaluates the technologies most applicable to the treatment of toxic and hazardous wastes and presents conceptual designs of processes for the installation of a new decontamination and waste treatment facility (DWTF) for future treatment of these wastes

  4. Development of robotic plasma radiochemical assays for positron emission tomography

    International Nuclear Information System (INIS)

    Alexoff, D.L.; Shea, C.; Fowler, J.S.; Gatley, S.J.; Schlyer, D.J.

    1995-01-01

    A commercial laboratory robot system (Zymate PyTechnology II Laboratory Automation System; Zymark Corporation, Hopkinton, MA) was interfaced to standard and custom laboratory equipment and programmed to perform rapid radiochemical analyses for quantitative PET studies. A Zymark XP robot arm was used to carry out the determination of unchanged (parent) radiotracer in plasma using only solid phase extraction methods. Robotic throughput for the assay of parent radiotracer in plasma is 4--6 samples/hour depending on the radiotracer. Robotic assays of parent compound in plasma were validated for the radiotracers [ 11 C]Benztropine, [ 11 C]cocaine, [ 11 C]clorgyline, [ 11 C]deprenyl, [ 11 C]methadone, [ 11 C]methylphenidate, [ 11 C]raclorpride, and [ 11 C]SR46349B. A simple robot-assisted methods development strategy has been implemented to facilitate the automation of plasma assays of new radiotracers

  5. Environmental Assessment for the vacuum process laboratory (VPL) relocation at the Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    1992-04-01

    This Environmental Assessment (EA) evaluates the potential environmental impacts of relocating a vacuum process laboratory (VPL) from Building 321 to Building 2231 at Lawrence Livermore National Laboratory (LLNL). The VPL provides the latest technology in the field of vacuum deposition of coatings onto various substrates for several weapons-related and energy-related programs at LLNL. Operations within the VPL at LLNL will not be expanded nor reduced by the relocation. No significant environmental impacts are expected as a result of the relocation of the VPL

  6. Accreditation of Medical Laboratories – System, Process, Benefits for Labs

    Directory of Open Access Journals (Sweden)

    Zima Tomáš

    2017-09-01

    Full Text Available One and key of the priorities in laboratory medicine is improvement of quality management system for patient safety. Quality in the health care is tightly connected to the level of excellence of the health care provided in relation to the current level of knowledge and technical development. Accreditation is an effective way to demonstrate competence of the laboratory, a tool to recognize laboratories world-wide, is linked to periodical audits, to stimulate the maintenance and improvement of the quality, which leads to high standard of services for clients (patients, health care providers, etc.. The strategic plans of IFCC and EFLM include focusing on accreditation of labs based on ISO standards and cooperation with European Accreditation and national accreditation bodies. IFCC and EFLM recognised that ISO 15189:2012 Medical laboratories – Requirements for quality and competence, encompasses all the assessment criteria specified in the policy of quality. The last version is oriented to process approach with detailed division and clearly defined requirements. The accreditation of labs improves facilitation of accurate and rapid diagnostics, efficiency of treatment and reduction of errors in the laboratory process. Accreditation is not about who the best is, but who has a system of standard procedures with aim to improve the quality and patient safety. Quality system is about people, with people and for people.

  7. Software process improvement in the NASA software engineering laboratory

    Science.gov (United States)

    Mcgarry, Frank; Pajerski, Rose; Page, Gerald; Waligora, Sharon; Basili, Victor; Zelkowitz, Marvin

    1994-01-01

    The Software Engineering Laboratory (SEL) was established in 1976 for the purpose of studying and measuring software processes with the intent of identifying improvements that could be applied to the production of ground support software within the Flight Dynamics Division (FDD) at the National Aeronautics and Space Administration (NASA)/Goddard Space Flight Center (GSFC). The SEL has three member organizations: NASA/GSFC, the University of Maryland, and Computer Sciences Corporation (CSC). The concept of process improvement within the SEL focuses on the continual understanding of both process and product as well as goal-driven experimentation and analysis of process change within a production environment.

  8. Advanced Manufacturing Processes Laboratory Building 878 hazards assessment document

    International Nuclear Information System (INIS)

    Wood, C.; Thornton, W.; Swihart, A.; Gilman, T.

    1994-07-01

    The introduction of the hazards assessment process is to document the impact of the release of hazards at the Advanced Manufacturing Processes Laboratory (AMPL) that are significant enough to warrant consideration in Sandia National Laboratories' operational emergency management program. This hazards assessment is prepared in accordance with the Department of Energy Order 5500.3A requirement that facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment provides an analysis of the potential airborne release of chemicals associated with the operations and processes at the AMPL. This research and development laboratory develops advanced manufacturing technologies, practices, and unique equipment and provides the fabrication of prototype hardware to meet the needs of Sandia National Laboratories, Albuquerque, New Mexico (SNL/NM). The focus of the hazards assessment is the airborne release of materials because this requires the most rapid, coordinated emergency response on the part of the AMPL, SNL/NM, collocated facilities, and surrounding jurisdiction to protect workers, the public, and the environment

  9. Advanced Manufacturing Processes Laboratory Building 878 hazards assessment document

    Energy Technology Data Exchange (ETDEWEB)

    Wood, C.; Thornton, W.; Swihart, A.; Gilman, T.

    1994-07-01

    The introduction of the hazards assessment process is to document the impact of the release of hazards at the Advanced Manufacturing Processes Laboratory (AMPL) that are significant enough to warrant consideration in Sandia National Laboratories` operational emergency management program. This hazards assessment is prepared in accordance with the Department of Energy Order 5500.3A requirement that facility-specific hazards assessments be prepared, maintained, and used for emergency planning purposes. This hazards assessment provides an analysis of the potential airborne release of chemicals associated with the operations and processes at the AMPL. This research and development laboratory develops advanced manufacturing technologies, practices, and unique equipment and provides the fabrication of prototype hardware to meet the needs of Sandia National Laboratories, Albuquerque, New Mexico (SNL/NM). The focus of the hazards assessment is the airborne release of materials because this requires the most rapid, coordinated emergency response on the part of the AMPL, SNL/NM, collocated facilities, and surrounding jurisdiction to protect workers, the public, and the environment.

  10. Radiochemical analysis of phosphorus in milk samples

    International Nuclear Information System (INIS)

    Oliveira, R.M. de; Cunha, I.I.L.

    1991-01-01

    The determination of phosphorus in milk samples by thermal neutron activation analysis employing radiochemical separation is described. The radiochemical separation consists of the simultaneous irradiation of samples and standards, dissolution of the milk samples in a perchloric acid and nitric acid mixture, addition of zinc hold-back carrier, precipitation of phosphorus as ammonium phospho molybdate (A.M.P.) and sample counting in a Geiger-Mueller detector. The analysis sources of error were studied and the established method was applied to phosphorus analyses in commercial milk samples. (author)

  11. Pyrochemical processing automation at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Dennison, D.K.; Domning, E.E.; Seivers, R.

    1991-01-01

    Lawrence Livermore National Laboratory (LLNL) is developing a fully automated system for pyrochemical processing of special nuclear materials (SNM). The system utilizes a glove box, an automated tilt-pour furnace (TPF), an IBM developed gantry robot, and specialized automation tooling. All material handling within the glove box (i.e., furnace loading, furnace unloading, product and slag separation, and product packaging) is performed automatically. The objectives of the effort are to increase process productivity, decrease operator radiation, reduce process wastes, and demonstrate system reliability and availability. This paper provides an overview of the automated system hardware, outlines the overall operations sequence, and discusses the current status

  12. Manual on laboratory testing for uranium ore processing

    International Nuclear Information System (INIS)

    1990-01-01

    Laboratory testing of uranium ores is an essential step in the economic evaluation of uranium occurrences and in the development of a project for the production of uranium concentrates. Although these tests represent only a small proportion of the total cost of a project, their proper planning, execution and interpretation are of crucial importance. The main purposes of this manual are to discuss the objectives of metallurgical laboratory ore testing, to show the specific role of these tests in the development of a project, and to provide practical instructions for performing the tests and for interpreting their results. Guidelines on the design of a metallurgical laboratory, on the equipment required to perform the tests and on laboratory safety are also given. This manual is part of a series of Technical Reports on uranium ore processing being prepared by the IAEA's Division of Nuclear Fuel Cycle and Waste Management. A report on the Significance of Mineralogy in the Development of Flowsheets for Processing Uranium Ores (Technical Reports Series No. 196, 1980) and an instruction manual on Methods for the Estimation of Uranium Ore Reserves (No. 255, 1985) have already been published. 17 refs, 40 figs, 17 tabs

  13. The role of high performance liquid chromatography in radiochemical/radiopharmaceutical synthesis and quality assurance

    International Nuclear Information System (INIS)

    Boothe, T.E.; Emran, A.M.

    1990-01-01

    The usefulness of HPLC in all areas of radiopharmaceutics has been demonstrated in numerous laboratories, particularly in the development of in-house radiopharmaceuticals for SPECT and PET. HPLC continues to be a powerful tool in preparation and quality assurance (QA) as illustrated in such areas as chemical and radiochemical identification; product separation and isolation; preparative scale purification; and specific activity determination. A review of established HPLC techniques in radiopharmaceutics will be presented. Examples from the literature as well as newer applications will be used in an attempt to assess and define the present-day role of HPLC in the preparation of radiochemicals and radiopharmaceuticals with emphasis on QA

  14. Environmental assessment for the Processing and Environmental Technology Laboratory (PETL)

    International Nuclear Information System (INIS)

    1995-09-01

    The U.S. Department of Energy (DOE) has prepared an environmental assessment (EA) on the proposed Processing and Environmental Technology Laboratory (PETC) at Sandia National Laboratories/New Mexico (SNL/NM). This facility is needed to integrate, consolidate, and enhance the materials science and materials process research and development (R ampersand D) currently in progress at SNL/NM. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, an environmental impact statement is not required, and DOE is issuing this Finding of No Significant Impact (FONSI)

  15. Environmental assessment for the Processing and Environmental Technology Laboratory (PETL)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The U.S. Department of Energy (DOE) has prepared an environmental assessment (EA) on the proposed Processing and Environmental Technology Laboratory (PETC) at Sandia National Laboratories/New Mexico (SNL/NM). This facility is needed to integrate, consolidate, and enhance the materials science and materials process research and development (R&D) currently in progress at SNL/NM. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, an environmental impact statement is not required, and DOE is issuing this Finding of No Significant Impact (FONSI).

  16. Implementing a lessons learned process at Sandia National Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Fosshage, Erik D.; Drewien, Celeste A.; Eras, Kenneth; Hartwig, Ronald Craig; Post, Debra S.; Stoecker, Nora Kathleen

    2016-01-01

    The Lessons Learned Process Improvement Team was tasked to gain an understanding of the existing lessons learned environment within the major programs at Sandia National Laboratories, identify opportunities for improvement in that environment as compared to desired attributes, propose alternative implementations to address existing inefficiencies, perform qualitative evaluations of alternative implementations, and recommend one or more near-term activities for prototyping and/or implementation. This report documents the work and findings of the team.

  17. Radiochemical studies on nuclear fission at Trombay

    Indian Academy of Sciences (India)

    227Ac to 245Cm were determined by radiochemical methods which involved ... foil, followed by direct γ counting using high resolution Ge(Li) detector was also ... the stiffness to mass asymmetric distortion decreases on either side of lead.Also ...

  18. On-Line Monitoring for Control and Safeguarding of Radiochemical Streams at Spent Fuel Reprocessing Plant

    International Nuclear Information System (INIS)

    Bryan, Samuel A.; Levitskaia, Tatiana G.; Billing, Justin M.; Casella, Amanda J.; Johnsen, Amanda M.; Peterson, James M.

    2009-01-01

    Advanced techniques enabling enhanced safeguarding of the spent fuel reprocessing plants are urgently needed. Our approach is based on prerequisite that real time monitoring of the solvent extraction flowsheets provides unique capability to quickly detect unwanted manipulations with fissile isotopes present in the radiochemical streams during reprocessing activities. The methods used to monitor these processes must be robust and must be able to withstand harsh radiation and chemical environments. A new on-line monitoring system satisfying these requirements and featuring Raman spectroscopy combined with a Coriolis and conductivity probes, has been recently developed by our research team. It provides immediate chemical data and flow parameters of high-level radioactive waste streams with high brine content generated during retrieval activities from Hanford nuclear waste storage tanks. The nature of the radiochemical streams at the spent fuel reprocessing plant calls for additional spectroscopic information, which can be gained by the utilization of UV-vis-NIR capabilities. Raman and UV-vis-NIR spectroscopies are analytical techniques that have extensively been extensively applied for measuring the various organic and inorganic compounds including actinides. The corresponding spectrometers used under the laboratory conditions are easily convertible to the process-friendly configurations allowing remote measurements under the flow conditions. A fiber optic Raman probe allows monitoring of the high concentration species encountered in both aqueous and organic phases within the UREX suite of flowsheets, including metal oxide ions, such as uranyl, components of the organic solvent, inorganic oxo-anions, and water. The actinides and lanthanides are monitored remotely by UV-vis-NIR spectroscopy in aqueous and organic phases. In this report, we will present our recent results on spectroscopic measurements of simulant flowsheet solutions and commercial fuels available at

  19. The Northern Marshall Islands radiological survey: A quality control program for radiochemical and gamma spectroscopy analysis

    International Nuclear Information System (INIS)

    Kehl, S.R.; Mount, M.E.; Robison, W.L.

    1995-09-01

    From 1979 to 1989, approximately 25,000 Post Northern Marshall Islands Radiological Survey (PNMIRS) samples were collected, and over 71,400 radiochemical and gamma spectroscopy analyses were performed to establish the concentration of 90 Sr, 137 Cs, 241 Am, and plutonium isotopes in soil, vegetation, fish, and animals in the Northern Marshall Islands. While the Low Level Gamma Counting Facility (B379) in the Health and Ecological Assessment (HEA) division accounted for over 80% of all gamma spectroscopy analyses, approximately 4889 radiochemical and 5437 gamma spectroscopy analyses were performed on 4784 samples of soil, vegetation, terrestrial animal, and marine organisms by outside laboratories. Four laboratories were used by Lawrence Livermore National Laboratory (LLNL) to perform the radiochemical analyses: Thermo Analytical Norcal, Richmond, California (TMA); Nuclear Energy Services, North Carolina State University (NCSU); Laboratory of Radiation Ecology, University of Washington (LRE); and Health and Ecological Assessment (HEA) division, LLNL, Livermore, California. Additionally, LRE and NCSU were used to perform gamma spectroscopy analyses. The analytical precision and accuracy were monitored by including blind duplicates and natural matrix standards in each group of samples analyzed. On the basis of reported analytical values for duplicates and standards, 88% of the gamma and 87% of the radiochemical analyses in this survey were accepted. By laboratory, 93% of the radiochemical analyses by TMA; 88% of the gamma-ray spectrometry and 100% of the radiochemistry analyses by NCSU; 89% of the gamma spectroscopy and 87% of the radiochemistry analyses by LRE; and 90% of the radiochemistry analyses performed by HEA's radiochemistry department were accepted

  20. Process data in safeguards at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Ehinger, M.H.

    1988-01-01

    The desire to improve timeliness and sensitivity of material control and accounting capabilities is the basis for evaluation and upgrade of regulatory requirements throughout the nuclear industry. Improvements invariably require better measurement capabilities and more frequent measurements. Operating plants typically include a broad range of measurements and equipment devoted to process control. How can these measurements be used to benefit safeguards? A part of the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory has focused on the use of process data for safeguards. This report discusses recent safeguards demonstrations and current activities in a test facility at Oak Ridge

  1. Industrial versus Laboratory Clinker Processing Using Grinding Aids (Scale Effect

    Directory of Open Access Journals (Sweden)

    Joseph Jean Assaad

    2015-01-01

    Full Text Available The evaluation of grinding aid (GA effect on clinker processing in laboratory grinding mills is relatively simple. Yet, the results obtained cannot be directly transposed to industrial mills, given the fundamentally different operational modes and grinding parameters. This paper seeks to evaluate the scale effect by comparing the results obtained from a closed-circuit tube mill operating at 90 ton/hr to those determined using a 50-liter laboratory mill. Tests results have shown that the decrease in specific energy consumption (Ec due to glycol or amine-based GA can be evaluated under laboratory conditions. However, such tests underestimate the actual performance that could be achieved in real-scale mills; the Ec reduction due to GA is around twofold higher when grinding is performed in real-scale mill. Compared to industrial tests, the cement particle size distribution curves widened and shifted towards higher diameters when grinding was performed under laboratory conditions, particularly with GA additions. This led to remarkable changes in water demand, setting time, and 1- and 28-day compressive strengths.

  2. Radiochemical education in Iasi, Romania

    International Nuclear Information System (INIS)

    Popa, Karin

    2009-01-01

    The teaching and research in radiochemistry is disregarded by most universities (mainly due to the cost and legal requirements for maintaining a nuclear unit of first or second class), although the interest in new generation nuclear reactors is increasing worldwide. The historical background and the educational and the research activities conducted in the Laboratory of Radiochemistry of the Al.I. Cuza University of Iasi as of one of the last bastions of radiochemistry in Romania are presented here. This unit remains one of the last Romanian educational structures which allow the next generation of radio chemists to gain hands on experience as a part of their training: an impressive number of former students are currently employed by nuclear research centres and nuclear energy production facilities not only in Romania but all around Europe. Unfortunately, without a stronger involvement of the authorities, the laboratory risks to be closed by 2011, despite of the effort of a few people (as most of other similar structures in Romania. (author)

  3. Methods for training radiochemical technicians at ORNL

    International Nuclear Information System (INIS)

    Parrott, J.R.; Nicol, R.G.

    1975-01-01

    The training of personnel to carry out radiochemical operations at ORNL is a formidable and recurrent task since repetitive, production-type operations are not involved, and programs are constantly shifting. It is essential that provisions be made for the routine retraining of personnel if they are to make effective contributions on a continuing basis. The present training methods have emerged as a result of thirty years experience in a variety of radiochemical pilot-plant programs. These programs have included operations performed in glove boxes, hot-cell manipulator work handling high-neutron-emitting isotopes, and the entire spectrum of remote solvent extraction operations. Present methods of training and the results obtained are summarized

  4. Radiochemical Means of Investigating Delayed Neutron Precursors

    International Nuclear Information System (INIS)

    Marmol, P. del

    1968-01-01

    Fast radiochemical methods used now for the determination of delayed neutron precursors are classified and reviewed: precipitations, solvent extractions, range experiments, milking, gas sweeping, isotopic and ion exchange, hot atom reactions and diffusion loss. Advantages and limitations of irradiation systems with respect to fast separations are discussed: external beams which allow faster separations only have low neutron fluxes, internal beams which are mostly fit for gaseous reactions; and rabbits for solution irradiations. Future prospects of radiochemical procedures are presented; among these, studies should be mostly oriented towards gaseous reactions which offer possibilities of isolating very short-lived delayed neutron precursors. Chemical procedures for delayed neutron precursor detection are compared with mass spectrometric and isotope separator techniques; it is concluded that the methods are complementary. (author)

  5. Radiochemical Means of Investigating Delayed Neutron Precursors

    International Nuclear Information System (INIS)

    Marmol, P. del

    1968-01-01

    Fast radiochemical methods used now for the determination of delayed neutron precursors are classified and reviewed: precipitations, solvent extractions, range experiments, milking, gas sweeping, isotopic and ion exchange, hot-atom reactions and diffusion loss. Advantages and limitations of irradiation systems with respect to fast separations are discussed: external beams which allow faster separations only have low neutron fluxes, internal beams which are mostly fit for gaseous reactions; and rabbits for solution irradiations. Future prospects of radiochemical procedures are presented; among these, studies should be mostly oriented towards gaseous reactions which offer possibilities of isolating very short-lived delayed neutron precursors. Chemical procedures for delayed neutron precursor detection are compared with mass spectrometric and isotope-separator techniques; it is concluded that the methods are complementary. (author)

  6. Radiochemical analysis of the Bikini ashes

    Energy Technology Data Exchange (ETDEWEB)

    Ishibashi, M; Shigematsu, T; Ishida, T

    1954-01-01

    The following nuclides were detected in the Bikini ashes by radiochemical procedures: /sup 45/Ca, /sup 89/Sr, /sup 91/Y, /sup 95/Zr, /sup 103/Ru, /sup 144/Pr, and /sup 237/U. The ion-exchange method was used for analysis of contaminated rain water which fell on the Kyoto area on May 16, 1954 from which the presence of /sup 89/Sr, /sup 95/Zr, and /sup 140/Ba, was detected. Rare earths seemed also to be present.

  7. Imaging Scanner Usage in Radiochemical Purity Test

    International Nuclear Information System (INIS)

    Norhafizah Othman; Yahaya Talib; Wan Hamirul Bahrin Wan Kamal

    2011-01-01

    Imaging Scanner model BIOSCAN AR-2000 has been used in the radiochemical purity test for the product of Mo-99/ Tc-99m generator. Result from this test was produced directly where the percentage of pertechnetate was calculated based on width peak area by thin layer chromatography. This paperwork will explain the function, procedure, calibration of the instrument and discussed the advantages compared to the previous method. (author)

  8. Radiochemical analysis of military nuclear facilities

    International Nuclear Information System (INIS)

    Bayramov, A.A.; Bayramova, S.M.

    2012-01-01

    Full text : Radiochemical Analysis is a branch of analytical chemistry comprising an aggregate of methods for qualitatively determining the composition and content of radioisotopes in the products of transformations. Safety and minimization of radiation impact on human and environment are important demand of operation of Military Nuclear Facilities (MNF). In accordance of recommendations of International Commission on Radiological Protection there are next objects of radiochemical analysis: 1) potential sources of radiochemical pollution; 2) environment (objects of environment, human environment including buildings, agricultural production, water, air et al.); 3) human himself (determination of dose from external and internal radiation, chemical poisoning). The chemical analysis can be carried out using, for example, the Gas Chromatography instrument whish separates chemical mixtures and identifies the components at a molecular level. It is one of the most accurate tools for analyzing environmental samples. The Gas Chromatography works on the principle that a mixture will separate into individual substances when heated. The heated gases are carried through a column with an inert gas (such as helium). As the separated substances emerge from the column opening, they flow into the Mass Spectrometry. Mass spectrometry identifies compounds by the mass of the analyte molecule. Newly developed portable Gas Chromatography and Mass Spectrometry are techniques that can be used to separate volatile organic compounds and pesticides. Other uses of Gas Chromatography, combined with other separation and analytical techniques, have been developed for radionuclides, explosive compounds such as royal demolition explosive and trinitrotoluene, and metals. So, based on the many years experience of operation of dangerous MNF, in concordance with norms of radiation and chemical safety it was considered that the tasks of the radiochemical analysis of Military Nuclear Facilities include

  9. 14th radiochemical conference. Booklet of abstracts

    International Nuclear Information System (INIS)

    2002-03-01

    The contributions dealt with the following topics: Radionuclides in the environment, radioecology; Nuclear analytical methods; Chemistry of actinide and trans-actinide elements; Ionizing radiation in science, technology, and arts and cultural heritage preservation; Production and application of radionuclides; Separation methods, speciation; Chemistry of nuclear fuel cycle, radiochemical problems in nuclear waste management; and Nuclear methods in medicine, radiopharmaceuticals, and radiodiagnostics, labelled compounds. Of the verbal and poster presentation, 192 have been input to INIS. (P.A.)

  10. Characterization of filter cartridges from the IEA-R1 reactor by radiochemical method

    International Nuclear Information System (INIS)

    Geraldo, Bianca; Vicente, Roberto; Ferreira, Robson J.; Goes, Marcos M.; Marumo, Julio T.

    2015-01-01

    The filter cartridges used in water purification system of research nuclear reactor IEA-R1 are considered radioactive wastes after their useful life. The characterization of these wastes is one of the stages of management, which aims to identify and quantify the radionuclides present, including those known as 'difficult to measure' (DTM) radionuclides. Establish a radiochemical analysis methodology for this type of waste is a difficult job, not only by the application of these techniques, but also by the amount of radionuclides that should be analyzed. In the waste produced in a nuclear reactor, the most important radionuclides are fission products, activation products and transuranic elements. Since these radionuclides emit gamma radiation not measurable in its decay process and consequently are difficult to measure, their concentrations can be estimated by indirect methods such as scale factors. This method is used to evaluate the DTM concentration, which is represented by alpha and beta nuclides using the correlation between them and the radionuclide key, a gamma emitter. The objective of this work is to describe a radiochemical analysis methodology for gamma emitter nuclides, present in the filter cartridges, evaluating the activity and concentrations by destructive assays. At the same time, two studies have been performed by non-destructive assays, the first one based on dose rates and the point kernel method to correlate the results and the second one based on calibration efficiency with Monte Carlo method. These studies belong to the radioactive waste characterization program that has been conducted at the Waste Management Laboratory of Nuclear and Energy Research Institute, IPEN-CNEN/SP. (author)

  11. Characterization of filter cartridges from the IEA-R1 reactor by radiochemical method

    Energy Technology Data Exchange (ETDEWEB)

    Geraldo, Bianca; Vicente, Roberto; Ferreira, Robson J.; Goes, Marcos M.; Marumo, Julio T., E-mail: bgeraldo@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The filter cartridges used in water purification system of research nuclear reactor IEA-R1 are considered radioactive wastes after their useful life. The characterization of these wastes is one of the stages of management, which aims to identify and quantify the radionuclides present, including those known as 'difficult to measure' (DTM) radionuclides. Establish a radiochemical analysis methodology for this type of waste is a difficult job, not only by the application of these techniques, but also by the amount of radionuclides that should be analyzed. In the waste produced in a nuclear reactor, the most important radionuclides are fission products, activation products and transuranic elements. Since these radionuclides emit gamma radiation not measurable in its decay process and consequently are difficult to measure, their concentrations can be estimated by indirect methods such as scale factors. This method is used to evaluate the DTM concentration, which is represented by alpha and beta nuclides using the correlation between them and the radionuclide key, a gamma emitter. The objective of this work is to describe a radiochemical analysis methodology for gamma emitter nuclides, present in the filter cartridges, evaluating the activity and concentrations by destructive assays. At the same time, two studies have been performed by non-destructive assays, the first one based on dose rates and the point kernel method to correlate the results and the second one based on calibration efficiency with Monte Carlo method. These studies belong to the radioactive waste characterization program that has been conducted at the Waste Management Laboratory of Nuclear and Energy Research Institute, IPEN-CNEN/SP. (author)

  12. Infralevel radiochemical applications-II

    International Nuclear Information System (INIS)

    Schachter, M.M.

    1989-01-01

    This paper discusses several practical applications of low level nuclear radiation from natural sources, and even from a man-made source-spent nuclear fuel elements from dismantled nuclear power plant reactors. The natural sources are the ubiquitous potassium 40 in the Earth's crust and the non-weapon isotope of uranium-238. Additionally, in this research it is appropriate to include the non-nuclear processes as the various forms of luminescences and the quasi-nuclear Cerenkov luminescence, since fluorescence can be induced by nuclear radiation, as is Cerenkov radiation; chemiluminescence can be initiated by nuclear radiation, and the secondary processes of nuclear radiation caused by the Compton effect, the (Irene) Curie effect, and the unusual and unique effect of a 3 He alpha-particle reacting oppositely from the beta-ray decay of 3 H, can influence and produce all the known luminescences. The conclusions from the small amount of research carried out are predominantly tentative and even conjectural. The device described is being called a nuclear electrophorus since its functional properties are the same as the static electricity-producing electrophorus of the late 19th Century

  13. RADCHEM - Radiochemical procedures for the determination of Sr, U, Pu, Am and Cm

    Energy Technology Data Exchange (ETDEWEB)

    Sidhu, R. [Inst. for Energy Technology (Norway)

    2006-04-15

    An accurate determination of radionuclides from various sources in the environment is essential for assessment of the potential hazards and suitable countermeasures both in case of accidents, authorised release and routine surveillance. Reliable radiochemical separation and detection techniques are needed for accurate determination of alpha and beta emitters. Rapid analytical methods are needed in case of an accident for early decision-making. The objective of this project has been to compare and evaluate radiochemical procedures used at Nordic laboratories for the determination of strontium, uranium, plutonium, americium and curium. To gather detailed information on the procedures in use, a questionnaire regarding various aspects of radionuclide determination was developed and distributed to all (sixteen) relevant laboratories in the Nordic countries. The response and the procedures used by each laboratory were then discussed between those who answered the questionnaire. This report summaries the findings and gives recommendation on suitable practice. (au)

  14. RADCHEM - Radiochemical procedures for the determination of Sr, U, Pu, Am and Cm

    International Nuclear Information System (INIS)

    Sidhu, R.

    2006-04-01

    An accurate determination of radionuclides from various sources in the environment is essential for assessment of the potential hazards and suitable countermeasures both in case of accidents, authorised release and routine surveillance. Reliable radiochemical separation and detection techniques are needed for accurate determination of alpha and beta emitters. Rapid analytical methods are needed in case of an accident for early decision-making. The objective of this project has been to compare and evaluate radiochemical procedures used at Nordic laboratories for the determination of strontium, uranium, plutonium, americium and curium. To gather detailed information on the procedures in use, a questionnaire regarding various aspects of radionuclide determination was developed and distributed to all (sixteen) relevant laboratories in the Nordic countries. The response and the procedures used by each laboratory were then discussed between those who answered the questionnaire. This report summaries the findings and gives recommendation on suitable practice. (au)

  15. The coupled process laboratory test of highly compacted bentonite

    International Nuclear Information System (INIS)

    Shen Zhenyao; Li Guoding; Li Shushen; Wang Chengzu

    2004-01-01

    Highly compacted bentonite blocks have been heated and hydrated in the laboratory in order to simulate the thermo-hydro-mechanical (THM) coupled processes of buffer material in a high-level radioactive waste (HLW) repository. The experiment facility, which is composed of experiment barrel, heated system, high pressure water input system, temperature measure system, water content measure system and swelling stress system, is introduced in this paper. The steps of the THM coupled experiment are also given out in detail. There are total 10 highly compacted bentonite blocks used in this test. Experimental number 1-4 are the tests with the heater and the hydrated process, which temperature distribution vs. time and final moisture distribution are measured. Experimental number 5-8 are the tests with the heater and without the hydrated process, which temperature distribution vs. time and final moisture distribution are measured. Experimental number 9-10 are the tests with the heater and the hydrated process, which temperature distribution vs. time, final moisture distribution and the swelling stress distribution at some typical points vs. time are measured. The maximum test time is nearly 20 days and the minimum test time is only 8 hours. The results show that the temperature field is little affected by hydration process and stress condition, but moisture transport and stress distribution are a little affected by the thermal gradient. The results also show that the water head difference is the mainly driving force of hydration process and the swelling stress is mainly from hydration process. It will great help to understand better about heat and mass transfer in porous media and the THM coupled process in actual HLW disposal. (author)

  16. Radiochemical schemes of obtaining 89Sr and 90Y radionuclides

    International Nuclear Information System (INIS)

    Usarov, Z. O.

    2010-03-01

    Key words: strontium-89, yttrium-90, extraction and extraction-chromatographic purification of radionuclides, radiopharmaceuticals. Subjects of research: strontium-89 and yttrium-90 radionuclides and their chloride forms. Purpose of work is developing of radiochemical technologies on obtaining of 89 Sr and 90 Y on the WWR-SM reactor with high radionuclide purity. Methods of research: extraction and extraction-chromatographic methods of radionuclides separation, beta- and gamma-spectrometric methods of activity measuring. The results obtained and their novelty: Were determined the conformity to laws of Y and Sr distribution in two-phase systems TBP-HNO 3 , TBP-NH 4 NO 3 , TBP-HCI, HDEHP-NO 3 , HDEHP-NH 4 NO 3 and HDEHP-HCI. Were determined the conformity to laws of Y and Sr distribution in systems with craun ethers DB-18K-6 and DTBDB-18K-6 from water solutions of HNO 3 . Radiochemical technologies on obtaining of 89 Sr and 90 Y radionuclides including radiochemical process of yttrium target with using the systems TBP-HNO 3 and HDEHP/Teflone were developed. Practical value: the radiochemical technology of obtaining 89 Sr with high radionuclide purity was developed. The method of preparation a chloride compound of 89 SrCl 2 which is used as a drug form for preparation of 89 Sr- 'Metastron' was developed. The relatively simple method of on the way obtaining 90 Y in the reactor with high radionuclidic purity that is useful for follow using in medical practice was offered. Degree of embed and economic effectivity: the developed technologies have approbation in manufacturing conditions in Radiopreparat Enterprise of INP AS RU and were offered for receiving of domestic preparations against of import foreign analogues. The statement about using the invention by obtained patent is attached to dissertation. Field of application: the received results will be introduced in manufacture at Radiopreparat Enterprise of INP AS RU for receiving of domestic preparations

  17. The Sodium Process Facility at Argonne National Laboratory-West

    International Nuclear Information System (INIS)

    Michelbacher, J.A.; Henslee, S.P.; McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

    1998-01-01

    Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal

  18. The Sodium Process Facility at Argonne National Laboratory-West

    Energy Technology Data Exchange (ETDEWEB)

    Michelbacher, J.A.; Henslee, S.P. McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

    1998-07-01

    Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal.

  19. Development of Radiochemical Separation Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eil Hee; Kim, K. W.; Yang, H. B. (and others)

    2007-06-15

    This project of the second phase was aimed at the development of basic unit technologies for advanced partitioning, and the application tests of pre-developed partitioning technologies for separation of actinides by using a simulated multi-component radioactive waste containing Am, Np, Tc, U and so on. The goals for recovery yield of TRU, and for purity of Tc are high than 99% and about 99%, respectively. The work scopes and contents were as follows. 1). For the development of basic unit technologies for advanced partitioning. 1. Development of technologies for co-removal of TRU and for mutual separation of U and TRU with a reduction-complexation reaction. 2. Development of extraction system for high-acidity co-separation of An(+3) and Ln(+3) and its radiolytic evaluation. 3. Synthesis of extractants for the selective separation of An(+3) and its relevant extraction system development. 4. Development of a hybrid system for the recovery of noble metals and its continuous separation tests. 5. Development of electrolytic system for the decompositions of N-NO3 and N-NH3 compounds to nitrogen gas. 2). For the application test of pre-developed partitioning technologies for the separation of actinide elements in a simulated multi-component solution equivalent to HLW level. 1. Co-separation of Tc, Np and U by a (TBP-TOA)/NDD system. 2. Mutual-separation of Am, Cm and RE elements by a (Zr-DEHPA)/NDD system. All results will be used as the fundamental data for the development of advanced partitioning process in the future.

  20. Laboratory Simulations of Martian and Venusian Aeolian Processes

    Science.gov (United States)

    Greeley, Ronald

    1999-01-01

    With the flyby of the Neptune system by Voyager, the preliminary exploration of the Solar System was accomplished. Data have been returned for all major planets and satellites except the Pluto system. Results show that the surfaces of terrestrial planets and satellites have been subjected to a wide variety of geological processes. On solid- surface planetary objects having an atmosphere, aeolian processes are important in modifying their surfaces through the redistribution of fine-grained material by the wind. Bedrock may be eroded to produce particles and the particles transported by wind for deposition in other areas. This process operates on Earth today and is evident throughout the geological record. Aeolian processes also occur on Mars, Venus, and possibly Titan and Triton, both of which are outer planet satellites that have atmospheres. Mariner 9 and Viking results show abundant wind-related landforms on Mars, including dune fields and yardangs (wind-eroded hills). On Venus, measurements made by the Soviet Venera and Vega spacecraft and extrapolations from the Pioneer Venus atmospheric probes show that surface winds are capable of transporting particulate materials and suggest that aeolian processes may operate on that planet as well. Magellan radar images of Venus show abundant wind streaks in some areas, as well as dune fields and a zone of possible yardangs. The study of planetary aeolian processes must take into account diverse environments, from the cold, low-density atmosphere of Mars to the extremely hot, high- density Venusian atmosphere. Factors such as threshold wind speeds (minimum wind velocity needed to move particles), rates of erosion and deposition, trajectories of windblown particles, and aeolian flow fields over various landforms are all important aspects of the problem. In addition, study of aeolian terrains on Earth using data analogous to planetary data-collection systems is critical to the interpretation of spacecraft information and

  1. Plutonium scrap processing at the Los Alamos Scientific Laboratory

    International Nuclear Information System (INIS)

    Nixon, A.E.; McKerley, B.J.; Christensen, E.L.

    1980-01-01

    The Los Alamos Scientific Laboratory currently has the newest plutonium handling facility in the nation. Los Alamos has been active in the processing of plutonium almost since the discovery of this man-made element in 1941. One of the functions of the new facility is the processing of plutonium scrap generated at LASL and other sites. The feed for the scrap processing program is extremely varied, and a wide variety of contaminants are often encountered. Depending upon the scrap matrix and contaminants present, the majority of material receives a nitric acid/hydrofluoric acid or nitric acid/calcium fluoride leach. The plutonium nitrate solutions are then loaded onto an anion exchange column charged with DOWEX 1 x 4, 50 to 100 mesh, nitrate form resin. The column is eluted with 0.48 M hydroxyl amine nitrate. The Pu(NO 3 ) 3 is then precipitated as plutonium III oxalate which is calcined at 450 to 500 0 C to yield a purified PuO 2 product

  2. Effects of delayed laboratory processing on platelet serotonin levels.

    Science.gov (United States)

    Sanner, Jennifer E; Frazier, Lorraine; Udtha, Malini

    2013-01-01

    Despite the availability of established guidelines for measuring platelet serotonin, these guidelines may be difficult to follow in a hospital setting where time to processing may vary from sample to sample. The purpose of this study was to evaluate the effect of the time to processing of human blood samples on the stability of the enzyme-linked immunosorbent assay (ELISA) for the determination of platelet serotonin levels in human plasma. Human blood samples collected from a convenience sample of eight healthy volunteers were analyzed to determine platelet serotonin levels from plasma collected in ethylene diamine tetra acetic acid (EDTA) tubes and stored at 4°C for 3 hr, 5 hr, 8 hr, and 12 hr. Refrigeration storage at 4°C for 3 hr, 5 hr, 8 hr, and 12 hr altered the platelet serotonin measurement when compared to immediate processing. The bias for the samples stored at 4°C for 3 hr was 102.3 (±217.39 ng/10(9) platelets), for 5 hr was 200.1 (±132.76 ng/10(9) platelets), for 8 hr was 146.9 (±221.41 ng/10(9) platelets), and for 12 hr was -67.6 (±349.60 ng/10(9) platelets). Results from this study show that accurate measurement of platelet serotonin levels is dependent on time to processing. Researchers should therefore follow a standardized laboratory guideline for obtaining immediate platelet serotonin levels after blood sample collection.

  3. Potential of Laboratory Execution Systems (LESs) to Simplify the Application of Business Process Management Systems (BPMSs) in Laboratory Automation.

    Science.gov (United States)

    Neubert, Sebastian; Göde, Bernd; Gu, Xiangyu; Stoll, Norbert; Thurow, Kerstin

    2017-04-01

    Modern business process management (BPM) is increasingly interesting for laboratory automation. End-to-end workflow automation and improved top-level systems integration for information technology (IT) and automation systems are especially prominent objectives. With the ISO Standard Business Process Model and Notation (BPMN) 2.X, a system-independent and interdisciplinary accepted graphical process control notation is provided, allowing process analysis, while also being executable. The transfer of BPM solutions to structured laboratory automation places novel demands, for example, concerning the real-time-critical process and systems integration. The article discusses the potential of laboratory execution systems (LESs) for an easier implementation of the business process management system (BPMS) in hierarchical laboratory automation. In particular, complex application scenarios, including long process chains based on, for example, several distributed automation islands and mobile laboratory robots for a material transport, are difficult to handle in BPMSs. The presented approach deals with the displacement of workflow control tasks into life science specialized LESs, the reduction of numerous different interfaces between BPMSs and subsystems, and the simplification of complex process modelings. Thus, the integration effort for complex laboratory workflows can be significantly reduced for strictly structured automation solutions. An example application, consisting of a mixture of manual and automated subprocesses, is demonstrated by the presented BPMS-LES approach.

  4. Diaphragms obtained by radiochemical grafting in PTFE

    International Nuclear Information System (INIS)

    Nenner, T.; Fahrasmane, A.

    1984-01-01

    Diaphragms for alkaline water electrolysis are prepared by radiochemical grafting of PTFE fabric with styrene, which is later on sulfonated, or with acrylic acid. The diaphragms obtained are mechanically resistant to potash at temperatures up to 200 0 C, but show some degrafting, which limits the lifetime. The sulfonated styrene group has been found to be more stable in electrolysis than the acrylic acid. In both cases, the incorporation of a cross-linking agent like divinyl benzene improves the lifetime of the diaphragms. Electrolysis during 500 hours at 120 0 C and 10 kAm 2 could be performed. (author)

  5. 13th Radiochemical Conference. Booklet of Abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    The Conference included the following sessions: (i) Opening plenary presentations (6 contributions); (ii) Chemistry of natural radionuclides, discovery of radium and polonium (6 verbal presentations + 5 poster presentations); (iii) Radionuclides in the environment, radioecology (29 + 48); (iv) Activation analysis and other radioanalytical methods (36 + 49); (v) Ionizing radiation in science and technology (12 + 12); (vi) Chemistry of actinide and trans-actinide elements (11 + 14); (vii) Separation methods, speciation (18 + 41); (viii) Production and application of radionuclides (14 + 29); and (ix) Radiochemical problems in nuclear waste management (12 + 22). The majority of verbal presentations has been input to INIS, mostly in the form of the full authors` abstracts. (P.A.)

  6. 13th Radiochemical Conference. Booklet of Abstracts

    International Nuclear Information System (INIS)

    1998-04-01

    The Conference included the following sessions: (i) Opening plenary presentations (6 contributions); (ii) Chemistry of natural radionuclides, discovery of radium and polonium (6 verbal presentations + 5 poster presentations); (iii) Radionuclides in the environment, radioecology (29 + 48); (iv) Activation analysis and other radioanalytical methods (36 + 49); (v) Ionizing radiation in science and technology (12 + 12); (vi) Chemistry of actinide and trans-actinide elements (11 + 14); (vii) Separation methods, speciation (18 + 41); (viii) Production and application of radionuclides (14 + 29); and (ix) Radiochemical problems in nuclear waste management (12 + 22). The majority of verbal presentations has been input to INIS, mostly in the form of the full authors' abstracts. (P.A.)

  7. The sodium process facility at Argonne National Laboratory - West

    International Nuclear Information System (INIS)

    Michelbacher, J.A.; Henslee, S.P.; McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

    1997-01-01

    Argonne National Laboratory - West (ANL-W) has approximately 680,000 liters (180,000 gallons) of raw sodium stored in facilities on site. As mandated by the State of Idaho and the United States Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The SPF was designed to react elemental sodium to sodium carbonate through two-stages involving caustic process and carbonate process steps. The sodium is first reacted to sodium hydroxide in the caustic process step. The caustic process step involves the injection of sodium into a nickel reaction vessel filled with a 50 wt% solution of sodium hydroxide. Water is also injected, controlling the boiling point of the solution. In the carbonate process, the sodium hydroxide is reacted with carbon dioxide to form sodium carbonate. This dry powder, similar in consistency to baking soda, is a waste form acceptable for burial in the State of Idaho as a non-hazardous, radioactive waste. The caustic process was originally designed and built in the 1980s for reacting the 290,000 liters (77,000 gallons) of primary sodium from the Fermi-1 Reactor to sodium hydroxide. The hydroxide was slated to be used to neutralize acid products from the PUREX process at the Hanford site. However, changes in the DOE mission precluded the need for hydroxide and the caustic process was never operated. With the shutdown of the Experimental Breeder Reactor-II (EBR-II), the necessity for a facility to react sodium was identified. In order to comply with Resource Conservation and Recovery Act (RCRA) requirements, the sodium had to be converted into a waste form acceptable for disposal in a Sub-Title D low-level radioactive waste disposal facility. Sodium hydroxide is a RCRA

  8. Laboratory Spacecraft Data Processing and Instrument Autonomy: AOSAT as Testbed

    Science.gov (United States)

    Lightholder, Jack; Asphaug, Erik; Thangavelautham, Jekan

    2015-11-01

    Recent advances in small spacecraft allow for their use as orbiting microgravity laboratories (e.g. Asphaug and Thangavelautham LPSC 2014) that will produce substantial amounts of data. Power, bandwidth and processing constraints impose limitations on the number of operations which can be performed on this data as well as the data volume the spacecraft can downlink. We show that instrument autonomy and machine learning techniques can intelligently conduct data reduction and downlink queueing to meet data storage and downlink limitations. As small spacecraft laboratory capabilities increase, we must find techniques to increase instrument autonomy and spacecraft scientific decision making. The Asteroid Origins Satellite (AOSAT) CubeSat centrifuge will act as a testbed for further proving these techniques. Lightweight algorithms, such as connected components analysis, centroid tracking, K-means clustering, edge detection, convex hull analysis and intelligent cropping routines can be coupled with the tradition packet compression routines to reduce data transfer per image as well as provide a first order filtering of what data is most relevant to downlink. This intelligent queueing provides timelier downlink of scientifically relevant data while reducing the amount of irrelevant downlinked data. Resulting algorithms allow for scientists to throttle the amount of data downlinked based on initial experimental results. The data downlink pipeline, prioritized for scientific relevance based on incorporated scientific objectives, can continue from the spacecraft until the data is no longer fruitful. Coupled with data compression and cropping strategies at the data packet level, bandwidth reductions exceeding 40% can be achieved while still downlinking data deemed to be most relevant in a double blind study between scientist and algorithm. Applications of this technology allow for the incorporation of instrumentation which produces significant data volumes on small spacecraft

  9. Computer aided piping layout design in radiochemical plants- an improved software package

    International Nuclear Information System (INIS)

    Raju, R.P.; Siddiqui, H.R.

    1995-01-01

    A software package was developed and it was successfully implemented for the piping layout design of the four process cells of the Kalpakkam Reprocessing Project. This paper discusses in detail all the improvements and modifications that are being carried out in the package so that it becomes more meaningful and useful for implementation for the forthcoming radiochemical plants

  10. Simulation of the planetary interior differentiation processes in the laboratory.

    Science.gov (United States)

    Fei, Yingwei

    2013-11-15

    A planetary interior is under high-pressure and high-temperature conditions and it has a layered structure. There are two important processes that led to that layered structure, (1) percolation of liquid metal in a solid silicate matrix by planet differentiation, and (2) inner core crystallization by subsequent planet cooling. We conduct high-pressure and high-temperature experiments to simulate both processes in the laboratory. Formation of percolative planetary core depends on the efficiency of melt percolation, which is controlled by the dihedral (wetting) angle. The percolation simulation includes heating the sample at high pressure to a target temperature at which iron-sulfur alloy is molten while the silicate remains solid, and then determining the true dihedral angle to evaluate the style of liquid migration in a crystalline matrix by 3D visualization. The 3D volume rendering is achieved by slicing the recovered sample with a focused ion beam (FIB) and taking SEM image of each slice with a FIB/SEM crossbeam instrument. The second set of experiments is designed to understand the inner core crystallization and element distribution between the liquid outer core and solid inner core by determining the melting temperature and element partitioning at high pressure. The melting experiments are conducted in the multi-anvil apparatus up to 27 GPa and extended to higher pressure in the diamond-anvil cell with laser-heating. We have developed techniques to recover small heated samples by precision FIB milling and obtain high-resolution images of the laser-heated spot that show melting texture at high pressure. By analyzing the chemical compositions of the coexisting liquid and solid phases, we precisely determine the liquidus curve, providing necessary data to understand the inner core crystallization process.

  11. Radiochemical analyses of several spent fuel Approved Testing Materials

    International Nuclear Information System (INIS)

    Guenther, R.J.; Blahnik, D.E.; Wildung, N.J.

    1994-09-01

    Radiochemical characterization data are described for UO 2 and UO 2 plus 3 wt% Gd 2 O 3 commercial spent nuclear fuel taken from a series of Approved Testing Materials (ATMs). These full-length nuclear fuel rods include MLA091 of ATM-103, MKP070 of ATM-104, NBD095 and NBD131 of ATM-106, and ADN0206 of ATM-108. ATMs 103, 104, and 106 were all irradiated in the Calvert Cliffs Nuclear Power Plant (Reactor No.1), a pressurized-water reactor that used fuel fabricated by Combustion Engineering. ATM-108 was part of the same fuel bundle designed as ATM-105 and came from boiling-water reactor fuel fabricated by General Electric and irradiated in the Cooper Nuclear Power Plant. Rod average burnups and expected fission gas releases ranged from 2,400 to 3,700 GJ/kgM. (25 to 40 Mwd/kgM) and from less than 1% to greater than 10%, respectively, depending on the specific ATM. The radiochemical analyses included uranium and plutonium isotopes in the fuel, selected fission products in the fuel, fuel burnup, cesium and iodine on the inner surfaces of the cladding, 14 C in the fuel and cladding, and analyses of the gases released to the rod plenum. Supporting examinations such as fuel rod design and material descriptions, power histories, and gamma scans used for sectioning diagrams are also included. These ATMs were examined as part of the Materials Characterization Center Program conducted at Pacific Northwest Laboratory provide a source of well-characterized spent fuel for testing in support of the US Department of Energy Office of Civilian Radioactive Waste Management Program

  12. IN10 data processing on the Rutherford Laboratory IBM 360

    International Nuclear Information System (INIS)

    Howells, W.S.; Anderson, I.S.

    1978-09-01

    This report described modifications made to some of the IN10 spectrometer data analysis programs in use at the Institut Laue-Langevin, Grenoble in order that they may be used on the IBM 360 system at the Rutherford Laboratory. Fuller descriptions of the programs are contained in the original manual (Users' Guide to Processing IN10 Data by W S Howells, ILL Internal Report (1977). Programs discussed are: a) FAST. A program for fitting Lorentzians to raw data. This is a modification of the ILL programs FAST and HAST. b) SUPER. A convolution program for fitting quasielastic peaks to corrected data. This program is based on the ILL program SUPER. c) SAND. A convolution program for fitting an elastic and a Quasielastic peak to data. This is similar to the ILL version of SAND. d) SWIFT. A program similar to SUPER but faster. It is based on the ILL program CONTTY. Before using these programs users must consult the NBRU in order to obtain an account number and a user identifier. (U.K.)

  13. Plasma separation process: Magnet move to Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1989-07-01

    This is the final report on the series of operations which culminated with the delivery of the Plasma Separation Process prototype magnet system (PMS) to Building K1432 at Oak Ridge National Laboratory (ORNL). This procedure included real time monitoring of the cold mass support strut strain gauges and an in-cab rider to monitor the instrumentation and direct the driver. The primary technical consideration for these precautions was the possibility of low frequency resonant vibration of the cold mass when excited by symmetrical rough road conditions at specific speeds causing excess stress levels in the support struts and consequent strut failure. A secondary consideration was the possibility of high acceleration loads due to sudden stops, severe road conditions, of impacts. The procedure for moving and transportation to ORNL included requirements for real time continuous monitoring of the eight strut stain gauges and three external accelerometers. Because the strain gauges had not been used since the original magnet cooldown, it was planned to verify their integrity during magnet warmup. The measurements made from the strut strain gauges resulted in stress values that were physically impossible. It was concluded that further evaluation was necessary to verify the usefulness of these gauges and whether they might be faulty. This was accomplished during the removal of the magnet from the building. 6 figs., 1 tab

  14. Oil bioremediation processes in Brazilian marine environments : laboratory simulations

    International Nuclear Information System (INIS)

    Souza, E.S.; Triguis, J.A.

    2003-01-01

    Bioremediation methods have been used in Brazil to remediate contaminated soils from refinery residues. In particular, bioremediation is a process that can reduce the amount of oil that reaches shorelines, by enhancing natural biodegradation. This presentation presents the results of a laboratory study in which seawater contaminated with light crude oil was bioremediated in a period of 28 days using NPK fertilizer. Whole oil gas chromatography and gas chromatography-mass spectrometry analyses of the hydrocarbon fractions were used to determine the extent of oil biodegradation. It was determined that natural degradation occurred in the first 4 days, and mostly through the evaporation of light end n-alkanes. Biodegradation of n-alkanes was found to be most effective after 7 days, and no changes were observed in the relative abundance of steranes and triterpanes. It appears that the addition of NPK nutrient reduces the biodegradation potential of polyaromatic compounds. Seawater samples were also measured to determine the efficiency of bioremediation. The use of NPK fertilizer resulted in higher toxicity after 14 days probably due to the creation of metabolites as polyaromatic compounds biodegrade. Non toxic levels were found to be reestablished after 28 days of bioremediation. 16 refs., 4 tabs., 6 figs

  15. Computer aided design of piping for a radiochemical plant

    Energy Technology Data Exchange (ETDEWEB)

    Selvaraj, P G; Chandrasekhar, A; Chandrasekar, A V [Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India); Raju, R P; Mahudeeswaran, K V; Kumar, S V [Reprocessing Group, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    In a radiochemical plant such as reprocessing plants, process equipment, storage tanks, liquid transfer systems and the associated pipe lines etc. are housed in series of concrete cells. Availability of limited cell space/volume, provision of various modes of liquid transfers with associated redundancies and instrumentation lines with standby alternatives increase the overall piping density. Designing such high density piping layout without interference is quite complex and needs lot of human efforts. This paper briefly describes development of computer codes for the entire scheme of design, drafting and fabrication of piping for nuclear fuel reprocessing plant. The general organisation of various programs, their functions, the complete sequence of the scheme and the flow of data are presented. High degree of reliability of each routine, considerable error checking facilities, marking legends on the drawings, provision for scaling in drafting and accuracy to the extent of one mm in layout design are some of the important features of this scheme. (author). 1 fig.

  16. Laser materials processing applications at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Hargrove, R.S.; Dragon, E.P.; Hackel, R.P.; Kautz, D.D.; Warner, B.E.

    1993-01-01

    High power and high radiance laser technologies developed at Lawrence Livermore National Laboratory (LLNL) such as copper-vapor lasers, solid-state slab lasers, dye lasers, harmonic wavelength conversion of these lasers, and fiber optic delivery systems show great promise for material processing tasks. Evaluation of models suggests significant potential for tenfold increases in welding, cutting, and drilling performance, as well as capability for applications in emerging technologies such as micromachining, surface treatment, and stereolithography. Copper and dye laser systems are currently being developed at LLNL for uranium enrichment production facilities. The goals of this program are to develop low-cost, reliable and maintainable industrial laser systems. Chains of copper lasers currently operate at more than 1.5 kW output and achieve mean time between failures of more than 1,000 hours. The beam quality of copper vapor lasers is approximately three times the diffraction limit. Dye lasers have near diffraction limited beam quality at greater than 1.0 kW. Diode laser pumped, Nd:YAG slab lasers are also being developed at LLNL. Current designs achieve powers of greater than 1.0 kW and projected beam quality is in the two to five times diffraction limited range. Results from cutting and drilling studies in titanium and stainless steel alloys show that cuts and holes with extremely fine features can be made with dye and copper-vapor lasers. High radiance beams produce low distortion and small heat-affected zones. The authors have accomplished very high aspect ratio holes in drilling tests (> 60: 1) and features with micron scale (5-50 μm) sizes. Other, traditionally more difficult, materials such as copper, aluminum and ceramics will soon be studied in detail

  17. Clinical Laboratory Data Management: A Distributed Data Processing Solution

    OpenAIRE

    Levin, Martin; Morgner, Raymond; Packer, Bernice

    1980-01-01

    Two turn-key systems, one for patient registration and the other for the clinical laboratory have been installed and linked together at the Hospital of the University of Pennsylvania, forming the nucleus of an evolving distributed Hospital Information System.

  18. Mixing and sampling tests for Radiochemical Plant

    International Nuclear Information System (INIS)

    Ehinger, M.N.; Marfin, H.R.; Hunt, B.

    1999-01-01

    The paper describes results and test procedures used to evaluate uncertainly and basis effects introduced by the sampler systems of a radiochemical plant, and similar parameters associated with mixing. This report will concentrate on experiences at the Barnwell Nuclear Fuels Plant. Mixing and sampling tests can be conducted to establish the statistical parameters for those activities related to overall measurement uncertainties. Density measurements by state-of-the art, commercially availability equipment is the key to conducting those tests. Experience in the U.S. suggests the statistical contribution of mixing and sampling can be controlled to less than 0.01 % and with new equipment and new tests in operating facilities might be controlled to better accuracy [ru

  19. Radiochemical Analysis Methodology for uranium Depletion Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Scatena-Wachel DE

    2007-01-09

    This report provides sufficient material for a test sponsor with little or no radiochemistry background to understand and follow physics irradiation test program execution. Most irradiation test programs employ similar techniques and the general details provided here can be applied to the analysis of other irradiated sample types. Aspects of program management directly affecting analysis quality are also provided. This report is not an in-depth treatise on the vast field of radiochemical analysis techniques and related topics such as quality control. Instrumental technology is a very fast growing field and dramatic improvements are made each year, thus the instrumentation described in this report is no longer cutting edge technology. Much of the background material is still applicable and useful for the analysis of older experiments and also for subcontractors who still retain the older instrumentation.

  20. Rapid radiochemical separation of short-lived radionuclides in neutron-activated samples

    International Nuclear Information System (INIS)

    Fardy, J.

    1985-11-01

    Radiochemical separation procedures based on the removal of metal ions by columns of C 18 -bonded silica gel after selective complexation are examined and the simplicity of the method demonstrated by its application to determination of Mn, Cu and Zn in neutron-activated biological material from the following solutions (pH 0-10, sulphate concentration 0,18M and 1,44M SO 4 ): 8-hydroxyquinoline (oxine), ammonium pyrrolidinedithiocarbamate (APDC), cupferron (CUP), 1-(2-pyridylazo)-2-naphthol (PAN), 1-(2'-thiazolylazo)-2-naphthol (TAN), 4-(2-pyridylazo) resorcinol (PAR), diethylammonium diethyldithiocarbamate (DDC), potassium ethyl xanthate (PEX), acetylacetone (AcAc) or thenoyltrifluoracetone (TTA). The method is rapid and reliable and readily adaptable in all radiochemical laboratories

  1. ZZ HATCHES-18, Database for radiochemical modelling

    International Nuclear Information System (INIS)

    Heath, T.G.

    2008-01-01

    1 - Description of program or function: HATCHES is a referenced, quality assured, thermodynamic database, developed by Serco Assurance for Nirex. Although originally compiled for use in radiochemical modelling work, HATCHES also includes data suitable for many other applications e.g. toxic waste disposal, effluent treatment and chemical processing. It is used in conjunction with chemical and geochemical computer programs, to simulate a wide variety of reactions in aqueous environments. The database includes thermodynamic data (the log formation constant and the enthalpy of formation for the chemical species) for the actinides, fission products and decay products. The datasets for Ni, Tc, U, Np, Pu and Am are based on the NEA reviews of the chemical thermodynamics of these elements. The data sets for these elements with oxalate, citrate and EDTA are based on the NEA-selected values. For iso-saccharinic acid, additional data (non-selected values) have been included from the NEA review as well as data derived from other sources. HATCHES also includes data for many toxic metals and for elements commonly found in groundwaters or geological materials. HARPHRQ operates by reference to the PHREEQE master species list. Thus the thermodynamic information supplied is: a) the log equilibrium constant for the formation reaction of the requested species from the PHREEQE master species for the corresponding elements; b) the enthalpy of reaction for the formation reaction of the requested species from the PHREEQE master species for the corresponding elements. This version of HATCHES has been updated since the previous release to provide consistency with the selected data from two recent publications in the OECD Nuclear Energy Agency series on chemical thermodynamics: Chemical Thermodynamics Series Volume 7 (2005): Chemical Thermodynamics of Selenium by Aeke Olin (Chairman), Bengt Nolaeng, Lars-Olof Oehman, Evgeniy Osadchii and Erik Rosen and Chemical Thermodynamics Series Volume 8

  2. Some problems concenrning the use of automated radiochemical separation systems in destructive neutron activation analysis

    International Nuclear Information System (INIS)

    Nagy, L.G.; Toeroek, G.

    1977-01-01

    The present state of a long term program is reviewed. It was started to elaborate a remote controlled automated radiochemical processing system for the neutron activation analysis of biological materials. The system is based on wet ashing of the sample followed by reactive desorption of some volatile components. The distillation residue is passed through a series of columns filled with selective ion screening materials to remove the matrix activity. The solution is thus ''stripped'' from the interfering radioions, and it is processed to single-elements through group separations using ion-exchange chromatographic techniques. Some special problems concerning this system are treated. (a) General aspects of the construction of a (semi)automated radiochemical processing system are discussed. (b) Comparison is made between various technical realizations of the same basic concept. (c) Some problems concerning the ''reconstruction'' of an already published processing system are outlined. (T.G.)

  3. [AT THE CROSSROADS: THE ROLE OF LABORATORY MEDICINE IN THE PATIENT CARE PROCESS].

    Science.gov (United States)

    Geffen, Yuval; Zaidise, Itzhak

    2017-06-01

    In recent decades, the laboratory medicine profession has undergone significant changes due to both technological developments and economic constraints. Technological innovations support automation, provide faster and more accurate equipment, and allow increased efficiency through the use of commercial test kits. These changes, combined with budgetary constraints, have led to mergers and centralization of medical laboratories to optimize work and cut costs. While this centralization may be a business necessity, it leads to a disconnection between the laboratory and the clinical context. In addition, laboratory tests are treated as a commodity, which places emphasis on price only, rather than quality. In this article, we review the developments and changes that medical laboratories and the laboratory medicine profession have undergone in recent decades. We focus on technological and structural challenges affecting the functioning of medical laboratories and the relations between laboratory workers and medical teams. We then introduce vocational education changes required for the laboratory medicine profession. We propose defining the role of medical laboratory directors in terms of their basic training as medical doctors or doctors of science. We suggest that laboratory employees should become a reliable source of information regarding selection of appropriate test methods, processing data and presenting the results to the medical staff. Laboratory workers must deepen their clinical knowledge and become an integral part of the patient care process, along with medical and nursing staff. Special training programs for medical laboratory workers and directors must be developed in order to match the complex activities currently being conducted in laboratories.

  4. 21 CFR 111.315 - What are the requirements for laboratory control processes?

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 2 2010-04-01 2010-04-01 false What are the requirements for laboratory control... MANUFACTURING, PACKAGING, LABELING, OR HOLDING OPERATIONS FOR DIETARY SUPPLEMENTS Production and Process Control System: Requirements for Laboratory Operations § 111.315 What are the requirements for laboratory control...

  5. Humidity requirements in WSCF Laboratories

    International Nuclear Information System (INIS)

    Evans, R.A.

    1994-01-01

    The purpose of this paper is to develop and document a position on Relative Humidity (RH) requirements in the WSCF Laboratories. A current survey of equipment vendors for Organic, Inorganic and Radiochemical laboratories indicate that 25% - 80% relative humidity may meet the environmental requirements for safe operation and protection of all the laboratory equipment

  6. Facilitating Improvements in Laboratory Report Writing Skills with Less Grading: A Laboratory Report Peer-Review Process

    Directory of Open Access Journals (Sweden)

    Jennifer R. Brigati

    2015-02-01

    Full Text Available Incorporating peer-review steps in the laboratory report writing process provides benefits to students, but it also can create additional work for laboratory instructors. The laboratory report writing process described here allows the instructor to grade only one lab report for every two to four students, while giving the students the benefits of peer review and prompt feedback on their laboratory reports. Here we present the application of this process to a sophomore level genetics course and a freshman level cellular biology course, including information regarding class time spent on student preparation activities, instructor preparation, prerequisite student knowledge, suggested learning outcomes, procedure, materials, student instructions, faculty instructions, assessment tools, and sample data. T-tests comparing individual and group grading of the introductory cell biology lab reports yielded average scores that were not significantly different from each other (p = 0.13, n = 23 for individual grading, n = 6 for group grading. T-tests also demonstrated that average laboratory report grades of students using the peer-review process were not significantly different from those of students working alone (p = 0.98, n = 9 for individual grading, n = 6 for pair grading. While the grading process described here does not lead to statistically significant gains (or reductions in student learning, it allows student learning to be maintained while decreasing instructor workload. This reduction in workload could allow the instructor time to pursue other high-impact practices that have been shown to increase student learning. Finally, we suggest possible modifications to the procedure for application in a variety of settings.

  7. Facilitating improvements in laboratory report writing skills with less grading: a laboratory report peer-review process.

    Science.gov (United States)

    Brigati, Jennifer R; Swann, Jerilyn M

    2015-05-01

    Incorporating peer-review steps in the laboratory report writing process provides benefits to students, but it also can create additional work for laboratory instructors. The laboratory report writing process described here allows the instructor to grade only one lab report for every two to four students, while giving the students the benefits of peer review and prompt feedback on their laboratory reports. Here we present the application of this process to a sophomore level genetics course and a freshman level cellular biology course, including information regarding class time spent on student preparation activities, instructor preparation, prerequisite student knowledge, suggested learning outcomes, procedure, materials, student instructions, faculty instructions, assessment tools, and sample data. T-tests comparing individual and group grading of the introductory cell biology lab reports yielded average scores that were not significantly different from each other (p = 0.13, n = 23 for individual grading, n = 6 for group grading). T-tests also demonstrated that average laboratory report grades of students using the peer-review process were not significantly different from those of students working alone (p = 0.98, n = 9 for individual grading, n = 6 for pair grading). While the grading process described here does not lead to statistically significant gains (or reductions) in student learning, it allows student learning to be maintained while decreasing instructor workload. This reduction in workload could allow the instructor time to pursue other high-impact practices that have been shown to increase student learning. Finally, we suggest possible modifications to the procedure for application in a variety of settings.

  8. Radiochemical surveillance of KNK primary sodium

    International Nuclear Information System (INIS)

    Stamm, H.-H.; Stade, K.Ch.

    1987-05-01

    Radiochemical surveillance of the KNK primary sodium has been performed now for 15 years with 953 effective full-power days. The overflow method used for sodium sampling proved to be reliable. Different crucible materials have been used for different analytical tasks. The amount of radionuclides in the primary system has not given restrictions to plant operation at any time. On-line gamma spectroscopy on pipings and components of the primary circuits was accomplished in reactor downtimes. Activity depositions on the walls were dominated by Ta-182 after KNK I operation. Main deposited activities at KNK II were Mn-54 (fresh core) and after operation with failed fuel Cs-137, in cover gas areas together with Zn-65. Efficient experimental radionuclide traps for the removal of Mn-54, Zn-65 and Cs-137 from the primary coolant were tested successfully. The dose rates on primary pipes and components of KNK I and KNK II were lower by an order of magnitude compared to water-cooled reactors. This is in good agreement with experiences from LMFBR's in other countries. The resulting average yearly accumulated personal dose rate was 0.21 man-Sv at KNK, compared to 3.9 man-Sv at German light-water-cooled power reactors

  9. Radiochemical studies on amorphous zirconium phosphate

    Energy Technology Data Exchange (ETDEWEB)

    Dyer, A; Moores, G E [Salford Univ. (UK). Dept. of Chemistry and Applied Chemistry

    1981-01-01

    Amorphous zirconium phosphate (ZrP) is used in some hemodialysis machines for the regeneration of dialysate. Its function is to adsorb ammonium ions formed by the pretreatment of urea by urease. It also adsorbs Ca, Mg and K ions but leaches phosphate ions which are then removed (along with F/sup -/ ions) by a bed of hydrous zirconium oxide. The sodium form of ZrP is used although other forms have been suggested for use. The work reported here describes some preliminary radiochemical studies on the mechanism of release of phosphate ions and its possible relationship to sodium ion-exchange. /sup 32/P labelled material (HHZrP) was used for elution experiments with deionized water and buffer solutions having the pH's 4.2, 7.0 and 9.2. Buffer solutions used were as supplied by BDH. Elution was at four different temperatures in the range 293 to 363/sup 0/C. In the second series of experiments HHZrP was suspended in a NaCl solution labelled with /sup 22/Na. From this, /sup 22/Na labelled ZrP (NaHZrP) was prepared and eluted in the same way as the HHZrP. Results are given and discussed.

  10. Towards a Toolbox for a Process Innovation Laboratory

    DEFF Research Database (Denmark)

    Gong, Jie; Møller, Charles

    2011-01-01

    Driven by the global competition, process Innovation has been a challenge to large enterprises for many years. The research in this paper discusses about the theory and methods of Business Process Innovation (BPI) in designing Intelligent Supply Chains (ISC) in inter-organizations. We first review...... the BPI concepts, compare it with Business Process Improvement (BPIm) and Business Process Reengineering (BPR), and then build an analytical framework to define business process innovation from four different perspectives: management science, knowledge management, information technology and quality...

  11. Towards a Toolbox for a Process Innovation Laboratory

    DEFF Research Database (Denmark)

    Gong, Jie; Møller, Charles

    2012-01-01

    Driven by the global competition, process Innovation has been a challenge to large enterprises for many years. The research in this paper discusses about the theory and methods of Business Process Innovation (BPI) in designing Intelligent Supply Chains (ISC) in inter-organizations. We first review...... the BPI concepts, compare it with Business Process Improvement (BPIm) and Business Process Reengineering (BPR), and then build an analytical framework to define business process innovation from four different perspectives: management science, knowledge management, information technology and quality...

  12. Rapid Radiochemical Analyses in Support of Fukushima Nuclear Accident - 13196

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, Sherrod L.; Culligan, Brian K.; Hutchison, Jay B. [Savannah River National Laboratory, Building 735-B, Aiken, SC 29808 (United States)

    2013-07-01

    precipitations, followed by Sr-Resin separation and gas flow proportional counting. To achieve a lower detection limit for analysis of some of the Japanese soil samples, a 10 gram aliquot of soil was taken, acid-leached and processed with similar preconcentration chemistry. The MDA using this approach was ∼0.03 pCi/g (1.1 mBq/g)/, which is less than the 0.05-0.10 pCi/g {sup 90}Sr levels found in soil as a result of global fallout. The chemical yields observed for the Japanese soil samples was typically 75-80% and the laboratory control sample (LCS) and matrix spike (MS) results looked very good for this work Individual QC results were well within the ± 25% acceptable range and the average of these results does not show significant bias. Additional data for a radiostrontium in soil method for 50 gram samples will also be presented, which appears to be a significant step forward based on looking at the current literature, with higher chemical yields for even larger sample aliquots and lower MDA [5, 6, 7] Hou et al surveyed a wide range of separation methods for Pu in waters and environmental solid samples [8]. While there are many actinide methods in the scientific literature, few would be considered rapid due to the tedious and time-consuming steps involved. For actinide analyses in soil, a new rapid method for the determination of actinide isotopes in soil samples using both alpha spectrometry and inductively-coupled plasma mass spectrometry was employed. The new rapid soil method utilizes an acid leaching method, iron/titanium hydroxide precipitation, a lanthanum fluoride soil matrix removal step, and a rapid column separation process with TEVA Resin. The large soil matrix is removed easily and rapidly using these two simple precipitations with high chemical recoveries and effective removal of interferences. [9, 10] Vacuum box technology and rapid flow rates were used to reduce analytical time. Challenges associated with the mineral content in the volcanic soil will be

  13. A radiochemical assay for biotin in biological materials

    International Nuclear Information System (INIS)

    Hood, R.L.

    1975-01-01

    A radiochemical assay for biotin is described. The assay was sensitive to one nanogram and simple enough for routine biotin analyses. The assay yielded results which were comparable to those obtained from a microbiological assay using Lactobacillus plantarum. (author)

  14. Safety and Waste Management for SAM Radiochemical Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the radiochemical analytes included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  15. Savannah River Laboratory monthly report: 238Pu fuel form processes

    International Nuclear Information System (INIS)

    1976-01-01

    Progress in the Savannah River 238 Pu Fuel Form Program is discussed. Goals of the Savannah River Laboratory (SRL) program are to provide technical support for the transfer of the 238 Pu fuel form fabrication operations from Mound Laboratory to new facilities being built at the Savannah River Plant (SRP), to provide the technical basis for 238 Pu scrap recovery at SRP, and to assist in sustaining plant operations. During the period it was found that the density of hot-pressed 238 PuO 2 pellets decreased as the particle size of ball-milled powder decreased;the surface area of calcined 238 PuO 2 powder increased with increasing precipitation temperature and may be related to the variation in ball-milling response observed among different H Area B-Line batches; calcined PuO 2 produced by Pu(III) reverse-strike precipitation was directly fabricated into a pellet without ball milling, slugging, or sharding. The pellet had good appearance with acceptable density and dimensional stability, and heat transfer measurements and calculations showed that the use of hollow aluminum sleeves in the plutonium fuel fabrication (PuFF) storage vault reduced the temperature of shipping cans to 170 0 C and will reduce the temperature at the center of pure plutonium oxide (PPO) spheres to 580 0 C

  16. [The balanced scorecard used as a management tool in a clinical laboratory: internal business processes indicators].

    Science.gov (United States)

    Salinas La Casta, Maria; Flores Pardo, Emilio; Uris Selles, Joaquín

    2009-01-01

    to propose a set of indicators as a management tool for a clinical laboratory, by using the balanced scorecard internal business processes perspective. indicators proposed are obtained from different sources; external proficiency testing of the Valencia Community Government, by means of internal surveys and laboratory information system registers. One year testing process proportion indicators results are showed. internal management indicators are proposed (process, appropriateness and proficiency testing). The process indicators results show gradual improvement since its establishment. after one years of using a conceptually solid Balanced Scorecard Internal business processes perspective indicators, the obtained results validate the usefulness as a laboratory management tool.

  17. Literature search, review, and compilation of data for chemical and radiochemical sensors: Task 1 report

    International Nuclear Information System (INIS)

    1993-01-01

    During the next several decades, the US Department of Energy is expected to spend tens of billions of dollars in the characterization, cleanup, and monitoring of DOE's current and former installations that have various degrees of soil and groundwater contamination made up of both hazardous and mixed wastes. Each of these phases will require site surveys to determine type and quantity of hazardous and mixed wastes. It is generally recognized that these required survey and monitoring efforts cannot be performed using traditional chemistry methods based on laboratory evaluation of samples from the field. For that reason, a tremendous push during the past decade or so has been made on research and development of sensors. This report contains the results of an extensive literature search on sensors that are used or have applicability in environmental and waste management. While restricting the search to a relatively small part of the total chemistry spectrum, a sizable body of reference material is included. Results are presented in tabular form for general references obtained from data base searches, as narrative reviews of relevant chapters from proceedings, as book reviews, and as reviews of journal articles with particular relevance to the review. Four broad sensor types are covered: electrochemical processes, piezoelectric devices, fiber optics, and radiochemical processes. The topics of surface chemistry processes and biosensors are not treated separately because they often are an adjunct to one of the four sensors listed. About 1,000 tabular entries are listed, including selected journal articles, reviews of conference/meeting proceedings, and books. Literature to about mid-1992 is covered

  18. Literature search, review, and compilation of data for chemical and radiochemical sensors: Task 1 report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-01-01

    During the next several decades, the US Department of Energy is expected to spend tens of billions of dollars in the characterization, cleanup, and monitoring of DOE`s current and former installations that have various degrees of soil and groundwater contamination made up of both hazardous and mixed wastes. Each of these phases will require site surveys to determine type and quantity of hazardous and mixed wastes. It is generally recognized that these required survey and monitoring efforts cannot be performed using traditional chemistry methods based on laboratory evaluation of samples from the field. For that reason, a tremendous push during the past decade or so has been made on research and development of sensors. This report contains the results of an extensive literature search on sensors that are used or have applicability in environmental and waste management. While restricting the search to a relatively small part of the total chemistry spectrum, a sizable body of reference material is included. Results are presented in tabular form for general references obtained from data base searches, as narrative reviews of relevant chapters from proceedings, as book reviews, and as reviews of journal articles with particular relevance to the review. Four broad sensor types are covered: electrochemical processes, piezoelectric devices, fiber optics, and radiochemical processes. The topics of surface chemistry processes and biosensors are not treated separately because they often are an adjunct to one of the four sensors listed. About 1,000 tabular entries are listed, including selected journal articles, reviews of conference/meeting proceedings, and books. Literature to about mid-1992 is covered.

  19. Radiochemical separation of actinides for their determination in environmental samples and waste products

    Energy Technology Data Exchange (ETDEWEB)

    Gleisberg, B [Nuclear Engineering and Analytics Rossendorf, Inc. (VKTA), Dresden (Germany)

    1997-03-01

    The determination of low level activities of actinides in environmental samples and waste products makes high demands on radiochemical separation methods. Artificial and natural actinides were analyzed in samples form the surrounding areas of NPP and of uranium mines, incorporation samples, solutions containing radioactive fuel, solutions and solids resutling from the process, and in wastes. The activities are measured by {alpha}-spectrometry and {gamma}-spectrometry. (DG)

  20. Safety decommissioning regulations of radiochemical objects - the problem, requires urgent decision

    International Nuclear Information System (INIS)

    Rovnyj, S.I.; Arsent'eva, N.V.; Emel'yanov, N.M.; Kolesnikov, V.N.

    2001-01-01

    The necessity of planning and pursuance of the measures on decommissioning of radiochemical industry is discussed. Technological processes were stopped more than in 30 buildings and constructions of the PO Mayak. The characteristics of the technological buildings to be decommissioned were treated in the context of building peculiarities, function, character and level of contamination. An acceptable variant for reactor decommissioning invites development of the standard-legal aspects [ru

  1. Statistical analysis of radiochemical measurements of TRU radionuclides in REDC waste

    International Nuclear Information System (INIS)

    Beauchamp, J.; Downing, D.; Chapman, J.; Fedorov, V.; Nguyen, L.; Parks, C.; Schultz, F.; Yong, L.

    1996-10-01

    This report summarizes results of the study on the isotopic ratios of transuranium elements in waste from the Radiochemical Engineering Development Center actinide-processing streams. The knowledge of the isotopic ratios when combined with results of nondestructive assays, in particular with results of Active-Passive Neutron Examination Assay and Gamma Active Segmented Passive Assay, may lead to significant increase in precision of the determination of TRU elements contained in ORNL generated waste streams

  2. OPERATIONAL EXPERIENCE: UPGRADED MPC AND A SYSTEMS FOR THE RADIOCHEMICAL PLANT OF THE SIBERIAN CHEMICAL COMBINE

    International Nuclear Information System (INIS)

    RODRIGUEZ, C.; GOLOSKOKOV, I.; FISHBONE, L.; GOODEY, K.; LOOMIS, M.; CRAIN, B. JR.; LARSEN, R.

    2003-01-01

    The success of reducing the risk of nuclear proliferation through physical protection and material control/accounting systems depends upon the development of an effective design that includes consideration of the objectives of the systems and the resources available to implement the design. Included among the objectives of the design are facility characterization, definition of threat, and identification of targets. When considering resources, the designer must consider funds available, rapid low-cost elements, technology elements, human resources, and the availability of resources to sustain operation of the end system. The Siberian Chemical Combine (SCC) is a multi-function nuclear facility located in the Tomsk region of Siberia, Russia. Beginning in 1996, SCC joined with the United States Department of Energy (US/DOE) Material Protection, Control, and Accounting (MPC and A) Program to develop and implement MPC and A upgrades for the Radiochemical, Chemical Metallurgical, Conversion, Uranium Enrichment, and Reactor Plants of the SCC. At the Radiochemical Plant the MPC and A design and implementation process has been largely completed for the Plutonium Storage Facility and related areas of the Radiochemical Plant. Design and implementation of upgrades for the Radiochemical Plant include rapid physical protection upgrades such as bricking up of doors and windows, and installation of security-hardened doors. Rapid material control and accounting upgrades include installation of modern balances and bar code equipment. Comprehensive MPC and A upgrades include the installation of access controls to sensitive areas of the Plant, alarm communication and display (AC and D) systems to detect and annunciate alarm conditions, closed circuit (CCTV) systems to assess alarm conditions, central and secondary alarm station upgrades that enable security forces to assess and respond to alarm conditions, material control and accounting upgrades that include upgraded physical

  3. Software for biomedical engineering signal processing laboratory experiments.

    Science.gov (United States)

    Tompkins, Willis J; Wilson, J

    2009-01-01

    In the early 1990's we developed a special computer program called UW DigiScope to provide a mechanism for anyone interested in biomedical digital signal processing to study the field without requiring any other instrument except a personal computer. There are many digital filtering and pattern recognition algorithms used in processing biomedical signals. In general, students have very limited opportunity to have hands-on access to the mechanisms of digital signal processing. In a typical course, the filters are designed non-interactively, which does not provide the student with significant understanding of the design constraints of such filters nor their actual performance characteristics. UW DigiScope 3.0 is the first major update since version 2.0 was released in 1994. This paper provides details on how the new version based on MATLAB! works with signals, including the filter design tool that is the programming interface between UW DigiScope and processing algorithms.

  4. Signal and Image Processing Research at the Lawrence Livermore National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, R S; Poyneer, L A; Kegelmeyer, L M; Carrano, C J; Chambers, D H; Candy, J V

    2009-06-29

    Lawrence Livermore National Laboratory is a large, multidisciplinary institution that conducts fundamental and applied research in the physical sciences. Research programs at the Laboratory run the gamut from theoretical investigations, to modeling and simulation, to validation through experiment. Over the years, the Laboratory has developed a substantial research component in the areas of signal and image processing to support these activities. This paper surveys some of the current research in signal and image processing at the Laboratory. Of necessity, the paper does not delve deeply into any one research area, but an extensive citation list is provided for further study of the topics presented.

  5. Waste treatment at the Radiochemical Engineering Development Center

    International Nuclear Information System (INIS)

    Brunson, R.R.; Bond, W.D.; Chattin, F.R.; Collins, R.T.; Sullivan, G.R.; Wiles, R.H.

    1997-01-01

    At the Radiochemical Engineering Development Center (REDC) irradiated targets are processed for the recovery of valuable radioisotopes, principally transuranium nuclides. A system was recently installed for treating the various liquid alkaline waste streams for removal of excess radioactive contaminants at the REDC. Radionuclides that are removed will be stored as solids and thus the future discharge of radionuclides to liquid low level waste tank storage will be greatly reduced. The treatment system is of modular design and is installed in a hot cell (Cubicle 7) in Building 7920 at the REDC where preliminary testing is in progress. The module incorporates the following: (1) a resorcinol-formaldehyde resin column for Cs removal, (2) a cross flow filtration unit for removal of rare earths and actinides as hydroxide, and (3) a waste solidification unit. Process flowsheets for operation of the module, key features of the module design, and its computer-assisted control system are presented. Good operability of the cross flow filter system is mandatory to the successful treatment of REDC wastes. Results of tests to date on the operation of the filter in its slurry collection mode and its slurry washing mode are presented. These tests include the effects of entrained organic solvent in the waste stream feed to the filter

  6. Trace analysis measurements in high-purity aluminium by means of radiochemical neutron and proton activation analysis

    International Nuclear Information System (INIS)

    Egger, K.P.

    1987-01-01

    The aim of the study consisted in the development of efficient radiochemical composite processes and activation methods for the multi-element determination of traces within the lower ng range in high-purity aluminium. More than 50 elements were determined with the help of activation with reactor neutrons; the selective separation of matrix activity (adsorption with hydrated antimony pentoxide) led to a noticeable improvement of detectability, as compared with instrumental neutron activation analysis. Further improvements were achieved with the help of radiochemical group separations in ion exchangers or with the help of the selective separation of the pure beta-emitting elements. Over 20 elements up to high atomic numbers were determined by means of activating 13 MeV protons and 23 Me protons. In this connection, improvements of the detection limit by as a factor of 10 were achieved with radiochemical separation techniques, as compared with pure instrumental proton activation analysis. (RB) [de

  7. Procedural and developmental aspects of a multielement automatic radiochemical machine, applied to neutron irradiated biomedical samples

    International Nuclear Information System (INIS)

    Iyengar, G.V.

    1976-06-01

    This report is intended to serve as a practical guide, elaborately describing the working details and some developmental work connected with an automatic multielement radiochemical machine based on thermal neutron activation analysis using ion exchange and partition chromatography. Some of the practical aspects and personal observations after much experience with this versatile multielement method, applied to investigate the elemental composition of different biomedical matrices, are summarized. Standard reference materials are analyzed, and the data are presented with a set of gamma-spectra obtained before and after chemical separation into convenient groups suitable for gamma spectroscopy. The samples analyzed included various human and animal tissues, body fluids, IAEA biological standard reference materials, and samples from the WHO/IAEA project on 'Trace elements in relation to cardiovascular diseases'. Simplified modifications of the radiochemical processing, suitable for fast and routine analysis of clinical samples have also been discussed. (orig.) [de

  8. Ultratrace determination of platinum in biological materials via neutron activation and radiochemical separation

    International Nuclear Information System (INIS)

    Zeisler, R.; Greenberg, R.R.

    1982-01-01

    A neutron activation analysis scheme based upon a radiochemical separation of the activation products has been developed. The method utilizes the inherent sensitivity of the activation reaction 198 Pt(n,ν) 199 Pt and counting of the daughter nuclide 199 Au. This nuclide is radiochemically separated from interfering activities by homogeneous precipitation as elemental gold. The remaining interference of the secondary reaction 197 Au(n,ν) 198 Au(n,ν) 199 Au from gold in the samples is quantitatively assessed and corrected. During this process accurate gold concentrations in the samples are obtained at ultratrace levels. The analysis scheme is applied to gold and platinum determinations in biological Standard Reference Materials and human liver specimens. Gold and platinum are determined at concentrations of 5x10 - 11 g/g, and at higher levels. (author)

  9. Radiochemical syntheses further radiopharmaceuticals for positron emission tomography and new strategies for their production

    CERN Document Server

    Kilbourn, Michael R; Kilbourn, Michael R

    2015-01-01

    This book describes methods and procedures for preparing PET radiopharmaceuticals, and highlights new methods for conducting radiochemical reactions with carbon-11 (C11) and fluorine-18 (F18), which are two of the most commonly used radionuclides in positron emission tomography (PET) imaging.     Provides reliable methods for radiochemical syntheses and reactions, including all essential information to duplicate the procedure     Eliminates the time-consuming process of searching journal articles and extracting pertinent details from lengthy experimental sections or supporting information     Focuses on an emerging and important area for pharmaceutical and medical applications     Encompasses technical, regulatory, and application aspects     Includes solid-phase radiochemistry, transition-metal catalyzed radiochemistry, microfluidics, click chemistry, green radiochemistry and new strategies for radiopharmaceutical quality control.

  10. Description of the EDF research and development laboratory's radiographic picture processing system

    International Nuclear Information System (INIS)

    Brillault, B.

    1985-01-01

    A digital radiographic picture processing system has been developed at the EDF Research and Development Laboratory to be supplied to EDF radiography experts. We describe it in pointing out the difficulties of radiograph digitization but also the numerous processing possibilities. The final goal of the Laboratory work is to extract the information from industrial radiographs by digital means. Our study is divided into three parts: digitization by a microdensitometer; display, processing and quantization of flaws; and, digital storing. 5 refs

  11. Detailed Modelling of Kinetic Biodegradation Processes in a Laboratory Mmicrocosm

    Science.gov (United States)

    Watson, I.; Oswald, S.; Banwart, S.; Mayer, U.

    2003-04-01

    Biodegradation of organic contaminants in soil and groundwater usually takes places via different redox processes happening sequentially as well as simultaneously. We used numerical modelling of a long-term lab microcosm experiment to simulate the dynamic behaviour of fermentation and respiration in the aqueous phase in contact with the sandstone material, and to develop a conceptual model describing these processes. Aqueous speciation, surface complexation, mineral dissolution and precipitation were taken into account also. Fermentation can be the first step of the degradation process producing intermediate species, which are subsequently consumed by TEAPs. Microbial growth and substrate utilisation kinetics are coupled via a formulation that also includes aqueous speciation and other geochemical reactions including surface complexation, mineral dissolution and precipitation. Competitive exclusion between TEAPs is integral to the conceptual model of the simulation, and the results indicate that exclusion is not complete, but some overlap is found between TEAPs. The model was used to test approaches like the partial equilibrium approach that currently make use of hydrogen levels to diagnose prevalent TEAPs in groundwater. The observed pattern of hydrogen and acetate concentrations were reproduced well by the simulations, and the results show the relevance of kinetics, lag times and inhibition, and especially that intermediate products play a key role.

  12. Quality Control of Boar Sperm Processing : Implications from European AI Centres and Two Spermatology Reference Laboratories

    NARCIS (Netherlands)

    Riesenbeck, A; Schulze, M; Rüdiger, K; Henning, H; Waberski, D

    In recent years, increased automatization has resulted in a higher efficiency of boar semen processing in AI laboratories. Sophisticated laboratory management and efficient quality control programmes are needed for current tendencies in major pork-producing countries to reduce the sperm number per

  13. Planning for maintenance in radiochemical facilities [Paper No.: VB-2

    International Nuclear Information System (INIS)

    Balasubramanian, G.R.

    1981-01-01

    Reprocessing facilities in the earlier stages of development were planned mainly based on the concept of direct maintenance in view of the inherent advantage of man-machine interface and initial savings in the investment costs. With the mechanical processes finding a firm place in head-end operation and increase in down time necessary for elaborate decontamination efforts even for a minor modification has led to the review of the concept. For the same reason, the recent plants are based on the concept of harmonious blend of both direct and remote maintenance. The paper describes the planning needed from consideration of various aspects related to such concepts of maintenance during different phases of such type of facilities, highlighting some of the tools and special equipments to be developed for this purpose. A brief description of recent development in the field of remote maintenance is also given. Though the basic hot facility of reference is the one of reprocessing fast reactor fuels, the concepts and systems discussed are equally applicable to other radiochemical and radiometallurgical facilities also. (author)

  14. Reprocessing of spent nuclear fuel, Annex 2: Chemical-technology study of the modified 'Purex' process Chemical and radiochemical control analyses; Prerada isluzenog nuklearnog goriva, Prilog 2: Hemijsko tehnolosko ispitivanje modifikovanog 'purex' procesa

    Energy Technology Data Exchange (ETDEWEB)

    Gal, I [Institute of Nuclear Sciences Boris Kidric, Laboratorija za hemiju visoke aktivnosti, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    The objective of this task was testing of the modified purex process in the constructed separation cell, and verification of the reliability and efficiency of the process. Extractors used were 1BX, 1BS and 1C. testing was done with syntetic solutions.

  15. Radiochemical determination of zirconium by inductively coupled plasma mass spectrometry (ICPMS)

    International Nuclear Information System (INIS)

    Oliveira, Thiago C.; Oliveira, Arno Heeren de

    2013-01-01

    The zirconium isotope 93 Zr is a long-lived pure β-particle-emitting radionuclide thus occurring as one of the radionuclides found in nuclear reactors. It's produced from 235 U fission and from 92 Zr neutron activation. Due to its long half-life, 93 Zr is one of the interest radionuclides for assessment studies performance of waste storage or disposal. Measurement of 93 Zr is difficult owing to its trace level concentration and its low activity in nuclear wastes and further because its certified standards are not frequently available. The aim of this work was to apply a selective radiochemical separation methodology for 93 Zr determination in nuclear waste and analyze it by Inductively Coupled Plasma Mass Spectrometry (ICPMS). To set up the zirconium radiochemical separation procedure, a zirconium tracer solution was used in order to follow the zirconium behavior during the radiochemical separation. A tracer solution containing the main interferences, Ba, Co, Eu, Fe, Mn, Nb, Ni, Sr, and Y was used in order to verify the decontamination factor during separation process. The limit of detection of 0,039 ppb was obtained for zirconium standard solutions by ICPMS. Then, the protocol will be applied to low level waste (LLW) and intermediate level waste (ILW) from nuclear power plants. (author)

  16. Discrete event simulation of the Defense Waste Processing Facility (DWPF) analytical laboratory

    International Nuclear Information System (INIS)

    Shanahan, K.L.

    1992-02-01

    A discrete event simulation of the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) analytical laboratory has been constructed in the GPSS language. It was used to estimate laboratory analysis times at process analytical hold points and to study the effect of sample number on those times. Typical results are presented for three different simultaneous representing increasing levels of complexity, and for different sampling schemes. Example equipment utilization time plots are also included. SRS DWPF laboratory management and chemists found the simulations very useful for resource and schedule planning

  17. Radiochemical studies on environmental radioactivity in Sudan

    Energy Technology Data Exchange (ETDEWEB)

    Sam, Adam Khatir [Sudan Atomic Energy Commission, Khartoum (Sudan)

    1998-09-01

    Measurements of uranium and thorium isotopes, {sup 226} Ra, {sup 210} Po, {sup 228} Ra, {sup 40} K and fallout radionuclide {sup 137} Cs in soil samples collected from different districts in Sudan, rock phosphate samples collected from the uro and kurun rock phosphate deposits in the eastern part of the Nuba mountains in Western Sudan, and surface marine sediments and marine organisms collected from the sudanese coastal waters of the Red Sea have been made using a high resolution gamma-spectrometry, radiochemical separation and {alpha} spectrometry. The external exposure due to {gamma} radiation from the ground has been calculated. The average exposure was found to be 45.4 {+-} 21.3 nGy/h, corresponding to the annual dose equivalent of 278 {mu}Sv/y. With the exception of some areas, the calculated exposure falls within the global wide range of outdoor radiation exposure given in the UNSCEAR publications. The nation-wide average concentrations of {sup 226} Ra, {sup 238} U, {sup 232} Th, {sup 40} K and {sup 137} Cs determined were 31.6 {+-} 27, 20.1 {+-} 16.4, 19.1 {+-} 8.1, 280.3 {+-} 137.6 and 4.1 {+-} 4.3 Bq/Kg, respectively. This shows that there is little contamination due to fallout radioactivity at survey sites. The exchangeable radium fraction constitutes 19-24% of the total radium content. The data show that {sup 238} U and its decay products are the principal contributors of radioactivity in both phosphate deposits at Uro and Kurun. The equivalent mass concentrations of uranium in the Uro rock phosphate fall within the range that could be economically recovered as the by-product of fertilizer industry. The mean activity concentrations weighted by average agricultural consumption of 300 kg/ha of untreated ground rock fertilizer resulted in an annual distribution of 120.63 Bq Ra/m{sup 2} with Uro rock and 12.97, 0.21 and 4.24 Bq/m{sup 2} respectively, with Kurun rock fertilizer. The external radiation exposure over agricultural areas was estimated 23.41 x 10

  18. Radiochemical studies on environmental radioactivity in Sudan

    International Nuclear Information System (INIS)

    Sam, Adam Khatir

    1998-01-01

    Measurements of uranium and thorium isotopes, 226 Ra, 210 Po, 228 Ra, 40 K and fallout radionuclide 137 Cs in soil samples collected from different districts in Sudan, rock phosphate samples collected from the uro and kurun rock phosphate deposits in the eastern part of the Nuba mountains in Western Sudan, and surface marine sediments and marine organisms collected from the sudanese coastal waters of the Red Sea have been made using a high resolution gamma-spectrometry, radiochemical separation and α spectrometry. The external exposure due to γ radiation from the ground has been calculated. The average exposure was found to be 45.4 ± 21.3 nGy/h, corresponding to the annual dose equivalent of 278 μSv/y. With the exception of some areas, the calculated exposure falls within the global wide range of outdoor radiation exposure given in the UNSCEAR publications. The nation-wide average concentrations of 226 Ra, 238 U, 232 Th, 40 K and 137 Cs determined were 31.6 ± 27, 20.1 ± 16.4, 19.1 ± 8.1, 280.3 ± 137.6 and 4.1 ± 4.3 Bq/Kg, respectively. This shows that there is little contamination due to fallout radioactivity at survey sites. The exchangeable radium fraction constitutes 19-24% of the total radium content. The data show that 238 U and its decay products are the principal contributors of radioactivity in both phosphate deposits at Uro and Kurun. The equivalent mass concentrations of uranium in the Uro rock phosphate fall within the range that could be economically recovered as the by-product of fertilizer industry. The mean activity concentrations weighted by average agricultural consumption of 300 kg/ha of untreated ground rock fertilizer resulted in an annual distribution of 120.63 Bq Ra/m 2 with Uro rock and 12.97, 0.21 and 4.24 Bq/m 2 respectively, with Kurun rock fertilizer. The external radiation exposure over agricultural areas was estimated 23.41 x 10 -9 Gy/h and 2.59 x 10 -9 Gy/h at 1 m above ground level for Uro and Kurun rock phosphate fertilizers

  19. Radiochemical methods to enhance efficiency of α-spectral measurements

    International Nuclear Information System (INIS)

    Silkina, G.P.; Artem'ev, O.I.

    2001-01-01

    The paper describes possible ways to improve a plutonium radiochemical separation technique developed in the Khlopin Radium Institute and modify it to account for the site-specific features of samples from the former Semipalatinsk test site (STS) and enhance the alpha spectrometry efficiency.The paper describes possible ways to improve a plutonium radiochemical separation technique developed in the Khlopin Radium Institute and modify it to account for the site-specific features of samples from the former Semipalatinsk test site (STS) and enhance the alpha spectrometry efficiency. (author)

  20. Radiochemical studies of some preparation methods for phosphorus

    International Nuclear Information System (INIS)

    Loos-Neskovic, C.; Fedoroff, M.

    1983-01-01

    Various methods of radiochemical separation were tested for the determination of phosphorus in metals and alloys by neutron activation analysis. Classical methods of separation revealed some defects when they were applied to this problem. Methods using liquid extraction gave low yields and were not reproducible. Methods based on precipitation gave better results, but were not selective enough in most cases. Retention on alumina was not possible without preliminary separations. Authors studied a new radiochemical separation based on the extraction of elemental phosphorus in the gaseous phase after reduction at high temperature with carbon. Measurements with radioactive phosphorus showed that the extraction yield is better than 99%. (author)

  1. Development and Implementation of a Quality Improvement Process for Echocardiographic Laboratory Accreditation.

    Science.gov (United States)

    Gilliland, Yvonne E; Lavie, Carl J; Ahmad, Homaa; Bernal, Jose A; Cash, Michael E; Dinshaw, Homeyar; Milani, Richard V; Shah, Sangeeta; Bienvenu, Lisa; White, Christopher J

    2016-03-01

    We describe our process for quality improvement (QI) for a 3-year accreditation cycle in echocardiography by the Intersocietal Accreditation Commission (IAC) for a large group practice. Echocardiographic laboratory accreditation by the IAC was introduced in 1996, which is not required but could impact reimbursement. To ensure high-quality patient care and community recognition as a facility committed to providing high-quality echocardiographic services, we applied for IAC accreditation in 2010. Currently, there is little published data regarding the IAC process to meet echocardiography standards. We describe our approach for developing a multicampus QI process for echocardiographic laboratory accreditation during the 3-year cycle of accreditation by the IAC. We developed a quarterly review assessing (1) the variability of the interpretations, (2) the quality of the examinations, (3) a correlation of echocardiographic studies with other imaging modalities, (4) the timely completion of reports, (5) procedure volume, (6) maintenance of Continuing Medical Education credits by faculty, and (7) meeting Appropriate Use Criteria. We developed and implemented a multicampus process for QI during the 3-year accreditation cycle by the IAC for Echocardiography. We documented both the process and the achievement of those metrics by the Echocardiography Laboratories at the Ochsner Medical Institutions. We found the QI process using IAC standards to be a continuous educational experience for our Echocardiography Laboratory physicians and staff. We offer our process as an example and guide for other echocardiography laboratories who wish to apply for such accreditation or reaccreditation. © 2016, Wiley Periodicals, Inc.

  2. The platinum group elements and gold: analysis by radiochemical and instrumental neutron activation analysis and relevance to geological exploration and related problems

    Energy Technology Data Exchange (ETDEWEB)

    Reeves, S.; Plimer, I. R. [Melbourne Univ., Parkville, VIC (Australia). School of Physics

    1996-12-31

    This paper presents an overview of research conducted with the support of the Australian Institute of Nuclear Science and Engineering, at the University of Melbourne, School of Earth Sciences, Radiochemical Neutron Activation Laboratory. The primary objective of this research is to realize the high potential of the platinum group elements (PGE) and gold to the solution of petrogenetic problems, the study of magma generation and magmatic processes in mafic/ultramafic rock suites, as tracers in hydrothermal ore formation. The PGEs (Os, Ru, Ir, Pt, Pd and Rh) are among the least abundant of all elements on earth with unique properties such as high melting points, high electrical and thermal conductivity, high density, strength and toughness as alloys. They exhibit both siderophile and chalcophile characteristics and are valuable tools in providing information about magmatic processes, in particular S-saturation, as well as crystal fractionation trends. Two distinct groups of PGEs are discerned; the IPGEs (Ru, Os, Ir) and the PPGEs (Pt, Pd, Rh, Au) on the basis of their behaviour during fractionation processes. Using chondrite normalized PGE patterns it is possible to distinguish between sulphides that segregated from primitive magmas, such as komatiites, and sulphides which segregated from more fractionated magmas, such as tholeiites. It is critical to the understanding of these processes to be able to analyse key elements, such as the PGE and gold, in the parts per billion to parts per trillion range. Platinum group elements and Au were determined by radiochemical neutron activation analysis using a modified NiS fire-assay preconcentration technique, adapted from procedures first used by Robert, R.V. D. and van Wyk, E. (1975) . Detection limits are generally 0.005-0.01 ppb (Au and Ir), 0.1-0.2 ppb (Pd and Pt), and 0.1-0.5 ppb for Ru. 9 refs.

  3. The platinum group elements and gold: analysis by radiochemical and instrumental neutron activation analysis and relevance to geological exploration and related problems

    International Nuclear Information System (INIS)

    Reeves, S.; Plimer, I. R.

    1996-01-01

    This paper presents an overview of research conducted with the support of the Australian Institute of Nuclear Science and Engineering, at the University of Melbourne, School of Earth Sciences, Radiochemical Neutron Activation Laboratory. The primary objective of this research is to realize the high potential of the platinum group elements (PGE) and gold to the solution of petrogenetic problems, the study of magma generation and magmatic processes in mafic/ultramafic rock suites, as tracers in hydrothermal ore formation. The PGEs (Os, Ru, Ir, Pt, Pd and Rh) are among the least abundant of all elements on earth with unique properties such as high melting points, high electrical and thermal conductivity, high density, strength and toughness as alloys. They exhibit both siderophile and chalcophile characteristics and are valuable tools in providing information about magmatic processes, in particular S-saturation, as well as crystal fractionation trends. Two distinct groups of PGEs are discerned; the IPGEs (Ru, Os, Ir) and the PPGEs (Pt, Pd, Rh, Au) on the basis of their behaviour during fractionation processes. Using chondrite normalized PGE patterns it is possible to distinguish between sulphides that segregated from primitive magmas, such as komatiites, and sulphides which segregated from more fractionated magmas, such as tholeiites. It is critical to the understanding of these processes to be able to analyse key elements, such as the PGE and gold, in the parts per billion to parts per trillion range. Platinum group elements and Au were determined by radiochemical neutron activation analysis using a modified NiS fire-assay preconcentration technique, adapted from procedures first used by Robert, R.V. D. and van Wyk, E. (1975) . Detection limits are generally 0.005-0.01 ppb (Au and Ir), 0.1-0.2 ppb (Pd and Pt), and 0.1-0.5 ppb for Ru. 9 refs

  4. The platinum group elements and gold: analysis by radiochemical and instrumental neutron activation analysis and relevance to geological exploration and related problems

    Energy Technology Data Exchange (ETDEWEB)

    Reeves, S; Plimer, I R [Melbourne Univ., Parkville, VIC (Australia). School of Physics

    1997-12-31

    This paper presents an overview of research conducted with the support of the Australian Institute of Nuclear Science and Engineering, at the University of Melbourne, School of Earth Sciences, Radiochemical Neutron Activation Laboratory. The primary objective of this research is to realize the high potential of the platinum group elements (PGE) and gold to the solution of petrogenetic problems, the study of magma generation and magmatic processes in mafic/ultramafic rock suites, as tracers in hydrothermal ore formation. The PGEs (Os, Ru, Ir, Pt, Pd and Rh) are among the least abundant of all elements on earth with unique properties such as high melting points, high electrical and thermal conductivity, high density, strength and toughness as alloys. They exhibit both siderophile and chalcophile characteristics and are valuable tools in providing information about magmatic processes, in particular S-saturation, as well as crystal fractionation trends. Two distinct groups of PGEs are discerned; the IPGEs (Ru, Os, Ir) and the PPGEs (Pt, Pd, Rh, Au) on the basis of their behaviour during fractionation processes. Using chondrite normalized PGE patterns it is possible to distinguish between sulphides that segregated from primitive magmas, such as komatiites, and sulphides which segregated from more fractionated magmas, such as tholeiites. It is critical to the understanding of these processes to be able to analyse key elements, such as the PGE and gold, in the parts per billion to parts per trillion range. Platinum group elements and Au were determined by radiochemical neutron activation analysis using a modified NiS fire-assay preconcentration technique, adapted from procedures first used by Robert, R.V. D. and van Wyk, E. (1975) . Detection limits are generally 0.005-0.01 ppb (Au and Ir), 0.1-0.2 ppb (Pd and Pt), and 0.1-0.5 ppb for Ru. 9 refs.

  5. Pharmaceutical process chemistry: evolution of a contemporary data-rich laboratory environment.

    Science.gov (United States)

    Caron, Stéphane; Thomson, Nicholas M

    2015-03-20

    Over the past 20 years, the industrial laboratory environment has gone through a major transformation in the industrial process chemistry setting. In order to discover and develop robust and efficient syntheses and processes for a pharmaceutical portfolio with growing synthetic complexity and increased regulatory expectations, the round-bottom flask and other conventional equipment familiar to a traditional organic chemistry laboratory are being replaced. The new process chemistry laboratory fosters multidisciplinary collaborations by providing a suite of tools capable of delivering deeper process understanding through mechanistic insights and detailed kinetics translating to greater predictability at scale. This transformation is essential to the field of organic synthesis in order to promote excellence in quality, safety, speed, and cost efficiency in synthesis.

  6. Effects of processing method and moisture history on laboratory fungal resistance of wood-HDPE composites.

    Science.gov (United States)

    Craig M. Clemons; Rebecca E. Ibach

    2004-01-01

    The purpose of this study was to clarify the effects of composite processing and moisture sorption on laboratory fungal resistance of wood-plastic composites. A 2-week water soaking or cyclic boiling-drying procedure was used to infuse moisture into composites made from high-density polyethylene filled with 50 percent wood flour and processed by extrusion, compression...

  7. Minicomputer system for radiochemical analysis by coincidence spectrometry

    International Nuclear Information System (INIS)

    Brauer, F.P.; Fager, J.E.

    1979-01-01

    Minicomputer-based coincidence analysis methods have been developed for use in performing radiochemical analysis by high-resolution x- and gamma-ray coincidence spectrometry. This paper describes the data-acquisition and analysis methods develolped for qualitative and quantitative analyses of coincidence spectrometric data. Data-acquisition capabilities include both direct multiparameter pulse-height analysis and buffered list-mode acquisition

  8. Instrumentation for chemical and radiochemical monitoring in nuclear power plants

    International Nuclear Information System (INIS)

    Nordmann, F.; Ballard, G.

    2009-01-01

    This article details the instrumentation implemented in French nuclear power plants for the monitoring of chemical and radiochemical effluents with the aim of limiting their environmental impact. It describes the controls performed with chemical automata for the search for drifts, anomalies or pollution in a given circuit. The operation principles of the different types of chemical automata are explained as well as the manual controls performed on samples manually collected. Content: 1 - general considerations; 2 - objectives of the chemical monitoring: usefulness of continuous monitoring with automata, transmission to control rooms and related actions, redundancy of automata; 3 - instrumentation and explanations for the main circuits: principle of chemical automata monitoring, instrumentation of the main primary circuit, instrumentation of the main secondary circuit, instrumentation of the tertiary circuit, preparation of water makeup (demineralized water), other loops, instrumentation for effluents and environment monitoring, measurement principles of chemical automata, control and maintenance of chemical automata; 4 - manual controls after sampling; 5 - radiochemical monitoring: automatized radiochemical measurements, manual radiochemical measurements; 6 - conclusion

  9. Dry sample storage system for an analytical laboratory supporting plutonium processing

    International Nuclear Information System (INIS)

    Treibs, H.A.; Hartenstein, S.D.; Griebenow, B.L.; Wade, M.A.

    1990-01-01

    The Special Isotope Separation (SIS) plant is designed to provide removal of undesirable isotopes in fuel grade plutonium by the atomic vapor laser isotope separation (AVLIS) process. The AVLIS process involves evaporation of plutonium metal, and passage of an intense beam of light from a laser through the plutonium vapor. The laser beam consists of several discrete wavelengths, tuned to the precise wavelength required to ionize the undesired isotopes. These ions are attracted to charged plates, leaving the bulk of the plutonium vapor enriched in the desired isotopes to be collected on a cold plate. Major portions of the process consist of pyrochemical processes, including direct reduction of the plutonium oxide feed material with calcium metal, and aqueous processes for purification of plutonium in residues. The analytical laboratory for the plant is called the Material and Process Control Laboratory (MPCL), and provides for the analysis of solid and liquid process samples

  10. 21 CFR 212.60 - What requirements apply to the laboratories where I test components, in-process materials, and...

    Science.gov (United States)

    2010-04-01

    ... maintenance. Each laboratory must have and follow written procedures to ensure that equipment is routinely... 21 Food and Drugs 4 2010-04-01 2010-04-01 false What requirements apply to the laboratories where...) Laboratory Controls § 212.60 What requirements apply to the laboratories where I test components, in-process...

  11. Present status and perspective of radiochemical analysis of radionuclides in Nordic countries

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Olsson, Mattias; Togneri, Laura

    2016-01-01

    Radiochemical analysis plays a critical role in the determination of pure beta and alpha emitting radionuclides for environmental monitoring, radioecology, decommissioning, nuclear forensics and geological dating. A remarkable development on radiochemical analysis has been achieved in the past...... of radionuclides, especially in Nordic countries; some requirements from nuclear industries and research organizations, as well as perspectives on the development of radiochemical analysis are discussed....

  12. Collection, transport and general processing of clinical specimens in Microbiology laboratory.

    Science.gov (United States)

    Sánchez-Romero, M Isabel; García-Lechuz Moya, Juan Manuel; González López, Juan José; Orta Mira, Nieves

    2018-02-06

    The interpretation and the accuracy of the microbiological results still depend to a great extent on the quality of the samples and their processing within the Microbiology laboratory. The type of specimen, the appropriate time to obtain the sample, the way of sampling, the storage and transport are critical points in the diagnostic process. The availability of new laboratory techniques for unusual pathogens, makes necessary the review and update of all the steps involved in the processing of the samples. Nowadays, the laboratory automation and the availability of rapid techniques allow the precision and turn-around time necessary to help the clinicians in the decision making. In order to be efficient, it is very important to obtain clinical information to use the best diagnostic tools. Copyright © 2018 Elsevier España, S.L.U. and Sociedad Española de Enfermedades Infecciosas y Microbiología Clínica. All rights reserved.

  13. Implementation of a configurable laboratory information management system for use in cellular process development and manufacturing.

    Science.gov (United States)

    Russom, Diana; Ahmed, Amira; Gonzalez, Nancy; Alvarnas, Joseph; DiGiusto, David

    2012-01-01

    Regulatory requirements for the manufacturing of cell products for clinical investigation require a significant level of record-keeping, starting early in process development and continuing through to the execution and requisite follow-up of patients on clinical trials. Central to record-keeping is the management of documentation related to patients, raw materials, processes, assays and facilities. To support these requirements, we evaluated several laboratory information management systems (LIMS), including their cost, flexibility, regulatory compliance, ongoing programming requirements and ability to integrate with laboratory equipment. After selecting a system, we performed a pilot study to develop a user-configurable LIMS for our laboratory in support of our pre-clinical and clinical cell-production activities. We report here on the design and utilization of this system to manage accrual with a healthy blood-donor protocol, as well as manufacturing operations for the production of a master cell bank and several patient-specific stem cell products. The system was used successfully to manage blood donor eligibility, recruiting, appointments, billing and serology, and to provide annual accrual reports. Quality management reporting features of the system were used to capture, report and investigate process and equipment deviations that occurred during the production of a master cell bank and patient products. Overall the system has served to support the compliance requirements of process development and phase I/II clinical trial activities for our laboratory and can be easily modified to meet the needs of similar laboratories.

  14. Monitoring, controlling and safeguarding radiochemical streams at spent fuel reprocessing facilities with optical and gamma-ray spectroscopic methods

    International Nuclear Information System (INIS)

    Schwantes, J.M.; Bryan, S.A.; Orton, C.R.; Levitskaia, T.G.; Fraga, C.G.

    2013-01-01

    The International Atomic Energy Agency (IAEA) has established international safeguards standards for fissionable material at spent fuel reprocessing plants to ensure that significant quantities of weapons-usable nuclear material are not diverted from these facilities. For large throughput nuclear facilities, it is difficult to satisfy the IAEA safeguards accountancy goal for detection of abrupt diversion. Currently, methods to verify material control and accountancy (MCA) at these facilities require time-consuming and resource intensive destructive assay (DA). Leveraging new on-line non-destructive assay (NDA) process monitoring techniques in conjunction with the traditional and highly precise DA methods may provide an additional measure to nuclear material accountancy which would potentially result in a more timely, cost-effective and resource efficient means for safeguards verification at such facilities. By monitoring process control measurements (e.g. flowrates, temperatures, or concentrations of reagents, products or wastes), abnormal plant operations can be detected. Pacific Northwest National Laboratory (PNNL) is developing on-line NDA process monitoring technologies based upon gamma-ray and optical spectroscopic measurements to potentially reduce the time and resource burden associated with current techniques. The Multi-Isotope Process (MIP) Monitor uses gamma spectroscopy and multivariate analysis to identify off-normal conditions in process streams. The spectroscopic monitor continuously measures chemical compositions of the process streams including actinide metal ions (U, Pu, Np), selected fission products, and major stable flowsheet reagents using UV-Vis, Near IR and Raman spectroscopy. Multi-variate analysis is also applied to the optical measurements in order to quantify concentrations of analytes of interest within a complex array of radiochemical streams. This paper will provide an overview of these methods and reports on-going efforts to develop

  15. SLIPTA e-Tool improves laboratory audit process in Vietnam and Cambodia.

    Science.gov (United States)

    Nguyen, Thuong T; McKinney, Barbara; Pierson, Antoine; Luong, Khue N; Hoang, Quynh T; Meharwal, Sandeep; Carvalho, Humberto M; Nguyen, Cuong Q; Nguyen, Kim T; Bond, Kyle B

    2014-01-01

    The Stepwise Laboratory Quality Improvement Process Towards Accreditation (SLIPTA) checklist is used worldwide to drive quality improvement in laboratories in developing countries and to assess the effectiveness of interventions such as the Strengthening Laboratory Management Toward Accreditation (SLMTA) programme. However, the paper-based format of the checklist makes administration cumbersome and limits timely analysis and communication of results. In early 2012, the SLMTA team in Vietnam developed an electronic SLIPTA checklist tool. The e-Tool was pilot tested in Vietnam in mid-2012 and revised. It was used during SLMTA implementation in Vietnam and Cambodia in 2012 and 2013 and further revised based on auditors' feedback about usability. The SLIPTA e-Tool enabled rapid turn-around of audit results, reduced workload and language barriers and facilitated analysis of national results. Benefits of the e-Tool will be magnified with in-country scale-up of laboratory quality improvement efforts and potential expansion to other countries.

  16. Radiochemical determination of cesium-137 in seawater

    International Nuclear Information System (INIS)

    Cunha, I.I.L.; Munita, C.S.; Paiva, R.P.

    1990-01-01

    Seawater samples were collected from the Atlantic Ocean, in the vicinity of Ubatuba (Sao Paulo State - Brazil), acidified to pH 1 and stored in polyethylene containers. Cesium was precipitated with ammonium phospho molybdate (AMP), synthesized in our laboratory. The elements potassium and rubidium present in the seawater are also coprecipitated by AMP and adequate decontamination of the cesium is made by preparing a column by mixing Cs-137 AMP precipitate and asbestos. The interfering elements were eluted with 1.0 M ammonium nitrate solution whereas cesium was eluted with 1.0 M sodium hydroxide solution. Cesium was reprecipitated by acidifying the solution with concentrated hydrochloric acid. The overall chemical yield of cesium was of 75%. (author)

  17. Radiochemical aspects of liquid mercury spallation targets

    CERN Document Server

    Neuhausen, Joerg; Eichler, Bernd; Eller, Martin; Horn, Susanne; Schumann, Dorothea; Stora, Thierry

    2012-01-01

    Liquid metal spallation targets using mercury as target material are used in state-of-the-art high power pulsed neutron sources that have been constructed in the USA and Japan within the last decade. Similar target concepts were also proposed for next generation ISOL, beta-beam and neutrino facilities. A large amount of radioactivity will be induced in the liquid metal during operation caused by the interaction of the target material with the intense proton beam. This radioactivity - carried by a wide range of radioisotopes of all the elements of the periodic table from hydrogen up to thallium - must be considered for the assessment of safe operation and maintenance procedures as well as for a final disposal of the used target material and components. This report presents an overview on chemical investigations performed in our laboratory that deal with the behavior of radionuclides in proton irradiated mercury samples. The solubility of elements in mercury was calculated using thermodynamical data obtained by...

  18. Cyclotron production, radiochemical separation and quality control of platinum radiotracers for toxicological studies

    International Nuclear Information System (INIS)

    Bonardi, M.; Birattari, C.; Groppi, F.; Arginelli, D.; Gini, L.; Gallorini, M.

    1998-01-01

    The increasing concentration of Pt, Pd and Rh in the environment is mainly due to the release of these elements from the catalytic converters of the motorvehicles. This situation makes it necessary to carry out metallotoxicological experiments on both cell cultures and laboratory animals, in order to assess their impact on living organisms after a Long Term and Low Level Exposure (LLE). Both nuclear reactions nat Ir(p,xn) and nat Os(α,xn) were investigated in the energy range up to 45 MeV for protons and 38 MeV for alpha-particles, in order to optimize the irradiation parameters for the production of 188,189,191 Pt. Several sets of thin- and thick-target excitation functions were determined experimentally by cyclotron irradiation at both Milano and Ispra cyclotrons. This paper reports the irradiation parameters studied and adopted and two radiochemical procedures for the separation of radio-Pt from an Os target, as well as from ruthenium, iridium and gold impurities. These procedures were used to obtain very high specific activity Pt radionuclides in No Carrier Added (NCA) form. Radionuclidic, radiochemical and chemical purity measurements were carried out by the use of several techniques like γ-spectrometry, ion-exchange radio-chromatography, atomic absorption spectrometry and neutron activation analysis. (author)

  19. Methods for nuclear material control used in the basic production of a typical radiochemical plant

    International Nuclear Information System (INIS)

    Kositsyn, V.F.; Mukhortov, N.F.; Korovin, Yu.I.; Rudenko, V.S.; Petrov, A.M.

    1999-01-01

    Techniques for destructive and non-destructive assay of the component and isotopic composition of nuclear materials are described, namely gravimetric, titrimetric, coulometric, mass spectrometry, as well as those based on registration of neutron and γ radiations. Their metrologic characteristics are described. The techniques described are suggested to be used for nuclear material (NM) control and accounting purposes at the model radiochemical plant for processing irradiated fuel subassemblies from power reactors. The measurement control program is also described. This program is intended for the measurement quality assurance in the framework of NM control and accountancy system [ru

  20. Radiochemical techniques for determining some naturally occurring radionuclides in marine environmental materials

    Energy Technology Data Exchange (ETDEWEB)

    Baker, C W [Ministry of Agriculture, Fisheries and Food, Lowestoft (UK). Fisheries Lab.

    1984-06-15

    The determination of some of the naturally-occurring, alpha-emitting radionuclides in marine environmental materials, is of interest for several reasons. Radium and radon nuclides are potentially useful as oceanographic tracers. Lead and thorium nuclides may be used to study sedimentation rates, mixing processes and bioturbation in sediments. Radium and polonium nuclides are incorporated into food chains and the data may provide a perspective against which to assess the significance, for marine organisms, of exposure to radiation in a marine radioactive waste disposal situation. This paper discusses the manner in which samples are taken, and the radiochemical methods which have been employed to measure the nuclides, together with some data produced.

  1. Radiochemical determination of 210 Pb and 226Ra in petroleum sludges and scales

    International Nuclear Information System (INIS)

    Araujo, Andressa Arruda de

    2005-01-01

    The oil extraction and production, both onshore and offshore, can generate different types of residues, such as sludge, that is deposited in the water/oil separators, valves and storage tanks and scales, which form i the inner surface of ducts and equipment. Analyses already carried out through gamma spectrometry indicated the existence of high radioisotope concentration. However, radionuclides emitting low-energy gamma-rays, such as 210 Pb, are hardly detected by that technique. Consequently, there is a need to test alternative techniques to determine this and other radionuclides from the 238 U series. This work, therefore, focuses on the radiochemical determination of the concentration of 210 Pb, and 226 Ra in samples of sludge and scale from the oil processing stations of the UN-SEAL, a PETROBRAS unit responsible for the exploration and production of petroleum in Sergipe and Alagoas. The sludge and scale samples went through a preliminary process of extraction of oil, in order to separate the solid phase, where the largest fraction of the radioactivity is concentrated. After oil removal, the samples were digested using alkaline fusion as an option for dissolution. Finally, their activity concentration was determined for the samples of sludge and scales, using and alternative radiochemical method, which is based on ionic exchange. The activity concentration found for 210 Pb varied from 1,14 to 507,3 kBq kg -1 . The values for 226 Ra were higher, varying from 4,36 to 3.445 kBq kg -1 . The results for 226 Ra were then compared with the ones found for the same samples of sludge and scales using gamma spectrometry. The results of the comparison confirm the efficiency of the methodology used int hi work, that is, radiochemical determination by means of ionic exchange. (author)

  2. What's to Be Done About Laboratory Quality? Process Indicators, Laboratory Stewardship, the Outcomes Problem, Risk Assessment, and Economic Value: Responding to Contemporary Global Challenges.

    Science.gov (United States)

    Meier, Frederick A; Badrick, Tony C; Sikaris, Kenneth A

    2018-02-17

    For 50 years, structure, process, and outcomes measures have assessed health care quality. For clinical laboratories, structural quality has generally been assessed by inspection. For assessing process, quality indicators (QIs), statistical monitors of steps in the clinical laboratory total testing, have proliferated across the globe. Connections between structural and process laboratory measures and patient outcomes, however, have rarely been demonstrated. To inform further development of clinical laboratory quality systems, we conducted a selective but worldwide review of publications on clinical laboratory quality assessment. Some QIs, like seven generic College of American Pathologists Q-Tracks monitors, have demonstrated significant process improvement; other measures have uncovered critical opportunities to improve test selection and result management. The College of Pathologists of Australasia Key Indicator Monitoring and Management System has deployed risk calculations, introduced from failure mode effects analysis, as surrogate measures for outcomes. Showing economic value from clinical laboratory testing quality is a challenge. Clinical laboratories should converge on fewer (7-14) rather than more (21-35) process monitors; monitors should cover all steps of the testing process under laboratory control and include especially high-risk specimen-quality QIs. Clinical laboratory stewardship, the combination of education interventions among clinician test orderers and report consumers with revision of test order formats and result reporting schemes, improves test ordering, but improving result reception is more difficult. Risk calculation reorders the importance of quality monitors by balancing three probabilities: defect frequency, weight of potential harm, and detection difficulty. The triple approach of (1) a more focused suite of generic consensus quality indicators, (2) more active clinical laboratory testing stewardship, and (3) integration of formal

  3. The Virtual Product-Process Design Laboratory for Structured Chemical Product Design and Analysis

    DEFF Research Database (Denmark)

    Mattei, Michele; Yunus, Nor Alafiza Binti; Kalakul, Sawitree

    2014-01-01

    The objective of this paper is to present new methods for design of chemicals based formulated products and their implementation in the software, the Virtual Product-Process Design Laboratory. The new products are tailor-made blended liquid products and emulsion-based products. The new software...

  4. Analytical methods and laboratory facility for the Defense Waste Processing Facility

    International Nuclear Information System (INIS)

    Coleman, C.J.; Dewberry, R.A.; Lethco, A.J.; Denard, C.D.

    1985-01-01

    This paper describes the analytical methods, instruments, and laboratory that will support vitrification of defense waste. The Defense Waste Processing Facility (DWPF) is now being constructed at Savannah River Plant (SRP). Beginning in 1989, SRP high-level defense waste will be immobilized in borosilicate glass for disposal in a federal repository. The DWPF will contain an analytical laboratory for performing process control analyses. Additional analyses will be performed for process history and process diagnostics. The DWPF analytical facility will consist of a large shielded sampling cell, three shielded analytical cells, a laboratory for instrumental analysis and chemical separations, and a counting room. Special instrumentation is being designed for use in the analytical cells, including microwave drying/dissolution apparatus, and remote pipetting devices. The instrumentation laboratory will contain inductively coupled plasma, atomic absorption, Moessbauer spectrometers, a carbon analyzer, and ion chromatography equipment. Counting equipment will include intrinsic germanium detectors, scintillation counters, Phoswich alpha, beta, gamma detectors, and a low-energy photon detector

  5. Database of full-scale laboratory experiments on wave-driven sand transport processes

    NARCIS (Netherlands)

    van der Werf, Jebbe J.; Schretlen, Johanna Lidwina Maria; Ribberink, Jan S.; O'Donoghue, Tom

    2009-01-01

    A new database of laboratory experiments involving sand transport processes over horizontal, mobile sand beds under full-scale non-breaking wave and non-breaking wave-plus-current conditions is described. The database contains details of the flow and bed conditions, information on which quantities

  6. Gamification in Science Education: Gamifying Learning of Microscopic Processes in the Laboratory

    Science.gov (United States)

    Fleischmann, Katja; Ariel, Ellen

    2016-01-01

    Understanding and trouble-shooting microscopic processes involved in laboratory tests are often challenging for students in science education because of the inability to visualize the different steps and the various errors that may influence test outcome. The effectiveness of gamification or the use of game design elements and game-mechanics were…

  7. Oak Ridge National Laboratory Melton Valley Storage Tanks Waste Filtration Process Evaluation

    International Nuclear Information System (INIS)

    Walker, B.W.

    1998-01-01

    Cross-flow filtration is being evaluated as a pretreatment in the proposed treatment processes for aqueous high-level radioactive wastes at Oak Ridge National Laboratory (ORNL) to separate insoluble solids from aqueous waste from the Melton Valley Storage Tanks (MVST)

  8. Radiochemical analysis of concrete samples for decommission of nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Zapata-Garcia, Daniel; Wershofen, Herbert [Physikalisch-Technische Bundesanstalt (PTB), Bundesallee 100 38116, Braunschweig (Germany); Larijani, Cyrus; Sobrino-Petrirena, Maitane; Garcia-Miranda, Maria; Jerome, Simon M. [National Physical Laboratory (NPL), Hampton Road, Teddington, Middlesex, TW11 0LW (United Kingdom)

    2014-07-01

    Decommissioning of the oldest nuclear power reactors are some of the most challenging technological legacy issues many countries will face in forthcoming years, as many power reactors reach the end of their design lives. Decommissioning of nuclear reactors generates large amounts of waste that need to be classified according to their radioactive content. Approximately 10 % of the contaminated material ends up in different repositories (depending on their level of contamination) while the rest is decontaminated, measured and released into the environment or sent for recycling. Such classification needs to be done accurately in order to ensure that both the personnel involved in decommissioning and the population at large are not needlessly exposed to radiation or radioactive material and to minimise the environmental impact of such work. However, too conservative classification strategies should not be applied, in order to make proper use of radioactive waste repositories since space is limited and the full process must be cost-effective. Implicit in decommissioning and classification of waste is the need to analyse large amounts of material which usually combine a complex matrix with a non-homogeneous distribution of the radionuclides. Because the costs involved are large, it is possible to make great savings by the adoption of best available practices, such as the use of validated methods for on-site measurements and simultaneous determination of more than one radionuclide whenever possible. The work we present deals with the development and the validation of a procedure for the simultaneous determination of {sup 241}Am, plutonium isotopes, uranium isotopes and {sup 90}Sr in concrete samples. Samples are firstly ground and fused with LiBO{sub 2} and Li{sub 2}B{sub 4}O{sub 7}. After dissolution of the fused sample, silicate and alkaline elements are removed followed by radiochemical separation of the target radionuclides using extraction chromatography. Measurement

  9. Miniaturized chromatographic radiochemical procedure for 131I - MIBG

    International Nuclear Information System (INIS)

    Barboza, M.F. de; Pereira, N.S. de; Colturato, M.T.; Silva, C.P.G. da.

    1989-12-01

    Different solvents were used in paper chromatographic methods to obtain the best system in routine radiochemical control for 131 I-MIBG produced at IPEN-CNEN/SP. The dates were compared with those obtained with eletrophoresis method in buffer acetate, pH=4.5, 350V, during 40 minutes. The stability of the labeled compound store under 4 0 C was studied during 15 days. Miniaturized chromatographic procedures were established using Whatman 3MM (8x1cm) and n-butanol-:acetic acid: water (S:2:1) as a solvent. the Rf values were: 0.3 (I - ) and 1.0 (MIBG). The radiochemical purity was 99.3 and 99.2% (first day) obtained with eletrophoresis and miniaturized chromatographic procedures, respectively and, 84.7% after 15 days of its preparation. It is a rapid, practical and reproductive method. (author) [pt

  10. The performance of the remote analytical laboratory during the first fluorinel dissolution process campaign

    International Nuclear Information System (INIS)

    Lewis, L.C.; Henscheid, J.P.

    1989-01-01

    The Remote Analytical Laboratory at the Idaho Chemical Processing Plant was designed to provide analytical chemistry support to the irradiated fuel processing and associated waste processing operations. The facility was put into radioactive operation on July 7, 1986, and operated for more than a year during the first fluorinel fuel dissolution process campaign. The facility incorporated a number of innovative features and was equipped with state-of-the-art analytical instrumentation. The success of the facility is a direct function of how well the remote analytical equipment performed. The performance is discussed in this article

  11. [Quality Management and Quality Specifications of Laboratory Tests in Clinical Studies--Challenges in Pre-Analytical Processes in Clinical Laboratories].

    Science.gov (United States)

    Ishibashi, Midori

    2015-01-01

    The cost, speed, and quality are the three important factors recently indicated by the Ministry of Health, Labour and Welfare (MHLW) for the purpose of accelerating clinical studies. Based on this background, the importance of laboratory tests is increasing, especially in the evaluation of clinical study participants' entry and safety, and drug efficacy. To assure the quality of laboratory tests, providing high-quality laboratory tests is mandatory. For providing adequate quality assurance in laboratory tests, quality control in the three fields of pre-analytical, analytical, and post-analytical processes is extremely important. There are, however, no detailed written requirements concerning specimen collection, handling, preparation, storage, and shipping. Most laboratory tests for clinical studies are performed onsite in a local laboratory; however, a part of laboratory tests is done in offsite central laboratories after specimen shipping. As factors affecting laboratory tests, individual and inter-individual variations are well-known. Besides these factors, standardizing the factors of specimen collection, handling, preparation, storage, and shipping, may improve and maintain the high quality of clinical studies in general. Furthermore, the analytical method, units, and reference interval are also important factors. It is concluded that, to overcome the problems derived from pre-analytical processes, it is necessary to standardize specimen handling in a broad sense.

  12. Rapid radiochemical separation of zirconium-95 and niobium-95

    International Nuclear Information System (INIS)

    Downey, D.M.; McLaughlin, C.L.

    1983-01-01

    A rapid method for the quantitative separation of 95 Zr and 95 Nb has been developed. The method is based on the ion flotation of cationic zirconium complex ions with sodium lauryl sulfate (NaLS) from niobium which is masked with hydrogen peroxide. The separation was applied to mixtures of 95 Zr and 95 Nb initially in oxalic acid solution and quantitative recoveries of the radiochemically pure radioisotopes were obtained. (orig.)

  13. Rapid radiochemical separation of zirconium-95 and niobium-95

    Energy Technology Data Exchange (ETDEWEB)

    Downey, D.M.; McLaughlin, C.L.

    1983-01-01

    A rapid method for the quantitative separation of /sup 95/Zr and /sup 95/Nb has been developed. The method is based on the ion flotation of cationic zirconium complex ions with sodium lauryl sulfate (NaLS) from niobium which is masked with hydrogen peroxide. The separation was applied to mixtures of /sup 95/Zr and /sup 95/Nb initially in oxalic acid solution and quantitative recoveries of the radiochemically pure radioisotopes were obtained.

  14. Radiochemical regularities of migration mobility of Chernobyl' discharge radionuclides

    International Nuclear Information System (INIS)

    Skorobogat'ko, E.P.; Rybalko, S.I.

    1992-01-01

    Data on the radionuclude (RN) migration in environment later the Chernobyl' accident are generalized. Introduction of fallout of the radioactive discharge into environment causes necessity to account and to study different factors of geochemical and physicochemical character determining further RN behaviour in the medium. For a well-founded forecast of the behaviour it is necessity to use a complex of radiochemical and physicochemical research, lying in the base of radiation monitoring of environment. 1 refs

  15. Electrochemistry as a basis for radiochemical generator systems

    International Nuclear Information System (INIS)

    Bentley, G.E.; Steinkruger, F.J.; Wanek, P.M.

    1984-01-01

    Ion exchange and solvent extraction techniques have been used extensively as the basis for radiochemical generators exploiting the differences in absorption behavior between the parent nuclide and its useful daughter nuclide. Many parent/daughter pairs of nuclides have sufficiently different polarographic half wave potentials so that their electrochemical behavior may be exploited for rapid separation of the daughter from the parent with minimal contamination of the product with the parent isotope

  16. Precise turnaround time measurement of laboratory processes using radiofrequency identification technology.

    Science.gov (United States)

    Mayer, Horst; Brümmer, Jens; Brinkmann, Thomas

    2011-01-01

    To implement Lean Six Sigma in our central laboratory we conducted a project to measure single pre-analytical steps influencing turnaround time (TAT) of emergency department (ED) serum samples. The traditional approach of extracting data from the Laboratory Information System (LIS) for a retrospective calculation of a mean TAT is not suitable. Therefore, we used radiofrequency identification (RFID) chips for real time tracking of individual samples at any pre-analytical step. 1,200 serum tubes were labelled with RFID chips and were provided to the emergency department. 3 RFID receivers were installed in the laboratory: at the outlet of the pneumatic tube system, at the centrifuge, and in the analyser area. In addition, time stamps of sample entry at the automated sample distributor and communication of results from the analyser were collected from LIS. 1,023 labelled serum tubes arrived at our laboratory. 899 RFID tags were used for TAT calculation. The following transfer times were determined (median 95th percentile in min:sec): pneumatic tube system --> centrifuge (01:25/04:48), centrifuge --> sample distributor (14:06/5:33), sample distributor --> analysis system zone (02:39/15:07), analysis system zone --> result communication (12:42/22:21). Total TAT was calculated at 33:19/57:40 min:sec. Manual processes around centrifugation were identified as a major part of TAT with 44%/60% (median/95th percentile). RFID is a robust, easy to use, and error-free technology and not susceptible to interferences in the laboratory environment. With this study design we were able to measure significant variations in a single manual sample transfer process. We showed that TAT is mainly influenced by manual steps around the centrifugation process and we concluded that centrifugation should be integrated in solutions for total laboratory automation.

  17. Standardization of radiochemical techniques aiming the study of Hg volatilization and methylation in water and sediment of gold mining areas in the Amazon region

    International Nuclear Information System (INIS)

    Guimaraes, Jean Remy Davee

    1992-09-01

    Methylation of inorganic Hg in aquatic systems is a key process in the environmental cycling of this metal, not yet studied in tropical conditions. Radiochemical techniques were adapted and simplified, aiming at the study of Hg volatilization and methylation in water and sediment of gold mining areas in the Amazon region. Preliminary experiments showed, in 35 days volatilization of up to 32 % of 203 Hg 2+ added to aqueous solutions. Acid K 2 Cr 2 0 7 0.1 M solutions were not effective in 203 Hg 0 trapping and the latter was highly and irreversibly absorbed by a variety of synthetic materials commonly used in laboratory work. Considerably simplified versions of the Furutani and Rudd (1980) radiochemical technique for the determination of methylation rates in environmental samples were developed and showed efficiencies close to 90 % in tests with methyl- 2 0 3 H g standards. In-situ incubations of surface sediments were performed in the Madeira River gold mining region, Rondonia State, Brazil, and potential net Hg methylation rates (MR) of up to 1 %.g-1.h-1 were found in black-water affluent like the Mutum-Parana and Jamari rivers and in the Samuel reservoir. MRs in the Madeira River sediments were lower, ranging 10-5 to 10-3 %.g-1.h-1 . MRs obtained in incubations of samples some weeks after collection were one or two orders of magnitude lower than those resulting from in-situ incubations. Methylation in autoclaved samples was close to minimum detectable rates. MRs in surface water samples was in all cases < 7.10-7 %.ml-1.h-1. The determination of the predominant methylation sites will allow a better standardization of the technique described herein, suitable for MR determinations even under the unfavorable conditions prevailing in the Amazon region. (author)

  18. Radiochemical separation and their application to neutron activation analysis technique

    International Nuclear Information System (INIS)

    Turel, Z.R.

    2013-01-01

    The present paper discusses the development of some new, rapid and selective method for the radiochemical separation and estimation of elements such as, Co(II) 2-3 , Ir(III) 4 , Au(III) 5 , Pt(IV), Pd(II), Os(IV) 6 , Cu(II), Ag(I), Mo(VI), Ni(II), Zn(II), Cd(II), Hg(II), Cs(I), Sb(III), La(III), Sc(III) etc. using various reagents. Various parameters such as pH, time of equilibrium, effect of anions and cations, effect of reagent etc. has been determined employing tracers of the elements under consideration and will be discussed. The method is made highly selective by the use of appropriate masking agent. The stoichiometry of metal reagent is determined by the substoichiometric method. Some examples of multielemental radiochemical separation methods thus developed which have been applied in determining the elements by radiochemical thermal neutron activation analysis will be presented and discussed. The implications of the results on the reference system will also be accounted. Statistical evaluation with reference to accuracy, precision and sensitivity will also be presented

  19. Metals Processing Laboratory Users (MPLUS) Facility Annual Report FY 2002 (October 1, 2001-September 30, 2002)

    Energy Technology Data Exchange (ETDEWEB)

    Angelini, P

    2004-04-27

    The Metals Processing Laboratory Users Facility (MPLUS) is a Department of Energy (DOE), Energy Efficiency and Renewable Energy, Industrial Technologies Program, user facility designated to assist researchers in key industries, universities, and federal laboratories in improving energy efficiency, improving environmental aspects, and increasing competitiveness. The goal of MPLUS is to provide access to the specialized technical expertise and equipment needed to solve metals processing issues that limit the development and implementation of emerging metals processing technologies. The scope of work can also extend to other types of materials. MPLUS has four primary user centers: (1) Processing--casting, powder metallurgy, deformation processing (including extrusion, forging, rolling), melting, thermomechanical processing, and high-density infrared processing; (2) Joining--welding, monitoring and control, solidification, brazing, and bonding; (3) Characterization--corrosion, mechanical properties, fracture mechanics, microstructure, nondestructive examination, computer-controlled dilatometry, and emissivity; and (4) Materials/Process Modeling--mathematical design and analyses, high-performance computing, process modeling, solidification/deformation, microstructure evolution, thermodynamic and kinetic, and materials databases A fully integrated approach provides researchers with unique opportunities to address technologically related issues to solve metals processing problems and probe new technologies. Access is also available to 16 additional Oak Ridge National Laboratory (ORNL) user facilities ranging from state-of-the-art materials characterization capabilities, and high-performance computing to manufacturing technologies. MPLUS can be accessed through a standardized user-submitted proposal and a user agreement. Nonproprietary (open) or proprietary proposals can be submitted. For open research and development, access to capabilities is provided free of charge

  20. Metals Processing Laboratory Users (MPLUS) Facility Annual Report: October 1, 2000 through September 30, 2001

    Energy Technology Data Exchange (ETDEWEB)

    Angelini, P

    2004-04-27

    The Metals Processing Laboratory Users Facility (MPLUS) is a Department of Energy (DOE), Energy Efficiency and Renewable Energy, Industrial Technologies Program user facility designated to assist researchers in key industries, universities, and federal laboratories in improving energy efficiency, improving environmental aspects, and increasing competitiveness. The goal of MPLUS is to provide access to the specialized technical expertise and equipment needed to solve metals processing issues that limit the development and implementation of emerging metals processing technologies. The scope of work can also extend to other types of materials. MPLUS has four primary User Centers including: (1) Processing--casting, powder metallurgy, deformation processing including (extrusion, forging, rolling), melting, thermomechanical processing, high density infrared processing; (2) Joining--welding, monitoring and control, solidification, brazing, bonding; (3) Characterization--corrosion, mechanical properties, fracture mechanics, microstructure, nondestructive examination, computer-controlled dilatometry, and emissivity; (4) Materials/Process Modeling--mathematical design and analyses, high performance computing, process modeling, solidification/deformation, microstructure evolution, thermodynamic and kinetic, and materials data bases. A fully integrated approach provides researchers with unique opportunities to address technologically related issues to solve metals processing problems and probe new technologies. Access is also available to 16 additional Oak Ridge National Laboratory (ORNL) user facilities ranging from state of the art materials characterization capabilities, high performance computing, to manufacturing technologies. MPLUS can be accessed through a standardized User-submitted Proposal and a User Agreement. Nonproprietary (open) or proprietary proposals can be submitted. For open research and development, access to capabilities is provides free of charge while

  1. Using Self-Reflection To Increase Science Process Skills in the General Chemistry Laboratory

    Science.gov (United States)

    Veal, William R.; Taylor, Dawne; Rogers, Amy L.

    2009-03-01

    Self-reflection is a tool of instruction that has been used in the science classroom. Research has shown great promise in using video as a learning tool in the classroom. However, the integration of self-reflective practice using video in the general chemistry laboratory to help students develop process skills has not been done. Immediate video feedback and direct instruction were employed in a general chemistry laboratory course to improve students' mastery and understanding of basic and advanced process skills. Qualitative results and statistical analysis of quantitative data proved that self-reflection significantly helped students develop basic and advanced process skills, yet did not seem to influence the general understanding of the science content.

  2. Process in Developing Zebra fish Laboratory at Malaysian Nuclear Agency for Toxicology Studies

    International Nuclear Information System (INIS)

    Fazliana Mohd Saaya; Mohd Noor Hidayat Adenan; Anee Suryani Sued

    2015-01-01

    Toxicology is a branch of the very important especially in determining the safety and effectiveness of herbal products to avoid any side effects to the user. Currently, toxicity tests conducted in the laboratory is testing the toxicity of shrimp, tests on cell cultures and experimental animal tests on the rats. One of the most recent exam easier and can reduce the use of experimental rats was testing on zebra fish fish. Fish zebra fish Danio rerio, suitable for the study of toxicity, teratogenicity, genetic, oncology and neurobiology. Zebra fish system of aquarium fish zebra fish system has been in Nuclear Malaysia since 2013 but has not yet fully operational due to several factors and is in the process of moving into a new laboratory which systematically and in accordance with the enabling environment for care. The development of a new fully equipped laboratory is expected to benefit all for use in research. (author)

  3. Mood and implicit alcohol expectancy processes: predicting alcohol consumption in the laboratory.

    Science.gov (United States)

    Wardell, Jeffrey D; Read, Jennifer P; Curtin, John J; Merrill, Jennifer E

    2012-01-01

    Implicit positive alcohol expectancy (PAE) processes are thought to respond phasically to external and internal stimuli-including mood states-and so they may exert powerful proximal influences over drinking behavior. Although social learning theory contends that mood states activate mood-congruent implicit PAEs, which in turn lead to alcohol use, there is a dearth of experimental research examining this mediation model relative to observable drinking. Moreover, an expectancy theory perspective might suggest that, rather than influencing PAEs directly, mood may moderate the association between PAEs and drinking. To test these models, this study examined the role of mood in the association between implicitly measured PAE processes (i.e., latency to endorse PAEs) and immediate alcohol consumption in the laboratory. Gender differences in these processes also were examined. College students (N = 146) were exposed to either a positive, negative, or neutral mood induction procedure, completed a computerized PAE reaction time (RT) task, and subsequently consumed alcohol ad libitum. The mood manipulation had no direct effects on drinking in the laboratory, making the mediation hypothesis irrelevant. Instead, gender and mood condition moderated the association between RT to endorse PAEs and drinking in the laboratory. For males, RT to tension reduction PAEs was a stronger predictor of volume of beer consumed and peak blood alcohol concentration in the context of general arousal (i.e., positive and negative mood) relative to neutral mood. RT to PAEs did not predict drinking in the laboratory for females. The results show that PAE processes are important determinants of immediate drinking behavior in men, suggesting that biased attention to mood-relevant PAEs-as indicated by longer RTs-predicts greater alcohol consumption in the appropriate mood context. The findings also highlight the need to consider gender differences in PAE processes. This study underscores the need for

  4. Standard practices for dissolving glass containing radioactive and mixed waste for chemical and radiochemical analysis

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2000-01-01

    1.1 These practices cover techniques suitable for dissolving glass samples that may contain nuclear wastes. These techniques used together or independently will produce solutions that can be analyzed by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), atomic absorption spectrometry (AAS), radiochemical methods and wet chemical techniques for major components, minor components and radionuclides. 1.2 One of the fusion practices and the microwave practice can be used in hot cells and shielded hoods after modification to meet local operational requirements. 1.3 The user of these practices must follow radiation protection guidelines in place for their specific laboratories. 1.4 Additional information relating to safety is included in the text. 1.5 The dissolution techniques described in these practices can be used for quality control of the feed materials and the product of plants vitrifying nuclear waste materials in glass. 1.6 These pr...

  5. Transforming the Learning Environment of Undergraduate Physics Laboratories to Enhance Physics Inquiry Processes

    Directory of Open Access Journals (Sweden)

    Gregory P. Thomas

    2017-04-01

    Full Text Available Concerns persist regarding the lack of promotion of students’ scientific inquiry processes in undergraduate physics laboratories. The consensus in the literature is that, especially in the early years of undergraduate physics programs, students’ laboratory work is characterized by recipe type, step-by-step instructions for activities where the aim is often confirmation of an already well-established physics principle or concept. In response to evidence reflecting these concerns at their university, the authors successfully secured funding for this study. A mixed-method design was employed. In the 2011/2012 academic year baseline data were collected. A quantitative survey, the Undergraduate Physics Laboratory Learning Environment Scale (UPLLES was developed, validated, and used to explore students’ perceptions of their physics laboratory environments. Analysis of data from the UPLLES and from interviews confirmed the concerns evident in the literature and in a previous evaluation of laboratories undertaken in 2002. To address these concerns the activities that students were to perform in the laboratory section of the course/s were re/designed to engage students in more inquiry oriented thinking and activity. In Fall 2012, the newly developed laboratory activities and tutorials, were implemented for the first time in PHYS124; a first year course. These changes were accompanied by structured training of teaching assistants and changes to the structure of the evaluation of students’ laboratory performance. At the end of that term the UPLLES was administered (n = 266 and interviews with students conducted (n = 16 to explore their perceptions of their laboratory environments. Statistically significant differences (p<.001 between the students in the PHYS 124 classes of 2011/2012 and 2012/2013 across all dimensions were found. Effect sizes of 0.82 to 1.3, between the views of students in the first semester physics classes of 2011/2012 and 2012

  6. Safety analysis of IFR fuel processing in the Argonne National Laboratory Fuel Cycle Facility

    International Nuclear Information System (INIS)

    Charak, I; Pedersen, D.R.; Forrester, R.J.; Phipps, R.D.

    1993-01-01

    The Integral Fast Reactor (IFR) concept developed by Argonne National Laboratory (ANL) includes on-site processing and recycling of discharged core and blanket fuel materials. The process is being demonstrated in the Fuel Cycle Facility (FCF) at ANL's Idaho site. This paper describes the safety analyses that were performed in support of the FCF program; the resulting safety analysis report was the vehicle used to secure authorization to operate the facility and carry out the program, which is now under way. This work also provided some insights into safety-related issues of a commercial IFR fuel processing facility. These are also discussed

  7. Impact of virtual chemistry laboratory instruction on pre-service science teachers’ scientific process skills

    Directory of Open Access Journals (Sweden)

    Mutlu Ayfer

    2016-01-01

    Full Text Available This study aimed to investigate the impact of virtual chemistry laboratory instruction on pre-service science teachers’ scientific process skills. For this purpose, eight laboratory activities related to chemical kinetic, chemical equilibrium, thermochemistry, acids-bases, and electrochemistry were developed. Those activities were performed in virtual laboratory environment by the pre-service teachers in the experimental group and in the real laboratory environment by c the preservice teachers in the control group during eight weeks. Scientific process skills test developed by Burns, Okey and Wise [3], and translated into Turkish by Ateş and Bahar [2] was used before and after the instructions for data collection. According to results, while there was no significant difference between pre-test mean scores (U=133.500, p>0.05, significant difference between post-test mean scores was found in favour of experimental group (U=76.000, p<0.05. In addition, while no significant difference between pre-test mean scores for each sub-dimension was found, significant difference between post-test mean scores for designing investigation and formulating hypothesis skills was found in favour of experimental group.

  8. Improving Histopathology Laboratory Productivity: Process Consultancy and A3 Problem Solving

    Directory of Open Access Journals (Sweden)

    Kutsal YÖRÜKOĞLU

    2017-01-01

    Full Text Available Objective: The ISO 17020 quality program has been run in our pathology laboratory for four years to establish an action plan for correction and prevention of identified errors. In this study, we aimed to evaluate the errors that we could not identify through ISO 17020 and/or solve by means of process consulting. Process consulting is carefully intervening in a group or team to help it to accomplish its goals. Material and Method: The A3 problem solving process was run under the leadership of a ‘workflow, IT and consultancy manager’. An action team was established consisting of technical staff. A root cause analysis was applied for target conditions, and the 6-S method was implemented for solution proposals. Applicable proposals were activated and the results were rated by six-sigma analysis. Non-applicable proposals were reported to the laboratory administrator. Results: A mislabelling error was the most complained issue triggering all pre-analytical errors. There were 21 non-value added steps grouped in 8 main targets on the fish bone graphic (transporting, recording, moving, individual, waiting, over-processing, over-transaction and errors. Unnecessary redundant requests, missing slides, archiving issues, redundant activities, and mislabelling errors were proposed to be solved by improving visibility and fixing spaghetti problems. Spatial re-organization, organizational marking, re-defining some operations, and labeling activities raised the six sigma score from 24% to 68% for all phases. Operational transactions such as implementation of a pathology laboratory system was suggested for long-term improvement. Conclusion: Laboratory management is a complex process. Quality control is an effective method to improve productivity. Systematic checking in a quality program may not always find and/or solve the problems. External observation may reveal crucial indicators about the system failures providing very simple solutions.

  9. Decreasing troponin turnaround time in the emergency department using the central laboratory: A process improvement study.

    Science.gov (United States)

    Boelstler, Arlene M; Rowland, Ralph; Theoret, Jennifer; Takla, Robert B; Szpunar, Susan; Patel, Shraddha P; Lowry, Andrew M; Pena, Margarita E

    2015-03-01

    To implement collaborative process improvement measures to reduce emergency department (ED) troponin turnaround time (TAT) to less than 60min using central laboratory. This was an observational, retrospective data study. A multidisciplinary team from the ED and laboratory identified opportunities and developed a new workflow model. Process changes were implemented in ED patient triage, staffing, lab collection and processing. Data collected included TAT of door-to-order, order-to-collect, collect-to-received, received-to-result, door-to-result, ED length of stay, and hemolysis rate before (January-August, 2011) and after (September 2011-June 2013) process improvement. After process improvement and implementation of the new workflow model, decreased median TAT (in min) was seen in door-to-order (54 [IQR43] vs. 11 [IQR20]), order-to-collect (15 [IQR 23] vs. 10 [IQR12]), collect-to-received (6 [IQR8] vs. 5 [IQR5]), received-to-result (30 [IQR12] vs. 24 [IQR11]), and overall door-to-result (117 [IQR60] vs. 60 [IQR40]). A troponin TAT of <60min was realized beginning in May 2012 (59 [IQR39]). Hemolysis rates decreased (14.63±0.74 vs. 3.36±1.99, p<0.0001), as did ED length of stay (5.87±2.73h vs. 5.15±2.34h, p<0.0001). Conclusion Troponin TAT of <60min using a central laboratory was achieved with collaboration between the ED and the laboratory; additional findings include a decreased ED length of stay. Copyright © 2014 The Canadian Society of Clinical Chemists. Published by Elsevier Inc. All rights reserved.

  10. Improving Histopathology Laboratory Productivity: Process Consultancy and A3 Problem Solving.

    Science.gov (United States)

    Yörükoğlu, Kutsal; Özer, Erdener; Alptekin, Birsen; Öcal, Cem

    2017-01-01

    The ISO 17020 quality program has been run in our pathology laboratory for four years to establish an action plan for correction and prevention of identified errors. In this study, we aimed to evaluate the errors that we could not identify through ISO 17020 and/or solve by means of process consulting. Process consulting is carefully intervening in a group or team to help it to accomplish its goals. The A3 problem solving process was run under the leadership of a 'workflow, IT and consultancy manager'. An action team was established consisting of technical staff. A root cause analysis was applied for target conditions, and the 6-S method was implemented for solution proposals. Applicable proposals were activated and the results were rated by six-sigma analysis. Non-applicable proposals were reported to the laboratory administrator. A mislabelling error was the most complained issue triggering all pre-analytical errors. There were 21 non-value added steps grouped in 8 main targets on the fish bone graphic (transporting, recording, moving, individual, waiting, over-processing, over-transaction and errors). Unnecessary redundant requests, missing slides, archiving issues, redundant activities, and mislabelling errors were proposed to be solved by improving visibility and fixing spaghetti problems. Spatial re-organization, organizational marking, re-defining some operations, and labeling activities raised the six sigma score from 24% to 68% for all phases. Operational transactions such as implementation of a pathology laboratory system was suggested for long-term improvement. Laboratory management is a complex process. Quality control is an effective method to improve productivity. Systematic checking in a quality program may not always find and/or solve the problems. External observation may reveal crucial indicators about the system failures providing very simple solutions.

  11. [Study of continuous quality improvement for clinical laboratory processes via the platform of Hospital Group].

    Science.gov (United States)

    Song, Wenqi; Shen, Ying; Peng, Xiaoxia; Tian, Jian; Wang, Hui; Xu, Lili; Nie, Xiaolu; Ni, Xin

    2015-05-26

    The program of continuous quality improvement in clinical laboratory processes for complete blood count (CBC) was launched via the platform of Beijing Children's Hospital Group in order to improve the quality of pediatric clinical laboratories. Fifteen children's hospitals of Beijing Children's Hospital group were investigated using the method of Chinese adapted continuous quality improvement with PDCA (Plan-Do-Check-Action). The questionnaire survey and inter-laboratory comparison was conducted to find the existing problems, to analyze reasons, to set forth quality targets and to put them into practice. Then, targeted training was conducted to 15 children's hospitals and the second questionnaire survey, self examinations by the clinical laboratories was performed. At the same time, the Group's online internal quality control platform was established. Overall effects of the program were evaluated so that lay a foundation for the next stage of PDCA. Both quality of control system documents and CBC internal quality control scheme for all of clinical laboratories were improved through this program. In addition, standardization of performance verification was also improved, especially with the comparable verification rate of precision and internal laboratory results up to 100%. In terms of instrument calibration and mandatory diagnostic rates, only three out of the 15 hospitals (20%) failed to pass muster in 2014 from 46.67% (seven out of the 15 hospitals) in 2013. The abnormal data of intraday precision variance coefficients of the five CBC indicator parameters (WBC, RBC, Hb, Plt and Hct) of all the 15 laboratories accounted for 1.2% (2/165) in 2014, a marked decrease from 9.6% (14/145) in 2013. While the number of the hospitals using only one horizontal quality control object for daily quality control has dropped to three from five. The 15 hospitals organized a total of 263 times of training in 2014 from 101 times in 2013, up 160%. The quality improvement program for

  12. Transaction processing in the common node of a distributed function laboratory computer system

    International Nuclear Information System (INIS)

    Stubblefield, F.W.; Dimmler, D.G.

    1975-01-01

    A computer network architecture consisting of a common node processor for managing peripherals and files and a number of private node processors for laboratory experiment control is briefly reviewed. Central to the problem of private node-common node communication is the concept of a transaction. The collection of procedures and the data structure associated with a transaction are described. The common node properties assigned to a transaction and procedures required for its complete processing are discussed. (U.S.)

  13. The material control and accounting system model development in the Radiochemical plant of Siberian Chemical Combine (SChC)

    International Nuclear Information System (INIS)

    Kozyrev, A.S.; Purygin, V.Ya.; Skuratov, V.A.; Lapotkov, A.A.

    1999-01-01

    The nuclear material (NM) control and accounting computerized system is designed to automatically account NM reception, movement and storage at the Radiochemical Plant. The objective of this system development is to provide a constant surveillance over the process material movement, to improve their accountability and administrative work, to upgrade the plant protection against possible NM thefts, stealing and diversion, to rule out any casual errors of operators, to improve the timeliness and significance (reliability) of information about nuclear materials. The NM control and accounting system at the Radiochemical Plant should be based on the computerized network. It must keep track of all the material movements in each Material Balance Areas: material receipt from other plant; material local movement within the plant; material shipment to other plants; generation of required documents about NM movements and its accounting [ru

  14. Laboratory Investigation of Contact Freezing and the Aerosol to Ice Crystal Transformation Process

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, Raymond A. [Michigan Technological Univ., Houghton, MI (United States)

    2014-10-28

    This project has been focused on the following objectives: 1. Investigations of the physical processes governing immersion versus contact nucleation, specifically surface-induced crystallization; 2. Development of a quadrupole particle trap with full thermodynamic control over the temperature range 0 to –40 °C and precisely controlled water vapor saturation ratios for continuous, single-particle measurement of the aerosol to ice crystal transformation process for realistic ice nuclei; 3. Understanding the role of ice nucleation in determining the microphysical properties of mixed-phase clouds, within a framework that allows bridging between laboratory and field measurements.

  15. SLIPTA e-Tool improves laboratory audit process in Vietnam and Cambodia

    Directory of Open Access Journals (Sweden)

    Thuong T. Nguyen

    2014-11-01

    Full Text Available Background: The Stepwise Laboratory Quality Improvement Process Towards Accreditation (SLIPTA checklist is used worldwide to drive quality improvement in laboratories in developing countries and to assess the effectiveness of interventions such as the Strengthening Laboratory Management Toward Accreditation (SLMTA programme. However, the paperbased format of the checklist makes administration cumbersome and limits timely analysis and communication of results. Development of e-Tool: In early 2012, the SLMTA team in Vietnam developed an electronic SLIPTA checklist tool. The e-Tool was pilot tested in Vietnam in mid-2012 and revised. It was used during SLMTA implementation in Vietnam and Cambodia in 2012 and 2013 and further revised based on auditors’ feedback about usability. Outcomes: The SLIPTA e-Tool enabled rapid turn-around of audit results, reduced workload and language barriers and facilitated analysis of national results. Benefits of the e-Tool will be magnified with in-country scale-up of laboratory quality improvement efforts and potential expansion to other countries.

  16. Evolution and applications of radiochemical procedures. From Marie Curie to Darleane Hoffman

    International Nuclear Information System (INIS)

    Contis, E. T.; Rengan, K.

    1996-01-01

    Marie Curie carried out the first radiochemical separations which eventually lead to the discovery of polonium and radium, two new elements. Nearly a century later Darleane Hoffman and her collaborators are devising new radiochemical separation procedures for studying the chemical properties of newly discovered transactinide elements. Safety requirements as well as changes necessitated by fast decaying radionuclides have transformed the nature of radiochemical separations. Further, applications in a wide variety of areas such as analysis of trace elements in food to radioimmunoassay have broadened the use of radiochemical separations. Examples of some early, historically important, radiochemical separations are described in this article. In addition, recent trends in the use of radiochemical separations in neutron activation analysis, in dating applications, in fission product studies and in the study of transactinide elements are briefly described with specific examples. (author). 52 refs

  17. Self-decomposition of radiochemicals. Principles, control, observations and effects

    International Nuclear Information System (INIS)

    Evans, E.A.

    1976-01-01

    The aim of the booklet is to remind the established user of radiochemicals of the problems of self-decomposition and to inform those investigators who are new to the applications of radiotracers. The section headings are: introduction; radionuclides; mechanisms of decomposition; effects of temperature; control of decomposition; observations of self-decomposition (sections for compounds labelled with (a) carbon-14, (b) tritium, (c) phosphorus-32, (d) sulphur-35, (e) gamma- or X-ray emitting radionuclides, decomposition of labelled macromolecules); effects of impurities in radiotracer investigations; stability of labelled compounds during radiotracer studies. (U.K.)

  18. Mercury determination in geological samples using radiochemical separation

    International Nuclear Information System (INIS)

    Goncalves, Cristina; Favaro, Deborah I.T.

    1997-01-01

    In this work, a radiochemical procedure is presented to increase the neutron activation analysis sensitivity. After irradiation, geological reference materials - Buffalo River Sediment (BRS- - NIST SRM 2704), Lake Sediment (BCR - CRM 280) and GXR-5 (USGS - AEG) - were leached with aqua regia in a Parr bomb placed in a domestic microwave oven and then bismuth diethyl dithiocarbamate was used to pre concentrate mercury by solvent extraction. This procedure eliminates the interference from 279 keV Se-75 photopeak and background radiation from 511 keV Cu-64 photopeak. (author). 15 refs., 2 figs., 1 tab

  19. Rapid, radiochemical-ligand binding assay for methotrexate

    International Nuclear Information System (INIS)

    Caston, J.D.

    1976-01-01

    A radiochemical ligand binding assay for methotrexate is provided. A binder factor comprising a partially purified dihydrofolic acid reductase preparation is employed. The binder factor is conveniently prepared by homogenizing a factor containing animal organ such as liver, and extracting with isotonic saline and ammonium sulfate. A binder cofactor, NADPH 2 , is also employed in the binding reaction. The procedure contemplates both direct and sequential assay techniques, and it is not interfered with by vast excesses of many natural folate derivatives. 12 claims, 6 drawing figures

  20. Preparation of proton rich radionuclides in support of radiochemical analysis

    International Nuclear Information System (INIS)

    Jerome, Simon; Larijani, Cyrus; Parker, David

    2012-01-01

    The production of proton rich radionuclides supports a wide range of radiochemical analyses via radioactive yield tracers ( 95m Tc and 236 Pu). In recent years, NPL and the University of Birmingham cyclotron have collaborated to produce these, and other, radionuclides. - Highlights: ► In this paper we options for the production of Tc and Pu tracers. ► The irradiation and measurement of targets producing Tc-95 m and Pu-236 are described. ► Options for production are discussed. ► The results of this study and future work needed are described.

  1. Studies on some Indian paints for radiochemical plants

    International Nuclear Information System (INIS)

    Mahesh Kumar, V.V.; Srinivasan, R.; Natarajan, R.

    1996-01-01

    The choice of paints in areas subjected to contamination and radiation in nuclear installation need special attention. The types of generic coatings are examined with reference to these requirements. Among those examined, certain types of epoxy paints are found to be attractive for these applications. Samples of epoxy paints obtained from some Indian manufacturers are tested for their suitability. Decontaminability and radiation resistance properties are also evaluated with special reference to radiochemical plants. Important specifications for such applications are listed. This report summarizes the results of these studies. (author)

  2. EDS Coal Liquefaction Process Development. Phase V. Laboratory evaluation of the characteristics of EDS Illinois bottoms

    Energy Technology Data Exchange (ETDEWEB)

    Lao, T C; Levasseur, A A

    1984-02-01

    This interim report documents work carried out by Combustion Engineering, Inc. under a contract to Exxon Research and Engineering Company to develop a conceptual Hybrid Boiler design fueled by the vacuum distillation residue (vacuum bottoms) derived from Illinois No. 6 coal in the EDS Coal Liquefaction Process. This report was prepared by Combustion Engineering, Inc., and is the first of two reports on the predevelopment phase of the Hybrid Boiler program. This report covers the results of a laboratory investigation to assess the fuel and ash properties of EDS vacuum bottoms. The results of the laboratory testing reported here were used in conjunction with Combustion Engineering's design experience to predict fuel performance and to develop appropriate boiler design parameters. These boiler design parameters were used to prepare the engineering design study reported in EDS Interim Report FE-2893-113, the second of the two reports on the predevelopment phase of the Hybrid Boiler Program. 46 figures, 29 tables.

  3. Estimating HAPs and radionuclide emissions from a laboratory complex at a nuclear processing site

    International Nuclear Information System (INIS)

    Paul, R.A.; Faugl, T.

    1993-01-01

    A unique methodology was developed for conducting an air emission inventory (AEI) at a DOE nuclear processing facility. This methodology involved the use of computer-assisted design (CAD) drawings to document emission points, computerized process drawings to document industrial processes leading to emissions, and a computerized data base of AEI forms to document emission estimates and related process data. A detailed air emissions inventory for operating years 1985--1991 was recently implemented for the entire site using this methodology. One industrial area at the DOE Site is comprised of laboratory facilities that provide direct support to the nuclear reactor and recovery operations, developmental studies to support reactor and separation operations, and developmental studies to support waste handling and storage. The majority of the functions are conducted in a single large building complex wherein bench scale and pilot scale experiments are carried out involving radionuclides, hazardous air pollutants (HAP), and other chemicals reportable under the Clean Air Act Amendments (CAAA) and Superfund Amendments and Re-authorization Act (SARA) Title 111. The results of the inventory showed that HAP and radionuclide emissions from the laboratory complex were relatively minor

  4. Description of the Sandia National Laboratories science, technology & engineering metrics process.

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, Gretchen B.; Watkins, Randall D.; Trucano, Timothy Guy; Burns, Alan Richard; Oelschlaeger, Peter

    2010-04-01

    There has been a concerted effort since 2007 to establish a dashboard of metrics for the Science, Technology, and Engineering (ST&E) work at Sandia National Laboratories. These metrics are to provide a self assessment mechanism for the ST&E Strategic Management Unit (SMU) to complement external expert review and advice and various internal self assessment processes. The data and analysis will help ST&E Managers plan, implement, and track strategies and work in order to support the critical success factors of nurturing core science and enabling laboratory missions. The purpose of this SAND report is to provide a guide for those who want to understand the ST&E SMU metrics process. This report provides an overview of why the ST&E SMU wants a dashboard of metrics, some background on metrics for ST&E programs from existing literature and past Sandia metrics efforts, a summary of work completed to date, specifics on the portfolio of metrics that have been chosen and the implementation process that has been followed, and plans for the coming year to improve the ST&E SMU metrics process.

  5. Clandestine laboratory scene investigation and processing using portable GC/MS

    Science.gov (United States)

    Matejczyk, Raymond J.

    1997-02-01

    This presentation describes the use of portable gas chromatography/mass spectrometry for on-scene investigation and processing of clandestine laboratories. Clandestine laboratory investigations present special problems to forensic investigators. These crime scenes contain many chemical hazards that must be detected, identified and collected as evidence. Gas chromatography/mass spectrometry performed on-scene with a rugged, portable unit is capable of analyzing a variety of matrices for drugs and chemicals used in the manufacture of illicit drugs, such as methamphetamine. Technologies used to detect various materials at a scene have particular applications but do not address the wide range of samples, chemicals, matrices and mixtures that exist in clan labs. Typical analyses performed by GC/MS are for the purpose of positively establishing the identity of starting materials, chemicals and end-product collected from clandestine laboratories. Concerns for the public and investigator safety and the environment are also important factors for rapid on-scene data generation. Here is described the implementation of a portable multiple-inlet GC/MS system designed for rapid deployment to a scene to perform forensic investigations of clandestine drug manufacturing laboratories. GC/MS has long been held as the 'gold standard' in performing forensic chemical analyses. With the capability of GC/MS to separate and produce a 'chemical fingerprint' of compounds, it is utilized as an essential technique for detecting and positively identifying chemical evidence. Rapid and conclusive on-scene analysis of evidence will assist the forensic investigators in collecting only pertinent evidence thereby reducing the amount of evidence to be transported, reducing chain of custody concerns, reducing costs and hazards, maintaining sample integrity and speeding the completion of the investigative process.

  6. Assessment of radiochemical purity of [{sup 18}F]fludeoxyglucose by high pressure liquid chromatography (HPLC)

    Energy Technology Data Exchange (ETDEWEB)

    Lacerda, Aline E.; Silva, Juliana B.; Silveira, Marina B.; Ferreira, Soraya Z., E-mail: radiofarmacoscdtn@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil). Unidade de Pesquisa e Producao de Radiofarmacos

    2011-07-01

    The quality control of [{sup 18}F]fludeoxyglucose ({sup 18}FDG) has received attention due to its increasing clinical use. Although the quality requirements of {sup 18}FDG are established in various pharmacopoeia, the suitability of all testing methods used should be verified under actual conditions of use and documented. The aim of this study was to develop a high pressure liquid chromatography (HPLC) method for radiochemical purity evaluation of {sup 18}FDG, based on pharmacopoeia references, and to verify its suitability for routine quality control in our centre. HPLC analysis was performed with an Agilent HPLC. {sup 18}FDG and impurities were separated on an anion-exchange column by isocratic elution with 0.1 M NaOH as the mobile phase. Detection was accomplished with refractive index and NaI (Tl) scintillation detectors. The flow rate of the mobile phase was set at 0.8 mL/min and the column temperature was kept at 35 deg C. Specificity, linearity, precision and robustness were assessed to verify if the method was adequate for its intended purpose. Retention time of {sup 18}FDG was not affected by the presence of other components of the formulation and a good peak resolution was achieved. The analytical curve of {sup 18}FDG was linear, with a correlation coefficient value of 0.9995. Intraday repeatable precision, reported as the relative standard deviation, was 0.11%. Analytical procedure remained unaffected by small variations in mobile phase flow rate. Results evidenced that HPLC is suitable for radiochemical purity evaluation of {sup 18}FDG, considering operational conditions of our laboratory. (author)

  7. Assessment of radiochemical purity of [18F]fludeoxyglucose by high pressure liquid chromatography (HPLC)

    International Nuclear Information System (INIS)

    Lacerda, Aline E.; Silva, Juliana B.; Silveira, Marina B.; Ferreira, Soraya Z.

    2011-01-01

    The quality control of [ 18 F]fludeoxyglucose ( 18 FDG) has received attention due to its increasing clinical use. Although the quality requirements of 18 FDG are established in various pharmacopoeia, the suitability of all testing methods used should be verified under actual conditions of use and documented. The aim of this study was to develop a high pressure liquid chromatography (HPLC) method for radiochemical purity evaluation of 18 FDG, based on pharmacopoeia references, and to verify its suitability for routine quality control in our centre. HPLC analysis was performed with an Agilent HPLC. 18 FDG and impurities were separated on an anion-exchange column by isocratic elution with 0.1 M NaOH as the mobile phase. Detection was accomplished with refractive index and NaI (Tl) scintillation detectors. The flow rate of the mobile phase was set at 0.8 mL/min and the column temperature was kept at 35 deg C. Specificity, linearity, precision and robustness were assessed to verify if the method was adequate for its intended purpose. Retention time of 18 FDG was not affected by the presence of other components of the formulation and a good peak resolution was achieved. The analytical curve of 18 FDG was linear, with a correlation coefficient value of 0.9995. Intraday repeatable precision, reported as the relative standard deviation, was 0.11%. Analytical procedure remained unaffected by small variations in mobile phase flow rate. Results evidenced that HPLC is suitable for radiochemical purity evaluation of 18 FDG, considering operational conditions of our laboratory. (author)

  8. Evaluation of Surface Runoff Generation Processes Using a Rainfall Simulator: A Small Scale Laboratory Experiment

    Science.gov (United States)

    Danáčová, Michaela; Valent, Peter; Výleta, Roman

    2017-12-01

    Nowadays, rainfall simulators are being used by many researchers in field or laboratory experiments. The main objective of most of these experiments is to better understand the underlying runoff generation processes, and to use the results in the process of calibration and validation of hydrological models. Many research groups have assembled their own rainfall simulators, which comply with their understanding of rainfall processes, and the requirements of their experiments. Most often, the existing rainfall simulators differ mainly in the size of the irrigated area, and the way they generate rain drops. They can be characterized by the accuracy, with which they produce a rainfall of a given intensity, the size of the irrigated area, and the rain drop generating mechanism. Rainfall simulation experiments can provide valuable information about the genesis of surface runoff, infiltration of water into soil and rainfall erodibility. Apart from the impact of physical properties of soil, its moisture and compaction on the generation of surface runoff and the amount of eroded particles, some studies also investigate the impact of vegetation cover of the whole area of interest. In this study, the rainfall simulator was used to simulate the impact of the slope gradient of the irrigated area on the amount of generated runoff and sediment yield. In order to eliminate the impact of external factors and to improve the reproducibility of the initial conditions, the experiments were conducted in laboratory conditions. The laboratory experiments were carried out using a commercial rainfall simulator, which was connected to an external peristaltic pump. The pump maintained a constant and adjustable inflow of water, which enabled to overcome the maximum volume of simulated precipitation of 2.3 l, given by the construction of the rainfall simulator, while maintaining constant characteristics of the simulated precipitation. In this study a 12-minute rainfall with a constant intensity

  9. A radiochemical analyses of metastudtite and leachates from spent fuel

    International Nuclear Information System (INIS)

    McNamara, Bruce K.; Hanson, Brady D.; Buck, Edgar C.; Soderquist, Chuck Z.

    2004-01-01

    Immersion of commercial spent nuclear fuel (CSNF) in deionized water produced two novel corrosion products after a two-year contact period. Another unexpected result was that suspensions of aggregates were observed to form at the air-water interface for each of five samples. These solids were characterized, by SEM and XRD to be nearly pure metastudtite (UO4-2H2O); while the corrosion present on the surface of the fuel itself was determined to be studtite (UO4-2H2O). The occurrence of the floating phase prompted a radiochemical analysis of these solids. This chemical analysis was a unique opportunity to study the relatively pure corrosion phase for incorporation of radionuclides. The analysis indicated that high concentration of 90Sr, 137Cs, 99Tc, and that lower concentrations 237Np, 238, 239Pu and 243, 244Cm had partitioned with the air-water interface aggregates. The concentrations of 241Am were two orders of magnitude lower than the expected inventory in the suspended solids. The radiochemical analyses of the several leachate samples provide preliminary solubility data for the hydrogen peroxide leaching of CSNF and these data are compared to leaching of the same fuel in J-13 and deionized waters. The extent of fuel dissolution in these media are discussed

  10. RADIOCHEMICAL YIELDS OF GRAFT POLYMERIZATION REACTIONS OF CELLULOSE

    Energy Technology Data Exchange (ETDEWEB)

    Arthur, Jr, J C; Blouin, F A

    1963-12-15

    The preparation of radioinduced graft polymers of cotton cellulose, while retaining the fibrous nature and high molecular weight of the cellulose, depended primarily on the radiochemical yields of cellulose reactions and of graft polymerization reactions. Yields of the initial major molecular changes in cellulosic polymer indicated that, in the case of scission of the molecule and carboxyl group formation, chain reactions were not initiated by radiation; however, in the case of carbonyl group formation chain reactions were initiated but quickly terminated. Generally, experimental procedures, used in graft polymerization reactions, were: simultaneous irradiation reactions, that is, application of monomers or solutions of monomers to cellulose or chemically modified celluloses, then irradiation; and post-irradiation reactions, that is, irradiation of cellulose or chemically modified celluloses, then after removal from the field of radiation, contacting the irradiated cellulose with monomer. Some of the most important factors influencing the radiochemical yields of graft polymerization reactions, of styrene and acrylonitrile onto cellulose were: concentration of monomer in treating solution; solvent; ratio of monomer solution to cellulose; prior chemical modification of cellulose; and absence of oxygen, particularly in post-irradiation reactions. Experimental data are presented, and the direct and indirect effects of Co/sup 60/ gamma radiation on these reactions are discussed. (auth)

  11. An Evaluation of a Human Development Laboratory. A Study of the Outcome and Process of a Laboratory Learning Experience

    Science.gov (United States)

    1977-08-01

    Lewis, W. A. Sensitivity training mutual emotional masturbation ? Personnel and Guidance Journal, 1970, 48, 525. L’Herisson, L., and Krumm, K. J. Changes...for the purpose of practicing their newly learned skills. The groups were formed by the participants’ selecting members of the laboratory with whom...34how" it is said) are con- ji 83 gruent. After this input, the participants returned to their respective small groups to continue practicing the skills

  12. Special study for the manual transfer of process samples from CPP [Chemical Processing Plant] 601 to RAL [Remote Analytical Laboratory

    International Nuclear Information System (INIS)

    Marts, D.J.

    1987-05-01

    A study of alternate methods to manually transport radioactive samples from their glove boxes to the Remote Analytical Laboratory (RAL) was conducted at the Idaho National Engineering Laboratory. The study was performed to mitigate the effects of a potential loss of sampling capabilities that could take place if a malfunction in the Pneumatic Transfer System (PTS) occurred. Samples are required to be taken from the cell glove boxes and analyzed at the RAL regardless of the operational status of the PTS. This paper documents the conclusions of the study and how a decision was reached that determined the best handling scenarios for manually transporting 15 mL vials of liquid process samples from the K, W, U, WG, or WH cell glove boxes in the Chemical Processing Plant (CPP) 601 to the RAL. This study of methods to manually remove the samples from the glove boxes, package them for safe shipment, transport them by the safest route, receive them at the RAL, and safely unload them was conducted by EG and G Idaho, Inc., for Westinghouse Idaho Nuclear Company as part of the Glove Box Sampling and Transfer System Project for the Fuel Processing Facilities Upgrade, Task 10, Subtask 2. The study focused on the safest and most reliable scenarios that could be implemented using existing equipment. Hardware modifications and new hardware proposals were identified, and their impact on the handling scenario has been evaluated. A conclusion was reached that by utilizing the existing facility hardware, these samples can be safely transported manually from the sample stations in CPP 601 to the RAL, and that additional hardware could facilitate the transportation process even further

  13. Modelling and experimental investigation of waste tyre pyrolysis process in a laboratory reactor

    Directory of Open Access Journals (Sweden)

    Rudniak Leszek

    2017-09-01

    Full Text Available A mathematical model of waste tyre pyrolysis process is developed in this work. Tyre material decomposition based on a simplified reaction mechanism leads to main product lumps: noncondensable (gas, condensable (pyrolytic oil and solid (char. The model takes into account kinetics of heat and mass transfer in the grain of the shredded rubber material as well as surrounding gas phase. The main reaction routes were modelled as the pseudo-first order reactions with a rate constant calculated from the Arrhenius type equation using literature values of activation energy determined for main tyre constituents based on TG/DTG measurements and tuned pre-exponential parameter values obtained by fitting theoretical predictions to the experimental results obtained in our laboratory reactor. The model was implemented within the CFD software (ANSYS Fluent. The results of numerical simulation of the pyrolysis process revealed non-uniformity of sample’s porosity and temperature. The simulation predictions were in satisfactory agreement with the experimentally measured mass loss of the tyre sample during pyrolysis process investigated in a laboratory reactor.

  14. Validation of mathematical model for CZ process using small-scale laboratory crystal growth furnace

    Science.gov (United States)

    Bergfelds, Kristaps; Sabanskis, Andrejs; Virbulis, Janis

    2018-05-01

    The present material is focused on the modelling of small-scale laboratory NaCl-RbCl crystal growth furnace. First steps towards fully transient simulations are taken in the form of stationary simulations that deal with the optimization of material properties to match the model to experimental conditions. For this purpose, simulation software primarily used for the modelling of industrial-scale silicon crystal growth process was successfully applied. Finally, transient simulations of the crystal growth are presented, giving a sufficient agreement to experimental results.

  15. The laboratory test rig with miniature jet engine to research aviation fuels combustion process

    Directory of Open Access Journals (Sweden)

    Gawron Bartosz

    2015-12-01

    Full Text Available This article presents laboratory test rig with a miniature turbojet engine (MiniJETRig – Miniature Jet Engine Test Rig, that was built in the Air Force Institute of Technology. The test rig has been developed for research and development works aimed at modelling and investigating processes and phenomena occurring in full scale jet engines. In the article construction of a test rig is described, with a brief discussion on the functionality of each of its main components. Additionally examples of measurement results obtained during the realization of the initial tests have been included, presenting the capabilities of the test rig.

  16. Waste Processing Cost Recovery at Los Alamos National Laboratory-Analysis and Recommendations

    International Nuclear Information System (INIS)

    Booth, St. R.

    2009-01-01

    Los Alamos National Laboratory is implementing full cost recovery for waste processing in fiscal year 2009 (FY2009), after a transition year in FY2008. Waste processing cost recovery has been implemented in various forms across the nuclear weapons complex and in corporate America. The fundamental reasoning of sending accurate price signals to waste generators is economically sound, and leads to waste minimization and reduced waste expense over time. However, Los Alamos faces significant implementation challenges because of its status as a government-owned, contractor-operated national scientific institution with a diverse suite of experimental and environmental cleanup activities, and the fact that this represents a fundamental change in how waste processing is viewed by the institution. This paper describes the issues involved during the transition to cost recovery and the ultimate selection of the business model. Of the six alternative cost recovery models evaluated, the business model chosen to be implemented in FY2009 is Recharge Plus Generators Pay Distributed Direct. Under this model, all generators who produce waste must pay a distributed direct share associated with their specific waste type to use a waste processing capability. This cost share is calculated using the distributed direct method on the fixed cost only, i.e., the fixed cost share is based on each program's forecast proportion of the total Los Alamos volume forecast of each waste type. (Fixed activities are those required to establish the waste processing capability, i.e., to make the process ready, permitted, certified, and prepared to handle the first unit of waste. Therefore, the fixed cost ends at the point just before waste begins to be processed. The activities to actually process the waste are considered variable.) The volume of waste actually sent for processing is charged a unit cost based solely on the variable cost of disposing of that waste. The total cost recovered each year is the

  17. Use of soft hydrothermal processing to improve and recycle bedding for laboratory animals.

    Science.gov (United States)

    Miyamoto, T; Li, Z; Kibushi, T; Yamasaki, N; Kasai, N

    2008-10-01

    Cage bedding for laboratory rodents can influence animal wellbeing and thus the experimental data. In addition, a large amount of used bedding containing excrement is discharged as medical waste from life science institutes and breeding companies. We developed a ground-breaking system to improve fresh bedding and recycle used bedding by applying a soft hydrothermal process with high-temperature and high-pressure dry steam. The system removes both harmful organic components and aromatic hydrocarbons that can affect animals' metabolism. The purpose of the present study was to evaluate the chemical and physical properties of the improved fresh bedding and the recycled used bedding treated by the system. The results showed that 68-99% of the predominant aromatic hydrocarbons were removed from fresh bedding treated at 0.35 MPa and 140 degrees C for 120 min ('improved bedding'). In addition, 59.4-99.0% of predominant harmful organic compounds derived from excrement were removed from used bedding treated at 0.45 MPa and 150 degrees C for 60 min ('recycled bedding'). The soft hydrothermal treatment increased the number of acidic functional groups on the bedding surface and gave it the high adsorptive efficiency of ammonia gas. Harmful substances such as microorganisms, heavy metals and pesticides decreased below the detection limit. The results clearly showed that the improved and recycled bedding is safer for laboratory rodents and has the potential to ameliorate conditions in primary and secondary enclosures (e.g. cages and animal rooms) used for maintaining laboratory animals. This process may be one of the most advanced techniques in providing an alternative to softwood and other bedding, economizing through the recycling of used bedding and reducing bedding waste from animal facilities.

  18. Emission characteristics of PBDEs during flame-retardant plastics extruding process: field investigation and laboratorial simulation.

    Science.gov (United States)

    Deng, Chao; Li, Ying; Li, Jinhui; Chen, Yuan; Li, Huafen

    2017-10-01

    Though mechanical recycling of WEEE plastics is supposed to be a promising method, PBDEs release and the resulting contamination during its processing remain unclear yet. The distribution of PBDEs pollution in production lines was investigated from two flame-retardant plastic modification plants in Southern China. This was followed by laboratory simulation experiments to characterize the emission processes. PBDEs concentrations ranged from 37 to 31,305 ng/L in cooling water and from 40,043 to 216,653 ng/g dry wt in solid samples taken during the field investigation. In the laboratory simulation, concentrations ranged from 146 to 433 ng/L in cooling water and from 411,436 to 747,516 ng/Nm 3 in flue gas. All samples were dominated by BDE-209 among the congeners. Temperatures and impurities in plastic substrate can significantly affect PBDEs release. Special attention should be paid to the risks of water directly discharge from the cooling system, especially for the biological sludge and sediments, as well as flue gas emissions to the environment.

  19. Technology roadmap for development of SiC sensors at plasma processes laboratory

    Directory of Open Access Journals (Sweden)

    Mariana Amorim Fraga

    2010-08-01

    Full Text Available Recognizing the need to consolidate the research and development (R&D activities in microelectronics fields in a strategic manner, the Plasma Processes Laboratory of the Technological Institute of Aeronautics (LPP-ITA has established a technology roadmap to serve as a guide for activities related to development of sensors based on silicon carbide (SiC thin films. These sensors have also potential interest to the aerospace field due to their ability to operate in harsh environment such as high temperatures and intense radiation. In the present paper, this roadmap is described and presented in four main sections: i introduction, ii what we have already done in the past, iii what we are doing in this moment, and iv our targets up to 2015. The critical technological issues were evaluated for different categories: SiC deposition techniques, SiC processing techniques for sensors fabrication and sensors characterization. This roadmap also presents a shared vision of how R&D activities in microelectronics should develop over the next five years in our laboratory.

  20. Incinerator development program for processing transuranic waste at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Hedahl, T.G.

    1982-01-01

    In the fall of 1981, two short-term tests were conducted on a controlled air and a rotary kiln incinerator to assess their potential for processing transuranic (TRU) contaminated waste at the Idaho National Engineering Laboratory (INEL). The primary purpose of the test program was a proof-of-principle verification that the incinerators could achieve near-complete combustion of the combustible portion of the waste, while mixed with high percentages of noncombustible and metal waste materials. Other important test objectives were to obtain system design information including off-gas and end-product characteristics and incinerator operating parameters. Approximately 7200 kg of simulated (non-TRU) waste from the INEL were processed during the two tests

  1. Remedial investigation of the High-Explosives (HE) Process Area, Lawrence Livermore National Laboratory Site 300

    Energy Technology Data Exchange (ETDEWEB)

    Crow, N.B.; Lamarre, A.L.

    1990-08-01

    This report presents the results of a Remedial Investigation (RI) to define the extent of high explosives (HE) compounds and volatile organic compounds (VOCs) found in the soil, rocks, and ground water of the HE Process Area of Lawrence Livermore National Laboratory's (LLNL) Site 300 Facility. The report evaluates potential public health environmental risks associated with these compounds. Hydrogeologic information available before February 15, 1990, is included; however, chemical analyses and water-level data are reported through March 1990. This report is intended to assist the California Regional Water Quality Control Board (RWQCB)--Central Valley Region and the US Environmental Protection Agency (EPA) in evaluating the extent of environmental contamination of the LLNL HE Process Area and ultimately in designing remedial actions. 90 refs., 20 figs., 7 tabs.

  2. The analytical of radiochemical purity of tumor receptor imaging agent 99Tcm-octreotide

    International Nuclear Information System (INIS)

    Wang Xufu; Zuo Shuyao; Shao Wenbo; Wang Guoming; Sun Jianwen; Zhang Qin

    2003-01-01

    The radiochemical purity of tumor receptor imaging agent 99 Tc m -octreotide is measured by High Pressure Liquid Chromatography (HPLC) and two systems of chromatography combining method of silver stain. The results show that the radiochemical purity of 98 Tc m -octreotide measured by both methods are effective and correct. It can separate 99 Tc m -octreotide from other radioactive compositions correctly and effectively

  3. Launching a Laboratory Testing Process Quality Improvement Toolkit: From the Shared Networks of Colorado Ambulatory Practices and Partners (SNOCAP).

    Science.gov (United States)

    Fernald, Douglas; Hamer, Mika; James, Kathy; Tutt, Brandon; West, David

    2015-01-01

    Family medicine and internal medicine physicians order diagnostic laboratory tests for nearly one-third of patient encounters in an average week, yet among medical errors in primary care, an estimated 15% to 54% are attributed to laboratory testing processes. From a practice improvement perspective, we (1) describe the need for laboratory testing process quality improvements from the perspective of primary care practices, and (2) describe the approaches and resources needed to implement laboratory testing process quality improvements in practice. We applied practice observations, process mapping, and interviews with primary care practices in the Shared Networks of Colorado Ambulatory Practices and Partners (SNOCAP)-affiliated practice-based research networks that field-tested in 2013 a laboratory testing process improvement toolkit. From the data collected in each of the 22 participating practices, common testing quality issues included, but were not limited to, 3 main testing process steps: laboratory test preparation, test tracking, and patient notification. Three overarching qualitative themes emerged: practices readily acknowledge multiple laboratory testing process problems; practices know that they need help addressing the issues; and practices face challenges with finding patient-centered solutions compatible with practice priorities and available resources. While practices were able to get started with guidance and a toolkit to improve laboratory testing processes, most did not seem able to achieve their quality improvement aims unassisted. Providing specific guidance tools with practice facilitation or other rapid-cycle quality improvement support may be an effective approach to improve common laboratory testing issues in primary care. © Copyright 2015 by the American Board of Family Medicine.

  4. Limits of the radiochemical and geochemical method for the test of nucleon stability

    Energy Technology Data Exchange (ETDEWEB)

    Bergamasco, L [CNR, Laboratorio di Cosmo-Geofisica, Turin, Italy; Texas A and M University, College Station, Tex.); Cini, G [CNR, Laboratorio di Cosmo-Geofisica; Torino, Universita, Turin, Italy)

    1978-07-01

    An estimate is obtained for the limiting nucleon lifetime that can be determined by the radiochemical method of Steinberg and Evans (1977), which counts the Ar-37 production from reactions due to nucleon decay in a large sample of KC2H3O2. To estimate the background rate, processes due to the atmospheric muon component are considered. It is found that the asymptotic limit on the maximum value of the nucleon lifetime is 2 x 10/sup 30/years. This value cannot be increased by going to larger depths or by using a larger sample, but is inherent in the method itself. To improve the limit one would have to resort to methods based on multiparticle decay modes.

  5. Development of radiochemical separation method for determination of toxic elements in biological samples

    International Nuclear Information System (INIS)

    Maihara, V.A.; Vasconcellos, M.B.A.; Favaro, D.I.T.; Armelin, M.J.A.

    1990-01-01

    In order to determine Hg, Sb, As and Se in biological materials by neutron activation analysis, a radiochemical separation was developed. The chemical separation procedure used was based on the digestion of the irradiated sample in a mixture of H NO 3 and H 2 SO 4 in a teflon bomb, at 130 0 C for 1 to 4 hours. After the dissolution of organic matter, Hg and Sb were retained by a Dowex 2-X8 resin column in 6 M HCl. The effluent was passed through a TDO, tin dioxide column which retains As and Se in 3 M HCl medium. Radioactive tracers of these elements were used to determine the yields of the separation process. Certified reference materials were analyzed to check the precision and accuracy of the method. (author)

  6. Development of a radiochemical separation method for toxic elements determination from biologic samples

    International Nuclear Information System (INIS)

    Malhara, V.A.; Vasconcellos, M.B.A.; Favaro, D.I.T.; Armelin, M.J.A.

    1990-01-01

    In order to determine Hg, Sb, As and Se in biological materials by neutron activation analysis, a radiochemical separation was developed. The chemical separation procedure used was based on the digestion of the irradiated sample in a mixture of HNO 3 and H 2 SO 4 in a teflon bomb, at 130 0 C for 1 to 4 hours. After the dissolution of organic matter, Hg and Sb were retained by a Dowex 2-XB resin column in 6M HCI. The efluent was passed through a TDO, tin dioxide column which retains As and Se in 3M HCI medium. Radioactive tracers of these elements were used to determine the yields of the separation process. Certified reference materials were analyzed to check the precision and accuracy of the method. (author)

  7. Continuous radiochemical analysis of fission products in a nuclear reactor water coolant

    International Nuclear Information System (INIS)

    Moskvin, L.N.; Zakharov, L.K.; Leont'ev, G.G.; Mel'nikov, V.A.; Orlenkov, I.S.; Slutskij, G.K.

    1975-01-01

    Method for continuous radiochemical analysis of I, Cs, Ba, Sr and Ce isotopes in a reactor water heat-transfer agent was developed. A continuous two-dimensional chromatographic process of complex mixtures separation of substances proved to be feasible on several parallel sorbent layers, which moved at constant velocities and separated by stationary intermediate collectors. Tests on model solutions containing I, Ce, Cs and Ba isotopes and on heat-carrier samples showed quantitative separation of elements. The results were indicative of a basic possibility of using multisorbent chromatographs for continuous control of multicomponent mixtures, particularly for control of radioactive fission product compositions in water heat-transfer agents in nuclear power plants. A diagram is shown for a two-dimensional chromatographic separation of a multicomponent mixture. Also shown is a flow chart of an installation for continuous control of iodine and cesium isotope activities

  8. Determination of rhenium in biological and environmental samples by radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Kucera, J.; Mizera, J.; Randa, Z.; Byrne, A.R.; Lucanikova, M.

    2006-01-01

    Radiochemical neutron activation procedures using liquid-liquid extraction with tetraphenylarsonium chloride in chloroform from 1 M HCl and solid extraction with ALIQUAT 336 incorporated in a polyacrylonitrile binding matrix from 0.1 M HCl were developed for accurate determination of rhenium in biological and environmental samples at the sub-ng.g -1 level. Concentrations of Re in the range of 0.1 to 2.4 ng.g -1 were determined in several botanical reference materials (RM), while in a RM of road dust a value of approx. 10 ng.g -1 was found. Significantly elevated values of Re, up to 90 ng.g -1 , were found in seaweed (brown algae). Results for Re in the brown algae Fucus vesiculosus in which elevated 99 Tc values had previously been determined suggest possible competition between Re and Tc in the accumulation process. (author)

  9. A radiochemical assay for detection of leukotriene B4 production from isolated cells

    International Nuclear Information System (INIS)

    Aharony, D.; Dobson, P.; Krell, R.D.

    1984-01-01

    A radiochemical procedure for quantitating the effect of inhibitors of leukotriene B4 (LTB4) biosynthesis is described. Rat peritoneal cells were labeled with 3 H-arachidonic acid and stimulated with the calcium ionophore A23187. 3 H-LTB4 was isolated by processing on C18-Sep Pak cartridges followed by reverse-phase high pressure liquid chromatography (HPLC). The identity of this product, as well as other arachidonic acid metabolites, was verified by using silicic acid column chromatography followed by straight-phase HPLC and thin layer chromatography. Using this assay, LTB4 release by ionophore A23187 has been shown to be both time- and concentration-dependent. Indomethacin enhanced, while NDGA and ETYA inhibited, the A23187-induced production of LTB4. This procedure is both simple and direct and is capable of assessing the ability of novel compounds to alter LTB4 production

  10. Laboratory Exercise: Study of Digestive and Regulatory Processes through the Exploration of Fasted and Postprandial Blood Glucose

    Science.gov (United States)

    Hopper, Mari K.; Maurer, Luke W.

    2013-01-01

    Digestive physiology laboratory exercises often explore the regulation of enzyme action rather than systems physiology. This laboratory exercise provides a systems approach to digestive and regulatory processes through the exploration of postprandial blood glucose levels. In the present exercise, students enrolled in an undergraduate animal…

  11. Electrical processes for the treatment of medium active liquid wastes: a laboratory-scale evaluation

    International Nuclear Information System (INIS)

    Turner, A.D.; Bowen, W.R.; Bridger, N.J.; Harrison, K.T.

    1983-10-01

    A wide range of electrochemical separation processes has been evaluated through literature and experimental studies for potential application to the treatment of medium-active liquid wastes. Of the ten processes considered, electro-osmosis and electrochemical ion-exchange show the most promise for immediate further development to a larger scale, while the faradaic deposition of PuO 2 , Tc, RuO 2 require further laboratory study before judgement can be passed on these. Electro-osmosis has an exceptionally high solids retention (99.99%) and is capable of dewatering suspensions to 35% - suitable for direct incorporation in concrete. Electrochemical ion-exchange has the attractions of a conventional ion-exchange process but with the added features of enhanced kinetics and pH operating range, as well as elution into demineralized water merely by polarity reversal. All electrical processes have the advantage of the added process variable of externally applied potential, which can enable remote, automatic control. (author)

  12. Electrical processes for the treatment of medium-active liquid wastes: a laboratory-scale evaluation

    International Nuclear Information System (INIS)

    Turner, A.D.; Bowen, W.R.; Bridger, N.J.; Harrison, K.T.

    1984-01-01

    A wide range of electrochemical separation processes have been evaluated through the literature and experimental studies for potential application to the treatment of medium-active liquid wastes. Of the 10 processes considered, electro-osmosis and electrochemical ion-exchange show the most promise for immediate further development to a larger scale, while the faradic deposition of PuO 2 , Tc, RuO 2 require further laboratory study before judgment can be passed on these. Electro-osmosis has an exceptionally high solids retention (99.99%) and is capable of dewatering suspensions to 35% - suitable for direct incorporation in concrete. Electrochemical ion-exchange has the attractions of a conventional ion-exchange process but with the added features of enhanced kinetics and pH operating range, as well as elution into demineralized water merely by polarity reversal. All electrical processes have the advantage of the added process variable of externally applied potential, which can enable remote, automatic control

  13. Water detritiation processing of JET purified waste water using the TRENTA facility at Tritium Laboratory Karlsruhe

    Energy Technology Data Exchange (ETDEWEB)

    Michling, R., E-mail: robert.michling@kit.edu; Bekris, N.; Cristescu, I.; Lohr, N.; Plusczyk, C.; Welte, S.; Wendel, J.

    2013-10-15

    Highlights: • Operation of a water detritiation facility under optimized conditions for high detritiation performances. • Improvement of operational procedures to process tritiated waste water. • Handling and reduction of tritiated waste water to achieve enriched low volume tritiated water for sufficient storage. • Demonstration of the efficient availability of the TRENTA WDS facility for technical scale operation. -- Abstract: A Water Detritiation System (WDS) is required for any Fusion machine in order to process tritiated waste water, which is accumulated in various subsystems during operation and maintenance. Regarding the European procurement packages for the ITER tritium fuel cycle, the WDS test facility TRENTA applying the Combined Electrolysis Catalytic Exchange (CECE) process was developed, installed and is currently in operation at the Tritium Laboratory Karlsruhe (TLK). Besides the on-going R and D work for the design of ITER WDS, the current status of the TRENTA facility provides the option to utilize the WDS for processing tritiated water. Therefore, in the framework of the EFDA JET Fusion Technology Work Programme 2011, the TLK was able to offer the capability on a representative scale to process tritiated water, which was produced during normal operation at JET. The task should demonstrate the availability of the CECE process to handle and detritiate the water in terms of tritium enrichment and volume reduction. The operational program comprised the processing of purified tritiated water from JET, with a total volume of 180 l and an activity of 74 GBq. The paper will give an introduction to the TRENTA WDS facility and an overview of the operational procedure regarding tritiated water reduction. Data concerning required operation time, decontamination and enrichment performances and different operating procedures will be presented as well. Finally, a preliminary study on a technical implementation of processing the entire stock of JET

  14. Simulation Based Low-Cost Composite Process Development at the US Air Force Research Laboratory

    Science.gov (United States)

    Rice, Brian P.; Lee, C. William; Curliss, David B.

    2003-01-01

    Low-cost composite research in the US Air Force Research Laboratory, Materials and Manufacturing Directorate, Organic Matrix Composites Branch has focused on the theme of affordable performance. Practically, this means that we use a very broad view when considering the affordability of composites. Factors such as material costs, labor costs, recurring and nonrecurring manufacturing costs are balanced against performance to arrive at the relative affordability vs. performance measure of merit. The research efforts discussed here are two projects focused on affordable processing of composites. The first topic is the use of a neural network scheme to model cure reaction kinetics, then utilize the kinetics coupled with simple heat transport models to predict, in real-time, future exotherms and control them. The neural network scheme is demonstrated to be very robust and a much more efficient method that mechanistic cure modeling approach. This enables very practical low-cost processing of thick composite parts. The second project is liquid composite molding (LCM) process simulation. LCM processing of large 3D integrated composite parts has been demonstrated to be a very cost effective way to produce large integrated aerospace components specific examples of LCM processes are resin transfer molding (RTM), vacuum assisted resin transfer molding (VARTM), and other similar approaches. LCM process simulation is a critical part of developing an LCM process approach. Flow simulation enables the development of the most robust approach to introducing resin into complex preforms. Furthermore, LCM simulation can be used in conjunction with flow front sensors to control the LCM process in real-time to account for preform or resin variability.

  15. Water detritiation processing of JET purified waste water using the TRENTA facility at Tritium Laboratory Karlsruhe

    International Nuclear Information System (INIS)

    Michling, R.; Bekris, N.; Cristescu, I.; Lohr, N.; Plusczyk, C.; Welte, S.; Wendel, J.

    2013-01-01

    Highlights: • Operation of a water detritiation facility under optimized conditions for high detritiation performances. • Improvement of operational procedures to process tritiated waste water. • Handling and reduction of tritiated waste water to achieve enriched low volume tritiated water for sufficient storage. • Demonstration of the efficient availability of the TRENTA WDS facility for technical scale operation. -- Abstract: A Water Detritiation System (WDS) is required for any Fusion machine in order to process tritiated waste water, which is accumulated in various subsystems during operation and maintenance. Regarding the European procurement packages for the ITER tritium fuel cycle, the WDS test facility TRENTA applying the Combined Electrolysis Catalytic Exchange (CECE) process was developed, installed and is currently in operation at the Tritium Laboratory Karlsruhe (TLK). Besides the on-going R and D work for the design of ITER WDS, the current status of the TRENTA facility provides the option to utilize the WDS for processing tritiated water. Therefore, in the framework of the EFDA JET Fusion Technology Work Programme 2011, the TLK was able to offer the capability on a representative scale to process tritiated water, which was produced during normal operation at JET. The task should demonstrate the availability of the CECE process to handle and detritiate the water in terms of tritium enrichment and volume reduction. The operational program comprised the processing of purified tritiated water from JET, with a total volume of 180 l and an activity of 74 GBq. The paper will give an introduction to the TRENTA WDS facility and an overview of the operational procedure regarding tritiated water reduction. Data concerning required operation time, decontamination and enrichment performances and different operating procedures will be presented as well. Finally, a preliminary study on a technical implementation of processing the entire stock of JET

  16. Laboratory evaluation of hot metal de siliconizing process in ladle; Avaliacao laboratorial do processo de dessiliciacao do gusa na panela

    Energy Technology Data Exchange (ETDEWEB)

    Passos, Sergio R.M.; Furtado, Henrique S.; Bentes, Miguel A.G.; Almeida, Pedro S. de [Companhia Siderurgica Nacional, Volta Redonda, RJ (Brazil). Centro de Pesquisas

    1996-12-31

    The attractiveness of hot metal de siliconizing in ladle, relative to the process in blast furnace runner, is the previous knowledge of silicon content of hot metal, without the constraints of slag removing by skimmer met in torpedo car, and the better efficiency in low range silicon content, making easier the process controllability. Meanwhile, the main question about this technology is the extent of the resulfurization of hot metal that may occur due to process be performed after the desulfurization. This work simulates de de siliconizing process in ladle by experiments in induction furnace to compare the efficiencies of various de siliconizing agents available at CSN iron and steel making plant, and to evaluate the resulfurization intensity able to occur during the process, as well as, unexpected increasing of refractory wear. (author) 4 refs., 8 figs., 6 tabs.

  17. Paleomagnetism and radiochemical age estimates for Late Brunhes polarity episodes

    International Nuclear Information System (INIS)

    Denham, C.R.; Anderson, R.F.; Bacon, M.P.

    1977-01-01

    Several reversed polarity magnetozones occur within deep-sea sediment core CH57-8 from the Greater Antilles Outer Ridge, within sediment of latest Pleistocene/Late Brunhes age. The uppermost reversed interval spanning 31 data points coincides with the X faunal zone of the Last Interglacial Period. Radiochemical dating of cores CH57-8 and KN25-4 has shown that all the reversed polarity magnetozones are significantly younger than the Brunhes/Matuyama boundary at 0.7 m.y.B.P. A variation of the excess 230 Th method was used, in which 210 Po and 238 U were the actual radionuclides measured. In a third core from the Mid-Atlantic Ridge, the 210 Po results were similar to those which others obtained earlier by direct 230 Th measurements. (Auth.)

  18. Quantitative radio-chemical separation of calcium, strontium and barium

    International Nuclear Information System (INIS)

    Dupuis, M.C.; Dupuis, M.; Le Nagard, M.; Michot, H.

    1965-01-01

    A method for separation of Ca 45 , Sr 89 and Ba 140 has been developed for the radiochemical determination of these isotopes in a solution of fission with a large concentration of mineral salts. After removal of most fission products by solvent extraction (TTA-MIBK) at different pH, the alkaline earths are extracted from the aqueous phase at pH 9. After recovery with diluted hydrochloric acid, the three elements are adsorbed on cationic resin Dowex 50 and eluted sequentially with ammonium α - Hydroxy iso-butyrate using gradient concentration and pH. Ca 45 and Sr 89 are measured by β - counting and Ba 140 by γ spectrometry. The chemical yield approximates 80 per cent for calcium, and 70 per cent for strontium and barium. The decontamination factor is 10 5 for most fission products. Four separations can be performed in twenty hours. (authors) [fr

  19. Radiochemical analysis in the nuclear research establishment (KFA) Juelich, FRG

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    KFA Juelich is one of the two great nuclear research centres of the Federal Republic of Germany. About 3700 employees including about 700 scientists are engaged in a great number of programs and projects belonging to six main fields of research and development: high temperature reactor and energy techniques; nuclear fusion; properties of materials; materials research; life and environment; methods. In the article the radiochemical analysis work of the former Central Institute of Analytical Chemistry and its two successors is described: activation analysis, application of tracer techniques, fission product analysis. Further on the irradiation facilities are described, a short survey is given on the instrumentation, and the future work is outlined. (T.G.)

  20. 15th radiochemical conference: Booklet of abstracts and conference programme

    International Nuclear Information System (INIS)

    John, J.; Benes, P.; Kucera, J.; Havela, L.; Bartonicek, B.; Vobecky, M.; Krizova, V.; Kopicka, K.; Prasil, Z.

    2006-04-01

    The conference was structured as follows: Opening plenary lectures (6 lectures); Topic 1 - radionuclides in the environment, radioecology (22 verbal presentations (VPs), 23 poster presentations (PPs)); Topic 2 - nuclear analytical methods (22 VPs, 32 PPs); Topic 3 - chemistry of actinide and transactinide elements (8 VPs, 10 PPs); Topic 4 - radiation chemistry (9 VPs, 5 PPs); Topic 5 - production and application of radionuclides (17 VPs, 6 PPs); Topic 6 - separation methods, speciation (21 VPs, 23 PPs); Topic 7 - chemistry of nuclear fuel cycle, radiochemical problems in nuclear waste management (20 VPs, 16 PPs); Topic 8 - nuclear methods in medicine, radiopharmaceuticals, and radiodiagnostics, labelled compounds (8 VPs, 7 PPs); and Panels (2 introductions). (P.A.)

  1. Fast analysis procedure of radiochemical coordinat uptake for methotrexate

    International Nuclear Information System (INIS)

    Caston, J.D.; Kamen, B.A.

    1976-01-01

    Under this invention, a radio-chemical analysis is submitted to determine the concentration of methotrexate or its equivalents in analysis in a biological medium. The amounts taken up of the labelled compound and the known concentrations of the unlabelled compound to be determined are radio-isotopically related to a first system containing a pre-determined amount of the labelled compound and a pre-determined amount of the unlabelled compound. In a second system, identical to the first, save that the sample of the biological medium to be analyzed takes the place of the unlabelled compound, the amount of labelled compound taken up is determined radio-isotopically. The concentration of the compound in the sample is then determined by correlation of the labelled compound uptake determined in the second system with the relation determined in the first system. The radio-isotopic relations and determinations may be made by direct and sequential analytical techniques [fr

  2. Radiochemical neutron activation analysis of gold in geochemical samples

    International Nuclear Information System (INIS)

    Zilliacus, R.

    1983-01-01

    A fast method for the radiochemical neutron activation analysis of gold in geochemical samples is described. The method is intended for samples having background concentrations of gold. The method is based on the dissolution of samples with hydrofluoric acid and aqua regia followed by the dissolution of the fluorides with boric acid and hydrochloric acid. Gold is then adsorbed on activated carbon by filtrating the solution through a thin carbon layer. The activity measurements are carried out using a Ge(Li)-detector and a multichannel analyzer. The chemical yields of the separation determined by reirradiation vary between 60 and 90%. The detection limit of the method is 0.2 ng/g gold in rock samples. USGS standard rocks and exploration reference materials are analyzed and the results are presented and compared with literature data. (author)

  3. Radiochemical methods for studying lipase-catalyzed interesterification of lipids

    International Nuclear Information System (INIS)

    Schuch, R.; Mukherjee, K.D.

    1987-01-01

    Reactions involving lipase-catalyzed interesterification of lipids, which are of commendable interest in biotechnology, have been monitored and assayed by radiochemical methods using 14 C-labeled substrates. Medium chain (C 12 plus C 14 ) triacylglycerols were reacted in the presence of an immobilized lipase from Mucor miehei and hexane at 45 0 C with methyl [1- 14 C]oleate, [1- 14 C]oleic acid, [carboxyl- 14 C]trioleoylglycerol, [1- 14 C]octadecenyl alcohol, and [U- 14 C]glycerol, each of known specific activity. The reactions were monitored and the rate of interesterification determined by radio thin layer chromatography from the incorporation of radioactivity into acyl moieties of triacylglycerols (from methyl oleate, oleic acid, and trioleoylglycerol), alkyl moieties of wax esters (from octadecenyl alcohol), and into glycerol backbone of monoacylglycerols and diacylglycerols (from glycerol). (orig.)

  4. Research reactor FR2 - 20 years chemical and radiochemical measurements

    International Nuclear Information System (INIS)

    Feuerstein, H.; Graebner, H.; Oschinski, J.; Hoffmann, W.; Beyer, J.

    1986-09-01

    The FR2 has been a D 2 O cooled and moderated research reactor with a thermal output of 44 MW. It was in operation from 1961 to 1981. Because of the operating conditions of the reactor, only a small number of routine measurements were performed. For these however special techniques had to be developed. During the 20 years of operation a number of special events occured or have been observed, sometimes with very amazing results, e.g. the 'aceton effect'. This report describes the chemical and radiochemical conditions of the reactor systems, as well as the results of the surveilance work. Not described are measurements for the many experiments. The last chapter gives in a short form a description of the most unusual events and observations. (orig.) [de

  5. Radiochemical plasma salicylamide assay using ring-labeled tritiated salicylamide

    Energy Technology Data Exchange (ETDEWEB)

    Stella, V J; Varia, S A; Riedy, M

    1979-05-01

    A rat plasma salicylamide assay was developed using ring-labeled tritiated salicylamide, synthesized by reacting salicylamide with tritium oxide in the presence of heptafluorobutyric acid. The reaction yielded /sup 3/H-salicylamide of specific activity up to 8.41 mCi/mmole, 60% yield. Plasma containing /sup 3/H-salicylamide and its metabolites was extracted with a toluene-based scintillation fluid, which was subsequently counted. Specificity for free salicylamide was demonstrated by radiochemical and standard fluorescence plasma salicylamide level-time curves. Specificity resulted from nonextraction of the salicylamide sulfate and glucuronide metabolites. Sulfatase and beta-glucuronidase treatment allowed the analysis of plasma sulfate and glucuronide conjugates as free salicylamide. This procedure should be effective for the analysis of salicylamide and its metabolites in the presence of similar phenolic compounds.

  6. Radiochemical investigations on the solubility of molybdatophosphate in phosphate determination

    International Nuclear Information System (INIS)

    Noack, S.

    1975-01-01

    The solubility of various molybdatophosphates was determined under the conditions of a gravimetric phosphate determination by radiochemical means by labelling PO 4 3- with P-32. Starting with various conditions for phosphate determination via the molybdatophosphate of quinoline, 8-hydroxyquinoline, dimorpholino ethane, N,N,N',N'-tetrakis-β-hydroxypropyl ethylene diamine and N,N,N',N'-tetrakis-β-hydroxybutyl ethylene diamine, a general working rule was developed to determine the solubility. Taking the example of quinoline molybdatophosphates, a series of influencing factors - work, concentration and measuring parameters - were investigated in order to be able to limit the reliability region of the gravimetric phosphate determination. Depending on the conditions, the measured solubilities were between 10 -10 and 10 -6 Mol/l, the corresponding degrees of precipitation between 99.0 and 99.9999%. Apparent solubility products were calculated for the different molybdatophosphates using computer programmes especially developed for this purpose. (orig./RB) [de

  7. A rapid, simple method for obtaining radiochemically pure hepatic heme

    International Nuclear Information System (INIS)

    Bonkowski, H.L.; Bement, W.J.; Erny, R.

    1978-01-01

    Radioactively-labelled heme has usually been isolated from liver to which unlabelled carrier has been added by long, laborious techniques involving organic solvent extraction followed by crystallization. A simpler, rapid method is devised for obtaining radiochemically-pure heme synthesized in vivo in rat liver from delta-amino[4- 14 C]levulinate. This method, in which the heme is extracted into ethyl acetate/glacial acetic acid and in which porphyrins are removed from the heme-containing organic phase with HCl washes, does not require addition of carrier heme. The new method gives better heme recoveries than and heme specific activities identical to, those obtained using the crystallization method. In this new method heme must be synthesized from delta-amino[4- 14 C]levulinate; it is not satisfactory to use [2- 14 C]glycine substrate because non-heme counts are isolated in the heme fraction. (Auth.)

  8. Mobile laboratories: An innovative and efficient solution for radiological characterization of sites under or after decommissioning.

    Science.gov (United States)

    Goudeau, V; Daniel, B; Dubot, D

    2017-04-21

    During the operation and the decommissioning of a nuclear site the operator must assure the protection of the workers and the environment. It must furthermore identify and classify the various wastes, while optimizing the associated costs. At all stages of the decommissioning radiological measurements are performed to determine the initial situation, to monitor the demolition and clean-up, and to verify the final situation. Radiochemical analysis is crucial for the radiological evaluation process to optimize the clean-up operations and to the respect limits defined with the authorities. Even though these types of analysis are omnipresent in activities such as the exploitation, the monitoring, and the cleaning up of nuclear plants, some nuclear sites do not have their own radiochemical analysis laboratory. Mobile facilities can overcome this lack when nuclear facilities are dismantled, when contaminated sites are cleaned-up, or in a post-accident situation. The current operations for the characterization of radiological soils of CEA nuclear facilities, lead to a large increase of radiochemical analysis. To manage this high throughput of samples in a timely manner, the CEA has developed a new mobile laboratory for the clean-up of its soils, called SMaRT (Shelter for Monitoring and nucleAR chemisTry). This laboratory is dedicated to the preparation and the radiochemical analysis (alpha, beta, and gamma) of potentially contaminated samples. In this framework, CEA and Eichrom laboratories has signed a partnership agreement to extend the analytical capacities and bring on site optimized and validated methods for different problematic. Gamma-emitting radionuclides can usually be measured in situ as little or no sample preparation is required. Alpha and beta-emitting radionuclides are a different matter. Analytical chemistry laboratory facilities are required. Mobile and transportable laboratories equipped with the necessary tools can provide all that is needed. The main

  9. LABORATORY PROCESS CONTROLLER USING NATURAL LANGUAGE COMMANDS FROM A PERSONAL COMPUTER

    Science.gov (United States)

    Will, H.

    1994-01-01

    The complex environment of the typical research laboratory requires flexible process control. This program provides natural language process control from an IBM PC or compatible machine. Sometimes process control schedules require changes frequently, even several times per day. These changes may include adding, deleting, and rearranging steps in a process. This program sets up a process control system that can either run without an operator, or be run by workers with limited programming skills. The software system includes three programs. Two of the programs, written in FORTRAN77, record data and control research processes. The third program, written in Pascal, generates the FORTRAN subroutines used by the other two programs to identify the user commands with the user-written device drivers. The software system also includes an input data set which allows the user to define the user commands which are to be executed by the computer. To set the system up the operator writes device driver routines for all of the controlled devices. Once set up, this system requires only an input file containing natural language command lines which tell the system what to do and when to do it. The operator can make up custom commands for operating and taking data from external research equipment at any time of the day or night without the operator in attendance. This process control system requires a personal computer operating under MS-DOS with suitable hardware interfaces to all controlled devices. The program requires a FORTRAN77 compiler and user-written device drivers. This program was developed in 1989 and has a memory requirement of about 62 Kbytes.

  10. Practical utilization of modeling and simulation in laboratory process waste assessments

    International Nuclear Information System (INIS)

    Lyttle, T.W.; Smith, D.M.; Weinrach, J.B.; Burns, M.L.

    1993-01-01

    At Los Alamos National Laboratory (LANL), facility waste streams tend to be small but highly diverse. Initial characterization of such waste streams is difficult in part due to a lack of tools to assist the waste generators in completing such assessments. A methodology has been developed at LANL to allow process knowledgeable field personnel to develop baseline waste generation assessments and to evaluate potential waste minimization technology. This process waste assessment (PWA) system is an application constructed within the process modeling system. The Process Modeling System (PMS) is an object-oriented, mass balance-based, discrete-event simulation using the common LISP object system (CLOS). Analytical capabilities supported within the PWA system include: complete mass balance specifications, historical characterization of selected waste streams and generation of facility profiles for materials consumption, resource utilization and worker exposure. Anticipated development activities include provisions for a best available technologies (BAT) database and integration with the LANL facilities management Geographic Information System (GIS). The environments used to develop these assessment tools will be discussed in addition to a review of initial implementation results

  11. Laboratory Tests on Post-Filtration Precipitation in the WTP Pretreatment Process

    International Nuclear Information System (INIS)

    Russell, Renee L.; Peterson, Reid A.; Rinehart, Donald E.; Crum, Jarrod V.

    2009-01-01

    Pacific Northwest National Laboratory (PNNL) has been tasked by Bechtel National Inc. (BNI) on the River Protection Project-Hanford Tank Waste Treatment and Immobilization Plant (RPP-WTP) project to perform research and development activities to resolve technical issues identified for the Pretreatment Facility (PTF). The Pretreatment Engineering Platform (PEP) was designed, constructed, and operated as part of a plan to respond to issue M12, 'Undemonstrated Leaching Processes,' of the External Flowsheet Review Team (EFRT) issue response plan (Barnes et al. 2006). The PEP is a 1/4.5-scale test platform designed to simulate the WTP pretreatment caustic leaching, oxidative leaching, ultrafiltration solids concentration, and slurry washing processes. The PEP replicates the WTP leaching processes using prototypic equipment and control strategies. A simplified flow diagram of the PEP system is shown in Figure 1.1. Two operating scenarios are currently being evaluated for the ultrafiltration process (UFP) and leaching operations. The first scenario has caustic leaching performed in the UFP-2 ultrafiltration feed vessels (i.e., vessel UFP-VSL-T02A in the PEP; and vessels UFP-VSL-00002A and B in the WTP PTF). The second scenario has caustic leaching conducted in the UFP-1 ultrafiltration feed preparation vessels (i.e., vessels UFP-VSL-T01A and B in the PEP; vessels UFP-VSL-00001A and B in the WTP PTF).

  12. Effects of process parameters on solid self-microemulsifying particles in a laboratory scale fluid bed.

    Science.gov (United States)

    Mukherjee, Tusharmouli; Plakogiannis, Fotios M

    2012-01-01

    The purpose of this study was to select the critical process parameters of the fluid bed processes impacting the quality attribute of a solid self-microemulsifying (SME) system of albendazole (ABZ). A fractional factorial design (2(4-1)) with four parameters (spray rate, inlet air temperature, inlet air flow, and atomization air pressure) was created by MINITAB software. Batches were manufactured in a laboratory top-spray fluid bed at 625-g scale. Loss on drying (LOD) samples were taken throughout each batch to build the entire moisture profiles. All dried granulation were sieved using mesh 20 and analyzed for particle size distribution (PSD), morphology, density, and flow. It was found that as spray rate increased, sauter-mean diameter (D(s)) also increased. The effect of inlet air temperature on the peak moisture which is directly related to the mean particle size was found to be significant. There were two-way interactions between studied process parameters. The main effects of inlet air flow rate and atomization air pressure could not be found as the data were inconclusive. The partial least square (PLS) regression model was found significant (P SME manufacturing process.

  13. Cost analysis and cost justification of automated data processing in the clinical laboratory.

    Science.gov (United States)

    Westlake, G E

    1983-03-01

    Prospective cost analysis of alternative data processing systems can be facilitated by proper selection of the costs to be analyzed and realistic appraisal of the effect on staffing. When comparing projects with dissimilar cash flows, techniques such as analysis of net present value can be helpful in identifying financial benefits. Confidence and accuracy in prospective analyses will increase as more retrospective studies are published. Several accounts now in the literature describe long-term experience with turnkey laboratory information systems. Acknowledging the difficulty in longitudinal studies, they all report favorable effects on labor costs and recovery of lost charges. Enthusiasm is also expressed for the many intangible benefits of the systems. Several trends suggest that cost justification and cost effectiveness will be more easily demonstrated in the future. These are the rapidly decreasing cost of hardware (with corresponding reduction in service costs) and the entry into the market of additional systems designed for medium to small hospitals. The effect of broadening the sales base may be lower software prices. Finally, operational and executive data management and reporting are destined to become the premier extensions of the LIS for cost justification. Aptly applied, these facilities can promote understanding of costs, control of costs, and greater efficiency in providing laboratory services.

  14. Contact pressure distribution during the polishing process of ceramic tiles: A laboratory investigation

    International Nuclear Information System (INIS)

    Sani, A S A; Hamedon, Z; Azhari, A; Sousa, F J P

    2016-01-01

    During the polishing process of porcelain tiles the difference in scratching speed between innermost and peripheral abrasives leads to pressure gradients linearly distributed along the radial direction of the abrasive tool. The aim of this paper is to investigate such pressure gradient in laboratory scale. For this purpose polishing tests were performed on ceramic tiles according to the industrial practices using a custom-made CNC tribometer. Gradual wear on both abrasives and machined surface of the floor tile were measured. The experimental results suggested that the pressure gradient tends to cause an inclination of the abraded surfaces, which becomes stable after a given polishing period. In addition to the wear depth of the machined surface, the highest value of gloss and finest surface finish were observed at the lowest point of the worn out surface of the ceramic floor tile corresponding to the point of highest pressure and lowest scratching speed. (paper)

  15. The AMES Laboratory chemical disposal site removal action: Source removal, processing, and disposal

    International Nuclear Information System (INIS)

    Shirley, R.S.

    1996-01-01

    The Ames Laboratory has historically supported the U.S. Department of Energy (USDOE) and its predecessor agencies by providing research into the purification and manufacturing of high purity uranium, thorium, and yttrium metals. Much of this work was accomplished in the late 1950s and early 1960s prior to the legislation of strict rules and regulations covering the disposal of radioactive and chemical wastes. As a result, approximately 800 cubic meters of low-level radioactive wastes, chemical wastes, and contaminated debris were disposed in nine near surface cells located in a 0.75 hectare plot of land owned by Iowa State University in Ames, Iowa. Under a national contract with the U.S. Army Corps of Engineers (USACE), OHM Remediation Services Corp (OHM) was tasked with providing turnkey environmental services to remove, process, package, transport, and coordinate the disposal of the waste materials and contaminated environmental media

  16. Waste processing to support 99Mo production at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Longley, S.; Carson, S.; McDonald, M.

    1997-01-01

    As part of the isotope production program at Sandia National Laboratories (SNL), procedures are being finalized for the production of 99 Mo from the irradiation of 235 U-coated stainless-steel targets at the Technical Area (TA) V reactor and hot-cell facilities. Methods have been identified and tested for the management of the nonproduct (waste) material as the final step in the production process. These methods were developed utilizing the waste material from a series of cold and hot tests, beginning with depleted uranium powder and culminating with a test involving an irradiated 235 U target with an initial fission product inventory of ∼18000 Ci at the end of the irradiation cycle. This paper describes the radioactive waste management from the isotope production

  17. Development of laboratory and process sensors to monitor particle size distribution of industrial slurries

    Energy Technology Data Exchange (ETDEWEB)

    Pendse, H.P.

    1992-10-01

    In this paper we present a novel measurement technique for monitoring particle size distributions of industrial colloidal slurries based on ultrasonic spectroscopy and mathematical deconvolution. An on-line sensor prototype has been developed and tested extensively in laboratory and production settings using mineral pigment slurries. Evaluation to date shows that the sensor is capable of providing particle size distributions, without any assumptions regarding their functional form, over diameters ranging from 0.1 to 100 micrometers in slurries with particle concentrations of 10 to 50 volume percents. The newly developed on-line sensor allows one to obtain particle size distributions of commonly encountered inorganic pigment slurries under industrial processing conditions without dilution.

  18. The Ames Laboratory Chemical Disposal Site removal action: Source removal, processing, and disposal

    International Nuclear Information System (INIS)

    Shirley, R.S.

    1995-01-01

    The Ames Laboratory has historically supported the US Department of Energy (USDOE) and its predecessor agencies by providing research into the purification and manufacturing of high purity uranium, thorium, and yttrium metals. Much of this work was accomplished in the late 1950s and early 1960s prior to the legislation of strict rules and regulations covering the disposal of radioactive and chemical wastes. As a result, approximately 800 cubic meters of low-level radioactive wastes, mixed wastes, and contaminated debris were disposed in nine near surface cells located in a 0.75 hectare plot of land owned by Iowa State University in Ames, Iowa. Under a national contract with the US Army Corps of Engineers (USACE), OHM Remediation Services Corp. (OHM) was tasked with providing turnkey environmental services to remove, process, package, transport, and coordinate the disposal of the waste materials and contaminated environmental media

  19. Laboratory modelling of the transfer processes between the ocean and atmosphere in the boundary layers

    Directory of Open Access Journals (Sweden)

    Sergeev Daniil

    2017-01-01

    Full Text Available The processes of momentum and heat transfer between ocean and atmosphere in the boundary layer were investigated within laboratory modeling for a wide range of wind speed and surface wave including hurricane conditions. Experiments were carried out on the Wind-Wave Flume of the Large Thermostratified Tank of IAP RAS. A special net located under the surface at different depths allows to vary parameters of surface waves independently on wind parameters. Theory of self-similarity of air flow parameters in the flume was used to calculate values aerodynamic and heat transfer coefficients from the measured velocity and temperature profiles by Pito and hotfilm gauges respectively. Simultaneous measurements of surface elevation with system wire allow to obtain spectra and integral parameters of waves. It was demonstrated that in contrast to the drag coefficient, heat transfer coefficient is virtually independent of wind speed and wave parameters to the moment of the beginning of spray generation and then increases rapidly.

  20. Integration of laboratory bioassays into the risk-based corrective action process

    International Nuclear Information System (INIS)

    Edwards, D.; Messina, F.; Clark, J.

    1995-01-01

    Recent data generated by the Gas Research Institute (GRI) and others indicate that residual hydrocarbon may be bound/sequestered in soil such that it is unavailable for microbial degradation, and thus possibly not bioavailable to human/ecological receptors. A reduction in bioavailability would directly equate to reduced exposure and, therefore, potentially less-conservative risk-based cleanup soil goals. Laboratory bioassays which measure bioavailability/toxicity can be cost-effectively integrated into the risk-based corrective action process. However, in order to maximize the cost-effective application of bioassays several site-specific parameters should be addressed up front. This paper discusses (1) the evaluation of parameters impacting the application of bioassays to soils contaminated with metals and/or petroleum hydrocarbons and (2) the cost-effective integration of bioassays into a tiered ASTM type framework for risk-based corrective action

  1. Project Title: Radiochemical Analysis by High Sensitivity Dual-Optic Micro X-ray Fluorescence

    International Nuclear Information System (INIS)

    Havrilla, George J.; Gao, Ning

    2002-01-01

    A novel dual-optic micro X-ray fluorescence instrument will be developed to do radiochemical analysis of high-level radioactive wastes at DOE sites such as Savannah River Site and Hanford. This concept incorporates new X-ray optical elements such as monolithic polycapillaries and double bent crystals, which focus X-rays. The polycapillary optic can be used to focus X-rays emitted by the X-ray tube thereby increasing the X-ray flux on the sample over 1000 times. Polycapillaries will also be used to collect the X-rays from the excitation site and screen the radiation background from the radioactive species in the specimen. This dual-optic approach significantly reduces the background and increases the analyte signal thereby increasing the sensitivity of the analysis. A doubly bent crystal used as the focusing optic produces focused monochromatic X-ray excitation, which eliminates the bremsstrahlung background from the X-ray source. The coupling of the doubly bent crystal for monochromatic excitation with a polycapillary for signal collection can effectively eliminate the noise background and radiation background from the specimen. The integration of these X-ray optics increases the signal-to-noise and thereby increases the sensitivity of the analysis for low-level analytes. This work will address a key need for radiochemical analysis of high-level waste using a non-destructive, multi-element, and rapid method in a radiation environment. There is significant potential that this instrumentation could be capable of on-line analysis for process waste stream characterization at DOE sites

  2. V-SIPAL - A VIRTUAL LABORATORY FOR SATELLITE IMAGE PROCESSING AND ANALYSIS

    Directory of Open Access Journals (Sweden)

    K. M. Buddhiraju

    2012-09-01

    Full Text Available In this paper a virtual laboratory for the Satellite Image Processing and Analysis (v-SIPAL being developed at the Indian Institute of Technology Bombay is described. v-SIPAL comprises a set of experiments that are normally carried out by students learning digital processing and analysis of satellite images using commercial software. Currently, the experiments that are available on the server include Image Viewer, Image Contrast Enhancement, Image Smoothing, Edge Enhancement, Principal Component Transform, Texture Analysis by Co-occurrence Matrix method, Image Indices, Color Coordinate Transforms, Fourier Analysis, Mathematical Morphology, Unsupervised Image Classification, Supervised Image Classification and Accuracy Assessment. The virtual laboratory includes a theory module for each option of every experiment, a description of the procedure to perform each experiment, the menu to choose and perform the experiment, a module on interpretation of results when performed with a given image and pre-specified options, bibliography, links to useful internet resources and user-feedback. The user can upload his/her own images for performing the experiments and can also reuse outputs of one experiment in another experiment where applicable. Some of the other experiments currently under development include georeferencing of images, data fusion, feature evaluation by divergence andJ-M distance, image compression, wavelet image analysis and change detection. Additions to the theory module include self-assessment quizzes, audio-video clips on selected concepts, and a discussion of elements of visual image interpretation. V-SIPAL is at the satge of internal evaluation within IIT Bombay and will soon be open to selected educational institutions in India for evaluation.

  3. Composting clam processing wastes in a laboratory- and pilot-scale in-vessel system.

    Science.gov (United States)

    Hu, Zhenhu; Lane, Robert; Wen, Zhiyou

    2009-01-01

    Waste materials from the clam processing industry (offal, shells) have several special characteristics such as a high salinity level, a high nitrogen content, and a low C/N ratio. The traditional disposal of clam waste through landfilling is facing the challenges of limited land available, increasing tipping fees, and strict environmental and regulatory scrutiny. The aim of this work is to investigate the performance of in-vessel composting as an alternative for landfill application of these materials. Experiments were performed in both laboratory-scale (5L) and pilot-scale (120L) reactors, with woodchips as the bulking agent. In the laboratory-scale composting test, the clam waste and woodchips were mixed in ratios from 1:0.5 to 1:3 (w/w, wet weight). The high ratios resulted in a better temperature performance, a higher electrical conductivity, and a higher ash content than the low-ratio composting. The C/N ratio of the composts was in the range of 9:1-18:1. In the pilot-scale composting test, a 1:1 ratio of clam waste to woodchips was used. The temperature profile during the composting process met the US Environmental Protection Agency sanitary requirement. The final cured compost had a C/N ratio of 14.6, with an ash content of 167.0+/-14.1g/kg dry matter. In addition to the major nutrients (carbon, nitrogen, calcium, magnesium, phosphorus, potassium, sulfur, and sodium), the compost also contained trace amounts of zinc, manganese, copper, and boron, indicating that the material can be used as a good resource for plant nutrients.

  4. Food and Drug Administration process validation activities to support 99Mo production at Sandia National Laboratories

    International Nuclear Information System (INIS)

    McDonald, M.J.; Bourcier, S.C.; Talley, D.G.

    1997-01-01

    Prior to 1989 99 Mo was produced in the US by a single supplier, Cintichem Inc., Tuxedo, NY. Because of problems associated with operating its facility, in 1989 Cintichem elected to decommission the facility rather than incur the costs for repair. The demise of the 99 Mo capability at Cintichem left the US totally reliant upon a single foreign source, Nordion International, located in Ottawa Canada. In 1992 the DOE purchased the Cintichem 99 Mo Production Process and Drug Master File (DMF). In 1994 the DOE funded Sandia National Laboratories (SNL) to produce 99 Mo. Although Cintichem produced 99 Mo and 99m Tc generators for many years, there was no requirement for process validation which is now required by the Food and Drug Administration (FDA). In addition to the validation requirement, the requirements for current Good manufacturing Practices were codified into law. The purpose of this paper is to describe the process validation being conducted at SNL for the qualification of SNL as a supplier of 99 Mo to US pharmaceutical companies

  5. [Internal audit in medical laboratory: what means of control for an effective audit process?].

    Science.gov (United States)

    Garcia-Hejl, Carine; Chianéa, Denis; Dedome, Emmanuel; Sanmartin, Nancy; Bugier, Sarah; Linard, Cyril; Foissaud, Vincent; Vest, Philippe

    2013-01-01

    To prepare the French Accreditation Committee (COFRAC) visit for initial certification of our medical laboratory, our direction evaluated its quality management system (QMS) and all its technical activities. This evaluation was performed owing an internal audit. This audit was outsourced. Auditors had an expertise in audit, a whole knowledge of biological standards and were independent. Several nonconformities were identified at that time, including a lack of control of several steps of the internal audit process. Hence, necessary corrective actions were taken in order to meet the requirements of standards, in particular, the formalization of all stages, from the audit program, to the implementation, review and follow-up of the corrective actions taken, and also the implementation of the resources needed to carry out audits in a pre-established timing. To ensure an optimum control of each step, the main concepts of risk management were applied: process approach, root cause analysis, effects and criticality analysis (FMECA). After a critical analysis of our practices, this methodology allowed us to define our "internal audit" process, then to formalize it and to follow it up, with a whole documentary system.

  6. Strain Localization and Weakening Processes in Viscously Deforming Rocks: Numerical Modeling Based on Laboratory Torsion Experiments

    Science.gov (United States)

    Doehmann, M.; Brune, S.; Nardini, L.; Rybacki, E.; Dresen, G.

    2017-12-01

    Strain localization is an ubiquitous process in earth materials observed over a broad range of scales in space and time. Localized deformation and the formation of shear zones and faults typically involves material softening by various processes, like shear heating and grain size reduction. Numerical modeling enables us to study the complex physical and chemical weakening processes by separating the effect of individual parameters and boundary conditions. Using simple piece-wise linear functions for the parametrization of weakening processes allows studying a system at a chosen (lower) level of complexity (e.g. Cyprych et al., 2016). In this study, we utilize a finite element model to test two weakening laws that reduce the strength of the material depending on either the I) amount of accumulated strain or II) deformational work. Our 2D Cartesian models are benchmarked to single inclusion torsion experiments performed at elevated temperatures of 900 °C and pressures of up to 400 MPa (Rybacki et al., 2014). The experiments were performed on Carrara marble samples containing a weak Solnhofen limestone inclusion at a maximum strain rate of 2.0*10-4 s-1. Our models are designed to reproduce shear deformation of a hollow cylinder equivalent to the laboratory setup, such that material leaving one side of the model in shear direction enters again on the opposite side using periodic boundary conditions. Similar to the laboratory tests, we applied constant strain rate and constant stress boundary conditions.We use our model to investigate the time-dependent distribution of stress and strain and the effect of different parameters. For instance, inclusion rotation is shown to be strongly dependent on the viscosity ratio between matrix and inclusion and stronger ductile weakening increases the localization rate while decreasing shear zone width. The most suitable weakening law for representation of ductile rock is determined by combining the results of parameter tests with

  7. Laboratory and Cloud Chamber Studies of Formation Processes and Properties of Atmospheric Ice Particles

    Science.gov (United States)

    Leisner, T.; Abdelmonem, A.; Benz, S.; Brinkmann, M.; Möhler, O.; Rzesanke, D.; Saathoff, H.; Schnaiter, M.; Wagner, R.

    2009-04-01

    The formation of ice in tropospheric clouds controls the evolution of precipitation and thereby influences climate and weather via a complex network of dynamical and microphysical processes. At higher altitudes, ice particles in cirrus clouds or contrails modify the radiative energy budget by direct interaction with the shortwave and longwave radiation. In order to improve the parameterisation of the complex microphysical and dynamical processes leading to and controlling the evolution of tropospheric ice, laboratory experiments are performed at the IMK Karlsruhe both on a single particle level and in the aerosol and cloud chamber AIDA. Single particle experiments in electrodynamic levitation lend themselves to the study of the interaction between cloud droplets and aerosol particles under extremely well characterized and static conditions in order to obtain microphysical parameters as freezing nucleation rates for homogeneous and heterogeneous ice formation. They also allow the observation of the freezing dynamics and of secondary ice formation and multiplication processes under controlled conditions and with very high spatial and temporal resolution. The inherent droplet charge in these experiments can be varied over a wide range in order to assess the influence of the electrical state of the cloud on its microphysics. In the AIDA chamber on the other hand, these processes are observable under the realistic dynamic conditions of an expanding and cooling cloud- parcel with interacting particles and are probed simultaneously by a comprehensive set of analytical instruments. By this means, microphysical processes can be studied in their complex interplay with dynamical processes as for example coagulation or particle evaporation and growth via the Bergeron - Findeisen process. Shortwave scattering and longwave absorption properties of the nucleating and growing ice crystals are probed by in situ polarised laser light scattering measurements and infrared extinction

  8. Determination of selenium in roasted beans coffee samples consumed in Algeria by radiochemical neutron activation analysis method

    International Nuclear Information System (INIS)

    Messaoudi, Mohammed; Begaa, Samir; Hamidatou, Lylia; Salhi, M'hamed

    2018-01-01

    The essential trace element selenium is a focus of attention due to its effects on human health, there being consequences of both its deficiency and excess. Due to the ultra-trace content of selenium, the neutron activation analysis method (NAA) is difficult to apply. We therefore made use of the radiochemical neutron activation analysis (RNAA) to determine Se at low level concentrations in several consumed food items in Algeria. A radiochemical procedure based on liquid-liquid separation was established in our laboratory. In this research we focused on the determination of selenium in two species of coffee: Arabica and Robusta. The accuracy of the method was assessed by analyzing the certified reference material NIST-SRM 1573a (tomato leaves). The results obtained show a selenium variation from 0.025 to 0.052 μg/g in coffee beans and an average yield of the separation of about 85%. The results of this study were compared with those obtained with samples from Brazilian, Caribbean, Indian and Kenyan coffee beans.

  9. Optimum Condition for Plutonium Electrodeposition Process in Radiochemistry and Environment Laboratory, Nuclear Malaysia

    International Nuclear Information System (INIS)

    Yii, Mei-Wo; Abdullah Siddiqi Ismail

    2014-01-01

    Determination of alpha emitting plutonium radionuclides such as Pu-238, Pu-239 and Pu-240 concentrations inside a sample require lots of radiochemistry purification process to separate them from other interfering alpha emitters. These pure isotopes are then been electrodeposited onto a stainless steel disc and quantified using alpha spectrometry counter. In Radiochemistry and Environment Laboratory (RAS), Nuclear Malaysia, the quantification is done by comparing these isotopes with the recovery of known amount plutonium tracer, Pu-242, that been added into the sample prior analysis. This study been conducted to find the optimum conditions for the electrolysis process used at RAS. Four variable parameters that may interfere the percentage recovery of tracer hence the current, cathode to anode distance, pH and electrolysis duration had been identify and studied. Study was carry out using Pu-242 standard solution and the deposition disc was counted using Zinc Sulphite (silver) counter. Studies outcome suggested that the optimum conditions to reduce plutonium ion happens at 1-1.1 ampere of current, 3-5 mm of electrodes distance, pH 2.2-2.5 and a minimal electrolysis duration of 2 hours. (author)

  10. Electrokinetic demonstration at Sandia National Laboratories: Use of transference numbers for site characterization and process evaluation

    International Nuclear Information System (INIS)

    Lindgren, E.R.; Mattson, E.D.

    1997-01-01

    Electrokinetic remediation is generally an in situ method using direct current electric potentials to move ionic contaminants and/or water to collection electrodes. The method has been extensively studied for application in saturated clayey soils. Over the past few years, an electrokinetic extraction method specific for sandy, unsaturated soils has been developed and patented by Sandia National Laboratories. A RCRA RD ampersand D permitted demonstration of this technology for the in situ removal of chromate contamination from unsaturated soils in a former chromic acid disposal pit was operated during the summer and fall of 1996. This large scale field test represents the first use of electrokinetics for the removal of heavy metal contamination from unsaturated soils in the United States and is part of the US EPA Superfund Innovative Technology Evaluation (SITE) Program. Guidelines for characterizing a site for electrokinetic remediation are lacking, especially for applications in unsaturated soil. The transference number of an ion is the fraction of the current carried by that ion in an electric field and represents the best measure of contaminant removal efficiency in most electrokinetic remediation processes. In this paper we compare the transference number of chromate initially present in the contaminated unsaturated soil, with the transference number in the electrokinetic process effluent to demonstrate the utility of evaluating this parameter

  11. Laboratory modelling of the physico-chemical processes in the cosmic gas-dust clouds

    International Nuclear Information System (INIS)

    Bakulina, I.N.; Blashenkov, N.M.; Varshalovich, D.A.; Lavrent'ev, G.Ya.; Shustrov, B.N.

    1980-01-01

    The preliminary results of an experiment on the complex laboratory modelling of the physico-chemical processes proceeding in the interstellar gas clouds are presented. The purpose of the modelling is an analysis of the molecule formation and dissociation processes kinetics. The basic component of the modelling system is 10 cm diameter spherical container with cooled walls (the dust particles surface analogue). The high frequency discharger (the discharge region - the H 2 zone analogue) is placed in the central part of the container. The container contains the mixture of simple gases: 10 -1 Tor of H 2 and He, 10 -2 Tor of CO, O 2 and N 2 and 0.5x10 -2 Tor of H 2 S (an analogue of the H 1 zone). The reactions are induced by the electrodeless high-frequency discharge (f=20 MHz) with the discharge power of 0.1-1 W. The resulting mixture has been analyzed by the high-resolution magnetic resonance mass spectrometer. (M/ΔM=2x10 4 ) with an electron impact source. It is shown that, in the reactions of the formation of many on the interstellar molecules, the on the cold dust surface reactions rather than the gas-phase reactions may play the dominant role

  12. Radioactive preparations. Determination of radiochemical purity by thin-layer chromatography

    International Nuclear Information System (INIS)

    1986-01-01

    The standard sets the data which must be attached to every sample, and the equipment, chemicals and auxiliary substances used in the determination of radiochemical purity of substances by chromatography. Described are preparation of the sample, the procedure of sample deposition, the development, drying and detection of the radioactive preparation. The qualitative and quantitative assessment of the radiochromatogram is described as are the calculation of radiochemical purity and the determination of the reproducibility of measurement of radiochemical purity of radioactive preparations. (E.S.)

  13. Comparative Laboratory and Numerical Simulations of Shearing Granular Fault Gouge: Micromechanical Processes

    Science.gov (United States)

    Morgan, J. K.; Marone, C. J.; Guo, Y.; Anthony, J. L.; Knuth, M. W.

    2004-12-01

    Laboratory studies of granular shear zones have provided significant insight into fault zone processes and the mechanics of earthquakes. The micromechanisms of granular deformation are more difficult to ascertain, but have been hypothesized based on known variations in boundary conditions, particle properties and geometries, and mechanical behavior. Numerical simulations using particle dynamics methods (PDM) can offer unique views into deforming granular shear zones, revealing the precise details of granular microstructures, particle interactions, and packings, which can be correlated with macroscopic mechanical behavior. Here, we describe a collaborative program of comparative laboratory and numerical experiments of granular shear using idealized materials, i.e., glass beads, glass rods or pasta, and angular sand. Both sets of experiments are carried out under similar initial and boundary conditions in a non-fracturing stress regime. Phenomenologically, the results of the two sets of experiments are very similar. Peak friction values vary as a function of particle dimensionality (1-D vs. 2-D vs. 3-D), particle angularity, particle size and size distributions, boundary roughness, and shear zone thickness. Fluctuations in shear strength during an experiment, i.e., stick-slip events, can be correlated with distinct changes in the nature, geometries, and durability of grain bridges that support the shear zone walls. Inclined grain bridges are observed to form, and to support increasing loads, during gradual increases in assemblage strength. Collapse of an individual grain bridge leads to distinct localization of strain, generating a rapidly propagating shear surface that cuts across multiple grain bridges, accounting for the sudden drop in strength. The distribution of particle sizes within an assemblage, along with boundary roughness and its periodicity, influence the rate of formation and dissipation of grain bridges, thereby controlling friction variations during

  14. 99mTc-ECD: Comparison of radiochemical purity evaluation techniques

    International Nuclear Information System (INIS)

    Dumont, A.; De Beco, V.; Ait Ben Ali, S.; Goudou-Sinha, C.; Izembart, M.; Jourdain, J.R.; Lemercier, V.; Linsker, S.; Lours, S.; Moati, F.; Pajard, D.; Piketty, M.L.; Rizzo, N.; Schlageter, M.H.; Moretti, J.L.

    1997-01-01

    The aim of this study was to validate a testing method for the radiochemical purity (RCP) of the preparations of 99m Tc - ECD that is to be reproducible and easy to realize in services of Nuclear Medicine. After a review of literature, four thin-layer chromatography techniques allowing to evidence the TcO 4 - were evaluated: no.1 - Papier Whatman 31ET / ethyl acetate; no.2 - Papier Whatman 3MM chr / ethyl acetate; no.3 - ITLC Silica gel / ethyl acetate; no.4 - Baker Flex silica gel aluminium oxide IB-F / ethyl acetate (the method proposed by the laboratory). The technique no.1 has presented a bad reproducibility, as well as percentages of RCP very different from those obtained by the other techniques. The techniques no.2 and no.3, although rapid, are characterized by lower reproducibilities in comparison with technique no.4, with, some times, peaks of undetermined nature on the radio-chromatograms no.3. So, in spite of a slower migration (10 min.) the technique no.4 has been selected from the group as the most reliable technique. For this technique, the comparison between the two modes of reading the chromatography (by means of a radio-chromatograph or by measuring the activity of the two halves of the plate by an activity-meter), has shown no significant difference in RCP. Consequently, this method (Baker Flex / ethyl acetate) may by adapted in any service of nuclear medicine, no matter of its equipment

  15. LWR spent-fuel radiochemical measurements and comparison with ORIGEN2 predictions

    International Nuclear Information System (INIS)

    Blahnik, D.E.; Jenquin, U.P.; Guenther, R.J.

    1988-01-01

    The Materials Characterization Center (MCC) at Pacific Northwest Laboratory is responsible for providing characterized spent fuel, designated approved testing material (ATMs) for subsequent use in the investigation of nuclear waste disposal forms by the US Department of Energy geologic repository project. The ATMs are selected to assure that test material is available that has a representative range of characteristics important to spent-fuel behavior in a geologic repository. Burnup and fission gas release were the primary criteria for selecting the ATMs. The five spent-fuel ATMs (ATM-101, -103, -104, -105, and -106) currently being characterized by the MCC have rod average burnups ranging from 20 to 43 MWd/kg M, fission gas releases ranging from 0.2 to 11.2%, and are from both boiling water reactors and pressurized water reactors. Radiochemical analyses of the fuel included measurements of 148 Nd (for fuel burnup), the isotopes of uranium and plutonium, and nuclides of importance to repository performance. Cladding samples were analyzed for 14 C. The measured values of selected nuclides were compared with values obtained from calculations with the ORIGEN2 code that was used to predict isotopic quantities for all of the ATMS. Ratios of the ORIGEN2 calculated values to the measured values for ATM-103 and ATM-106 fuel are given

  16. Laboratory-scale dry/wet-milling process for the extraction of starch and gluten from wheat

    NARCIS (Netherlands)

    Steeneken, P.A.M.; Helmens, H.J.

    2009-01-01

    A laboratory-scale process is presented for the manufacture of starch and gluten from wheat. Main feature of this process is that whole wheat kernels are crushed dry between smooth rolls prior to wet disintegration in excess water in such way that gluten formation is prevented and fibres can be

  17. Parameter Sensitivity and Laboratory Benchmarking of a Biogeochemical Process Model for Enhanced Anaerobic Dechlorination

    Science.gov (United States)

    Kouznetsova, I.; Gerhard, J. I.; Mao, X.; Barry, D. A.; Robinson, C.; Brovelli, A.; Harkness, M.; Fisher, A.; Mack, E. E.; Payne, J. A.; Dworatzek, S.; Roberts, J.

    2008-12-01

    A detailed model to simulate trichloroethene (TCE) dechlorination in anaerobic groundwater systems has been developed and implemented through PHAST, a robust and flexible geochemical modeling platform. The approach is comprehensive but retains flexibility such that models of varying complexity can be used to simulate TCE biodegradation in the vicinity of nonaqueous phase liquid (NAPL) source zones. The complete model considers a full suite of biological (e.g., dechlorination, fermentation, sulfate and iron reduction, electron donor competition, toxic inhibition, pH inhibition), physical (e.g., flow and mass transfer) and geochemical processes (e.g., pH modulation, gas formation, mineral interactions). Example simulations with the model demonstrated that the feedback between biological, physical, and geochemical processes is critical. Successful simulation of a thirty-two-month column experiment with site soil, complex groundwater chemistry, and exhibiting both anaerobic dechlorination and endogenous respiration, provided confidence in the modeling approach. A comprehensive suite of batch simulations was then conducted to estimate the sensitivity of predicted TCE degradation to the 36 model input parameters. A local sensitivity analysis was first employed to rank the importance of parameters, revealing that 5 parameters consistently dominated model predictions across a range of performance metrics. A global sensitivity analysis was then performed to evaluate the influence of a variety of full parameter data sets available in the literature. The modeling study was performed as part of the SABRE (Source Area BioREmediation) project, a public/private consortium whose charter is to determine if enhanced anaerobic bioremediation can result in effective and quantifiable treatment of chlorinated solvent DNAPL source areas. The modelling conducted has provided valuable insight into the complex interactions between processes in the evolving biogeochemical systems

  18. Laboratory-Scale Bismuth Phosphate Extraction Process Simulation To Track Fate of Fission Products

    Energy Technology Data Exchange (ETDEWEB)

    Serne, R. JEFFREY; Lindberg, Michael J.; Jones, Thomas E.; Schaef, Herbert T.; Krupka, Kenneth M.

    2007-02-28

    Recent field investigation that collected and characterized vadose zone sediments from beneath inactive liquid disposal facilities at the Hanford 200 Areas show lower than expected concentrations of a long-term risk driver, Tc-99. Therefore laboratory studies were performed to re-create one of the three processes that were used to separate the plutonium from spent fuel and that created most of the wastes disposed or currently stored in tanks at Hanford. The laboratory simulations were used to compare with current estimates based mainly on flow sheet estimates and spotty historical data. Three simulations of the bismuth phosphate precipitation process show that less that 1% of the Tc-99, Cs-135/137, Sr-90, I-129 carry down with the Pu product and thus these isotopes should have remained within the metals waste streams that after neutralization were sent to single shell tanks. Conversely, these isotopes should not be expected to be found in the first and subsequent cycle waste streams that went to cribs. Measurable quantities (~20 to 30%) of the lanthanides, yttrium, and trivalent actinides (Am and Cm) do precipitate with the Pu product, which is higher than the 10% estimate made for current inventory projections. Surprisingly, Se (added as selenate form) also shows about 10% association with the Pu/bismuth phosphate solids. We speculate that the incorporation of some Se into the bismuth phosphate precipitate is caused by selenate substitution into crystal lattice sites for the phosphate. The bulk of the U daughter product Th-234 and Np-237 daughter product Pa-233 also associate with the solids. We suspect that the Pa daughter products of U (Pa-234 and Pa-231) would also co-precipitate with the bismuth phosphate induced solids. No more than 1 % of the Sr-90 and Sb-125 should carry down with the Pu product that ultimately was purified. Thus the current scheme used to estimate where fission products end up being disposed overestimates by one order of magnitude the

  19. 324 Building radiochemical engineering cells, high-level vault, low-level vault, and associated areas closure plan

    International Nuclear Information System (INIS)

    Barnett, J.M.

    1998-01-01

    The Hanford Site, located adjacent to and north of Richland, Washington, is operated by the US Department of Energy, Richland Operations Office (RL). The 324 Building is located in the 300 Area of the Hanford Site. The 324 Building was constructed in the 1960s to support materials and chemical process research and development activities ranging from laboratory/bench-scale studies to full engineering-scale pilot plant demonstrations. In the mid-1990s, it was determined that dangerous waste and waste residues were being stored for greater than 90 days in the 324 Building Radiochemical Engineering Cells (REC) and in the High-Level Vault/Low-Level Vault (HLV/LLV) tanks. [These areas are not Resource Conservation and Recovery Act of 1976 (RCRA) permitted portions of the 324 Building.] Through the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-89, agreement was reached to close the nonpermitted RCRA unit in the 324 Building. This closure plan, managed under TPA Milestone M-20-55, addresses the identified building areas targeted by the Tri-Party Agreement and provides commitments to achieve the highest degree of compliance practicable, given the special technical difficulties of managing mixed waste that contains high-activity radioactive materials, and the physical limitations of working remotely in the areas within the subject closure unit. This closure plan is divided into nine chapters. Chapter 1.0 provides the introduction, historical perspective, 324 Building history and current mission, and the regulatory basis and strategy for managing the closure unit. Chapters 2.0, 3.0, 4.0, and 5.0 discuss the detailed facility description, process information, waste characteristics, and groundwater monitoring respectively. Chapter 6.0 deals with the closure strategy and performance standard, including the closure activities for the B-Cell, D-Cell, HLV, LLV; piping and miscellaneous associated building areas. Chapter 7.0 addresses the

  20. Radiochemical search for neutron-rich isotopes of element 107

    International Nuclear Information System (INIS)

    Schaedel, M.

    1987-01-01

    Recent mass calculations have indicated that there is a region of deformed nuclei around neutron number N=162 that is especially stable against spontaneous fission. Barrier heights of about 5 MeV for Z = 107 nuclides can be extrapolated. To search for new, neutron-rich isotopes of element 107 in radiochemical experiments with 254 Es as a target an on-line chemical separation of element 107 (EKA-Rhenium), especially from the actinide elements is needed. An on-line gas-phase chemistry was developed with the homolog Re based on the volatility of the oxide which is transported in an O 2 containing atmosphere along a temperature gradient in a quartz tube and is condensed onto a thin Ta coated Ni-foil. The authors applied this technique in two series of experiments with their rotating wheel on-line gas-phase chemistry apparatus at the 88-inch cyclotron where they irradiated 254 Es as a target with 93 MeV and 96 MeV 16 O ions to search for 266 107. The assignment of the observed alpha events between 8 and 9 MeV to possibly (1) non actinide contaminants like 212 Po, (2) known isotopes of heavy elements like 261 105, or (3) a new isotope will be discussed

  1. Development of a radiochemical sensor. Part I: Feasibility study

    Energy Technology Data Exchange (ETDEWEB)

    Tarancon, A. [Departament de Quimica Analitica, Facultat de Quimica, Universitat de Barcelona, C/ Marti Franques 1, 08028 Barcelona (Spain); Garcia, J.F. [Departament de Pintura, Facultat de Belles Arts, Universitat de Barcelona, C/ Pau Gargallo 4, 08028 Barcelona (Spain)]. E-mail: jfgarcia@apolo.qui.ub.es; Rauret, G. [Departament de Quimica Analitica, Facultat de Quimica, Universitat de Barcelona, C/ Marti Franques 1, 08028 Barcelona (Spain)

    2005-05-04

    The evolution of nuclear activities and criteria for radiation protection have led to a continuous increase in measures to monitor and control the environment and therefore in the number of determinations required for such purposes. Classical analytical procedures are time-consuming, labor-intense and generate a large amount of waste. The alternative use of sensors for such determinations has seen very limited development. The present study focuses on the evaluation of the behavior of a prototype radiochemical sensor for liquid effluents. The sensor is based on a receptor made of a plastic scintillator and is capable of continuous, on-time and accurate remote quantification of the activity of alpha, beta and beta-gamma emitters. Low-level active solutions of {sup 90}Sr/{sup 90}Y, {sup 238}Pu, {sup 134}Cs and {sup 60}Co in matrices of groundwater, seawater and drinking water were quantified with prediction errors lower than 10% in most cases. The study also yields information about light generation and transmission and transductor configuration that will be useful in the design of future versions of this sensor.

  2. Proceedings of the Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants

    International Nuclear Information System (INIS)

    1999-01-01

    The problems of creation and operation of nuclear materials (NM) control and accounting systems and their components at radiochemical plants were discussed in seminar during November 2-6 of 1998. There were 63 Russian and 25 foreign participants in seminar. The seminar programme includes following sessions and articles: the aspects of State NM control and accountancy; NM control and accounting in radiochemical plants and at separate stages of reprocessing of spent nuclear fuel and irradiated fuel elements of commercial reactors; NM control and accountancy in storage facilities of radiochemical plants; NM control and accounting computerization, material balance assessment, preparation of reports; qualitative and quantitative measurements in NM control and accounting at radiochemical plants destructive analysis techniques [ru

  3. Automated radiochemical synthesis and biodistribution of [11C]l-α-acetylmethadol ([11C]LAAM)

    International Nuclear Information System (INIS)

    Sai, Kiran Kumar Solingapuram; Fan, Jinda; Tu, Zhude; Zerkel, Patrick; Mach, Robert H.; Kharasch, Evan D.

    2014-01-01

    Long-acting opioid agonists methadone and l-α-acetylmethadol (LAAM) prevent withdrawal in opioid-dependent persons. Attempts to synthesize [ 11 C]-methadone for PET evaluation of brain disposition were unsuccessful. Owing, however, to structural and pharmacologic similarities, we aimed to develop [ 11 C]LAAM as a PET ligand to probe the brain exposure of long-lasting opioids in humans. This manuscript describes [ 11 C]LAAM synthesis and its biodistribution in mice. The radiochemical synthetic strategy afforded high radiochemical yield, purity and specific activity, thereby making the synthesis adaptable to automated modules. - Highlights: • Radiochemical synthesis of opioid [ 11 C]l-α-acetylmethadol (LAAM) described for the first time. • High radiochemical yield, purity and specific activity. • Easily reproducible and adaptable synthesis to any C-11 automated modules. • [ 11 C]LAAM utility as a PET radiopharmaceutical for assessing brain penetration

  4. Investigations of radiochemical methods for the platinum group metals for NAA

    International Nuclear Information System (INIS)

    Tredoux, M.

    A radiochemical procedure for the determination of the platinum group metals and gold is outlined in this report. The sample is irradiated, treated with acids and passed through anion-exchange columns before being determined by gamma spectrometry

  5. Radiochemical and biological control of metaiodobenzyl-guanidine (MIBG) labeled with 131I

    International Nuclear Information System (INIS)

    Barboza, M.R.F.F. de; Muramoto, E.; Colturato, M.T.; Silva Valente Goncalves, R. da; Pereira, N.P.S. de; Almeida, M.A.T.M. de; Silva, C.P.G. da.

    1988-07-01

    This study shows the standardization of the radiochemical control of MIBG - 131 I in eletrophoretic system and also the biological control in Wistar rat for a period of time, not longer than 60 minutes after tracer administration. (author) [pt

  6. The use of radiochemical analysis for detecting biotracers of food radioactive contamination in Cherkasy Region

    International Nuclear Information System (INIS)

    Matvyijenko, D.G.

    2003-01-01

    Stable biotracers of radioactive contamination according to the findings of analytical control of the foodstuffs was determined. The use of radiochemical analysis for determining the activity of the foodstuffs and water (Sr-90, Cs-137) was evaluated

  7. Laboratory simulated slipstream testing of novel sulfur removal processes for gasification application

    International Nuclear Information System (INIS)

    Schmidt, Roland; Tsang, Albert; Cross, Joe; Summers, Clinton; Kornosky, Bob

    2008-01-01

    The Wabash River Integrated Methanol and Power Production from Clean Coal Technologies (IMPPCCT) project is investigating an Early Entrance Coproduction Plant (EECP) concept to evaluate integrated electrical power generation and methanol production from coal and other carbonaceous feedstocks. Research, development and testing (RD and T) that is currently being conducted under the project is evaluating cost effective process systems for removing contaminants, particularly sulfur species, from the generated gas which contains mainly synthesis gas (syngas), CO 2 and steam at concentrations acceptable for the methanol synthesis catalyst. The RD and T includes laboratory testing followed by bench-scale and field testing at the SG Solutions Gasification Plant located in West Terre Haute, Indiana. Actual synthesis gas produced by the plant was utilized at system pressure and temperature for bench-scale field testing. ConocoPhillips Company (COP) developed a sulfur removal technology based on a novel, regenerable sorbent - S Zorb trademark - to remove sulfur contaminants from gasoline at high temperatures. The sorbent was evaluated for its sulfur removal performance from the generated syngas especially in the presence of other components such as water and CO 2 which often cause sorbent performance to decline over time. This publication also evaluates the performance of a regenerable activated carbon system developed by Nucon International, Inc. in polishing industrial gas stream by removing sulfur species to parts-per-billion (ppb) levels. (author)

  8. Impact of lean six sigma process improvement methodology on cardiac catheterization laboratory efficiency.

    Science.gov (United States)

    Agarwal, Shikhar; Gallo, Justin J; Parashar, Akhil; Agarwal, Kanika K; Ellis, Stephen G; Khot, Umesh N; Spooner, Robin; Murat Tuzcu, Emin; Kapadia, Samir R

    2016-03-01

    Operational inefficiencies are ubiquitous in several healthcare processes. To improve the operational efficiency of our catheterization laboratory (Cath Lab), we implemented a lean six sigma process improvement initiative, starting in June 2010. We aimed to study the impact of lean six sigma implementation on improving the efficiency and the patient throughput in our Cath Lab. All elective and urgent cardiac catheterization procedures including diagnostic coronary angiography, percutaneous coronary interventions, structural interventions and peripheral interventions performed between June 2009 and December 2012 were included in the study. Performance metrics utilized for analysis included turn-time, physician downtime, on-time patient arrival, on-time physician arrival, on-time start and manual sheath-pulls inside the Cath Lab. After implementation of lean six sigma in the Cath Lab, we observed a significant improvement in turn-time, physician downtime, on-time patient arrival, on-time physician arrival, on-time start as well as sheath-pulls inside the Cath Lab. The percentage of cases with optimal turn-time increased from 43.6% in 2009 to 56.6% in 2012 (p-trendprocess improvement initiative, lean six sigma, on improving and sustaining efficiency of our Cath Lab operation. After the successful implementation of this continuous quality improvement initiative, there was a significant improvement in the selected performance metrics namely turn-time, physician downtime, on-time patient arrival, on-time physician arrival, on-time start as well as sheath-pulls inside the Cath Lab. Copyright © 2016 Elsevier Inc. All rights reserved.

  9. Long core model apparatus for laboratory investigation of oil recovery processes

    Energy Technology Data Exchange (ETDEWEB)

    Milley, Gy; Bukta, B; Jonap, K; Lovei, J; Wagner, O

    1982-01-01

    In studying the secondary and Tertiary processes of intensifying oil output, an analysis was made of the following main factors: behavior of multiple-phase and multiple-component system in the porous medium, their stability, mobility, effect of viscosity and pressure differential in the system, configuration of the displacement front, influence of chemical additives on optimizing the surface energy, economic characteristics of the processes. All of these factors can be studied on a laboratory unit with core samples up to 120 cm long with temperatures to 120/sup 0/C, pressures to 30 MPa and consumption of reagents to 100 cm/sup 3//h. The unit contains feed vessels of high pressure for water, oil and gas in different reagents. There is a pumping unit of two-stage type, and in the first loop there is a piston pump which feeds the cylinder of the pump of the second stage of the plunger type. The outlet stage of this pump through the valve system is connected to the corresponding vessel for pressing the necessary reagent through the core sample. One can continually change the pressure to 100 MPa. The core is placed in a special core carrier and using special high temperature resins, it is packed in it in order to exclude side overflows. There is a technology of packing of comparatively soft rocks (clay). Sketches are presented of the sealing assemblies, and also the plans for inserting cables for the sensors. The sensor system is arranged over the entire length of the core and generates signals which are proportional to the magnitude of water saturation. The outlet of the core carrier has devices for resetting pressure, collecting filtrate, measurement of its composition and consumption. The core carrier is thermostatically controlled and contains two kW electrical heater for taking measurements at different temperatures. With a change in the system modes, the equilibrium is reached in 2-3 h.

  10. Determination of thorium in native gold by radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Liu, Y.; Kraehenbuehl, U.

    1995-01-01

    Thorium concentrations in 11 native gold samples from different sources, e.g. placer gold, vein and lode gold were determined. Thorium was determined by radiochemical separation and measurement of protactinium from irradiated native gold samples. The chemical yield of the separation procedures is 90%. Other elements were measured by gamma-ray spectroscopy. The radiochemical separation procedures described in this work make accurate determination of Th concentrations in native gold at picogram concentrations possible. (orig.)

  11. Current studies of biological materials using instrumental and radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Fardy, J.J.; McOrist, G.D.; Farrar, Y.J.

    1985-01-01

    Instrumental neutron activation analysis still remains the preferred option when analysing the trace element distribution in a wide rage of materials by neutron activation analysis. However, when lower limits of detection are required or major interferences reduce the effectiveness of this technique, radiochemical neutron activation analysis is applied. This paper examines the current use of both methods and the development of rapid radiochemical techniques for analysis of the biological materials, hair, cow's milk, human's milk, milk powder, blood and blood serum

  12. A comparison of the radiochemical stability of different iodine-131 labelled metaiodobenzylguanidine formulations for therapeutic use

    International Nuclear Information System (INIS)

    Wafelman, A.R.; Beijnen, J.H.; Hoefnagel, C.A.; Maes, R.A.A.

    1994-01-01

    The results of a stability study of three commercially available formulations of [ 131 I]MIBG for therapeutic use and an unstabilized formulation, stored under various conditions, are presented. The stability was followed for 20 days. In all formulations tested, free [ 131 I]iodide, formed by radiolysis, was the most important radiochemical impurity. The pharmaceutical formulation with the largest amount of stabilizer was radiochemically - but not chemically -most stable. (author)

  13. Implementation of advanced electrochemical oxidation for radiochemical concentrate treatment

    International Nuclear Information System (INIS)

    Velin, Anna; Bengtsson, Bernt; Lundblad, Magnus

    2012-09-01

    Water treatments in Nuclear Power Plants include ion exchange, evaporation and mechanical filtration techniques. These technologies are used to control the chemical release and to treat coolant in light water reactor types from chemicals and most importantly, from radioactive nuclides. Most of the conventional methods are efficient, but at the same time producing aqueous concentrates with high organic load. Before final storage, the level of organic content of those concentrates must be reduced. Advanced electrochemical oxidation with Boron Doped Diamond (BDD) electrodes are being investigated in laboratory- and pilot scale for treatment of dilute and concentrated aqueous waste streams at Vattenfall-Ringhals NPP. BDD anodes and cathodes are having high over potential against water electrolysis, and therefore well suitable for oxidation of organics. Dilute wastewater, such as laundry water, which has an initial COD level of around 500 mg/l, was reduced to a level of < 20 mg/l in the laboratory. Evaporator concentrates, with a TS content of 3% and pH of 7-8, were treated in pilot scale of 800 liters, working in batch operation mode, at temperatures between 25-50 deg. C. Initial COD levels between 2500 and 8000 mg/l in concentrate was reduced to < 100 mg/l at the first tests and later to < 300 mg/l. The advanced electrochemical oxidation is proven to be a promising technique for radioactive concentrate treatment. Long-term operation is still ongoing to evaluate the performance of the electrodes, cell components and overall process efficiency. (authors)

  14. Development and implementation of the Caribbean Laboratory Quality Management Systems Stepwise Improvement Process (LQMS-SIP) Towards Accreditation.

    Science.gov (United States)

    Alemnji, George; Edghill, Lisa; Guevara, Giselle; Wallace-Sankarsingh, Sacha; Albalak, Rachel; Cognat, Sebastien; Nkengasong, John; Gabastou, Jean-Marc

    2017-01-01

    Implementing quality management systems and accrediting laboratories in the Caribbean has been a challenge. We report the development of a stepwise process for quality systems improvement in the Caribbean Region. The Caribbean Laboratory Stakeholders met under a joint Pan American Health Organization/US Centers for Disease Control and Prevention initiative and developed a user-friendly framework called 'Laboratory Quality Management System - Stepwise Improvement Process (LQMS-SIP) Towards Accreditation' to support countries in strengthening laboratory services through a stepwise approach toward fulfilling the ISO 15189: 2012 requirements. This approach consists of a three-tiered framework. Tier 1 represents the minimum requirements corresponding to the mandatory criteria for obtaining a licence from the Ministry of Health of the participating country. The next two tiers are quality improvement milestones that are achieved through the implementation of specific quality management system requirements. Laboratories that meet the requirements of the three tiers will be encouraged to apply for accreditation. The Caribbean Regional Organisation for Standards and Quality hosts the LQMS-SIP Secretariat and will work with countries, including the Ministry of Health and stakeholders, including laboratory staff, to coordinate and implement LQMS-SIP activities. The Caribbean Public Health Agency will coordinate and advocate for the LQMS-SIP implementation. This article presents the Caribbean LQMS-SIP framework and describes how it will be implemented among various countries in the region to achieve quality improvement.

  15. Automation of process accountability flow diagrams at Los Alamos National Laboratory's Plutonium Facility

    International Nuclear Information System (INIS)

    Knepper, P.; Whiteson, R.; Strittmatter, R.; Mousseau, K.

    1999-01-01

    Many industrial processes (including reprocessing activities; nuclear fuel fabrication; and material storage, measurement and transfer) make use of process flow diagrams. These flows can be used for material accountancy and for data analysis. At Los Alamos National Laboratory (LANL), the Technical Area (TA)-55 Plutonium Facility is home to various research and development activities involving the use of special nuclear material (SNM). A facility conducting research and development (R and D) activities using SNM must satisfy material accountability guidelines. All processes involving SNM or tritium processing, at LANL, require a process accountability flow diagram (PAFD). At LANL a technique was developed to generate PAFDs that can be coupled to a relational database for use in material accountancy. These techniques could also be used for propagation of variance, measurement control, and inventory difference analysis. The PAFD is a graphical representation of the material flow during a specific process. PAFDs are currently stored as PowerPoint files. In the PowerPoint format, the data captured by the PAFD are not easily accessible. Converting the PAFDs to an accessible electronic format is desirable for several reasons. Any program will be able to access the data contained in the PAFD. For the PAFD data to be useful in applications such as an expert system for data checking, SNM accountability, inventory difference evaluation, measurement control, and other kinds of analysis, it is necessary to interface directly with the information contained within the PAFD. The PAFDs can be approved and distributed electronically, eliminating the paper copies of the PAFDs and ensuring that material handlers have the current PAFDs. Modifications to the PAFDs are often global. Storing the data in an accessible format would eliminate the need to manually update each of the PAFDs when a global change has occurred. The goal was to determine a software package that would store the

  16. Applications of neural networks to real-time data processing at the Environmental and Molecular Sciences Laboratory (EMSL)

    International Nuclear Information System (INIS)

    Keller, P.E.; Kouzes, R.T.; Kangas, L.J.

    1993-06-01

    Detailed design of the Environmental and Molecular Sciences Laboratory (EMSL) at the Pacific Northwest Laboratory (PNL) is nearing completion and construction is scheduled to begin later this year. This facility will assist in the environmental restoration and waste management mission at the Hanford Site. This paper identifies several real-time data processing applications within the EMSL where neural networks can potentially be beneficial. These applications include real-time sensor data acquisition and analysis, spectral analysis, process control, theoretical modeling, and data compression

  17. Soil transference patterns on bras: Image processing and laboratory dragging experiments.

    Science.gov (United States)

    Murray, Kathleen R; Fitzpatrick, Robert W; Bottrill, Ralph S; Berry, Ron; Kobus, Hilton

    2016-01-01

    In a recent Australian homicide, trace soil on the victim's clothing suggested she was initially attacked in her front yard and not the park where her body was buried. However the important issue that emerged during the trial was how soil was transferred to her clothing. This became the catalyst for designing a range of soil transference experiments (STEs) to study, recognise and classify soil patterns transferred onto fabric when a body is dragged across a soil surface. Soil deposits of interest in this murder were on the victim's bra and this paper reports the results of anthropogenic soil transfer to bra-cups and straps caused by dragging. Transfer patterns were recorded by digital photography and photomicroscopy. Eight soil transfer patterns on fabric, specific to dragging as the transfer method, appeared consistently throughout the STEs. The distinctive soil patterns were largely dependent on a wide range of soil features that were measured and identified for each soil tested using X-ray Diffraction and Non-Dispersive Infra-Red analysis. Digital photographs of soil transfer patterns on fabric were analysed using image processing software to provide a soil object-oriented classification of all soil objects with a diameter of 2 pixels and above transferred. Although soil transfer patterns were easily identifiable by naked-eye alone, image processing software provided objective numerical data to support this traditional (but subjective) interpretation. Image software soil colour analysis assigned a range of Munsell colours to identify and compare trace soil on fabric to other trace soil evidence from the same location; without requiring a spectrophotometer. Trace soil from the same location was identified by linking soils with similar dominant and sub-dominant Munsell colour peaks. Image processing numerical data on the quantity of soil transferred to fabric, enabled a relationship to be discovered between soil type, clay mineralogy (smectite), particle size and

  18. Implementation of the World Health Organization Regional Office for Africa Stepwise Laboratory Quality Improvement Process Towards Accreditation

    Directory of Open Access Journals (Sweden)

    Jean-Bosco Ndihokubwayo

    2016-05-01

    SLIPTA implementation process: WHO AFRO defined a governance structure with roles and responsibilities for six main stakeholders. Laboratories were evaluated by auditors trained and certified by the African Society for Laboratory Medicine. Laboratory performance was measured using the WHO AFRO SLIPTA scoring checklist and recognition certificates rated with 1–5 stars were issued. Preliminary results: By March 2015, 27 of the 47 (57% WHO AFRO member states had appointed a SLIPTA focal point and 14 Ministers of Health had endorsed SLIPTA as the desired programme for continuous quality improvement. Ninety-eight auditors from 17 African countries, competent in the Portuguese (3, French (12 and English (83 languages, were trained and certified. The mean score for the 159 laboratories audited between May 2013 and March 2015 was 69% (median 70%; SD 11.5; interquartile range 62–77. Of these audited laboratories, 70% achieved 55% compliance or higher (2 or more stars and 1% scored at least 95% (5 stars. The lowest scoring sections of the WHO AFRO SLIPTA checklist were sections 6 (Internal Audit and 10 (Corrective Action, which both had mean scores below 50%. Conclusion: The WHO AFRO SLIPTA is a process that countries with limited resources can adopt for effective implementation of quality management systems. Political commitment, ownership and investment in continuous quality improvement are integral components of the process.

  19. NC ISO/IEC1725:00 Accreditation process of CPHR main laboratories

    International Nuclear Information System (INIS)

    Marrero Garcia, Mariela; Molina perez, Daniel; Fernandez Gomez, Maria; Walwyn Salas, Gonzalo

    2003-01-01

    With the objective of offering technically qualified and competitive services one works in our laboratories under the requirements of a System of the Quality from 1993. In 1999 that was already with a draft of the new model ISO/IEC 17025:00 the steps they were given for the change of the Guide 25. At the moment with 3 laboratories accredited by the Cuban organ (ONARC), we are pioneer in these changes because alone a very reduced group of laboratories in the country has achieved it. The present work enunciates the antecedents of the change, the main non conformities during the evaluations for the accreditation and the obtained results

  20. Commissioning of calorimeter in radiochemical laboratory for non-destructive assay of special nuclear materials

    International Nuclear Information System (INIS)

    Patra, S.; Mhatre, A.M.; Agarwal, C.; Chaudhury, S.; Pujari, P.K.

    2017-01-01

    Accounting of special nuclear materials (SNM) in every stages of nuclear fuel cycle is a necessity where one needs the quantitative estimation of SNM in variety of samples like sealed containers or finished products without altering its physical and chemical form. Non-destructive assay (NDA) techniques are capable of assaying such samples by the way of measuring passive/active neutrons/gamma rays or by the measurement of decay heat. Radiochemistry Division has been actively involved in the development and deployment of various NDA methodologies for meeting the demand of nuclear material accounting as and when required. Recently a radiometric calorimeter, developed by Reactor Control Division, E and I Group, BARC, has been installed in Lab C-33, Radiochemistry Division

  1. Scientific achievements of the Institute of General Chemistry Radiochemical Laboratory during the 1972-1979 period

    International Nuclear Information System (INIS)

    Magas, S.; Kostanski, M.; Kasprzak, K.S.

    1980-01-01

    The results of experimental investigations in which radioisotopic tracers were employed to solve research problems of our Institute as well as other scientific and industrial institutions are briefly reported. (author)

  2. Phenolsulphotransferase in human tissue: radiochemical enzymatic assay and biochemical properties

    International Nuclear Information System (INIS)

    Anderson, R.J.; Weinshilboum, R.M.

    1980-01-01

    Phenolsulphotransferase (EC 2.8.2.1) (PST) is an important catecholamine and drug metabolizing enzyme. Optimal conditions have been determined for the accurate measurement of PST activity in the human platelet, human renal cortex, and human jejunum with a radiochemical microassay. 3-Methoxy-4-hydroxyphenylglycol (MHPG) and 35 S-3'-phosphoadenosine-5'-phosphosulfate ( 35 S-PAPS) were the substrates for the reaction. The apparent Michaelis-Menten (Ksub(m)) values for MHPG with platelet, renal cortex, and jejunum were 1.09, 0.46 and 1.16 mmol/l, respectively. Apparent Ksub(m) values for PAPS in the same tissues were 0.14, 0.13 and 0.21 μmol/l. The pH optimum of the reacton in all three tissues was approximately 6.2-6.8 with three different buffer systems. The coefficients of variation for the assay of platelet, renal cortex, and jejunal activities were 6.2%, 3.4% and 4.4%, respectively. Mean platelet PST activity in blood samples from 75 randomly selected adult subjects was 5.0 +- 1.72 mmol of MHPG sulfate formed per hour per mg of platelet protein (8.3 X 10 -5 +- 2.9 X 10 -5 μmol min -1 mg -1 , mean +- S.D.). There was a 5-fold intersubject variation in platelet PST activity within two standard deviations of the mean value. Experiments in which partially purified human erythrocyte PST was added to platelet, kidney and gut homogenates under these assay conditions provided evidence that endogenous PST inhibitors did not affect the observed enzyme activity. (Auth.)

  3. Implementation of the World Health Organization Regional Office for Africa Stepwise Laboratory Quality Improvement Process Towards Accreditation.

    Science.gov (United States)

    Ndihokubwayo, Jean-Bosco; Maruta, Talkmore; Ndlovu, Nqobile; Moyo, Sikhulile; Yahaya, Ali Ahmed; Coulibaly, Sheick Oumar; Kasolo, Francis; Turgeon, David; Abrol, Angelii P

    2016-01-01

    The increase in disease burden has continued to weigh upon health systems in Africa. The role of the laboratory has become increasingly critical in the improvement of health for diagnosis, management and treatment of diseases. In response, the World Health Organization Regional Office for Africa (WHO AFRO) and its partners created the WHO AFRO Stepwise Laboratory (Quality) Improvement Process Towards Accreditation (SLIPTA) program. WHO AFRO defined a governance structure with roles and responsibilities for six main stakeholders. Laboratories were evaluated by auditors trained and certified by the African Society for Laboratory Medicine. Laboratory performance was measured using the WHO AFRO SLIPTA scoring checklist and recognition certificates rated with 1-5 stars were issued. By March 2015, 27 of the 47 (57%) WHO AFRO member states had appointed a SLIPTA focal point and 14 Ministers of Health had endorsed SLIPTA as the desired programme for continuous quality improvement. Ninety-eight auditors from 17 African countries, competent in the Portuguese (3), French (12) and English (83) languages, were trained and certified. The mean score for the 159 laboratories audited between May 2013 and March 2015 was 69% (median 70%; SD 11.5; interquartile range 62-77). Of these audited laboratories, 70% achieved 55% compliance or higher (2 or more stars) and 1% scored at least 95% (5 stars). The lowest scoring sections of the WHO AFRO SLIPTA checklist were sections 6 (Internal Audit) and 10 (Corrective Action), which both had mean scores below 50%. The WHO AFRO SLIPTA is a process that countries with limited resources can adopt for effective implementation of quality management systems. Political commitment, ownership and investment in continuous quality improvement are integral components of the process.

  4. Progress on radiochemical analysis for nuclear waste management in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Hou, X. (Technical Univ. of Denmark. Center for Nuclear Technologies (NuTech), Roskilde (Denmark))

    2012-01-15

    This report summarized the progress in the development and improvement of radioanalytical methods for decommissioning and waste management completed in the NKS-B RadWaste 2011 project. Based on the overview information of the analytical methods in Nordic laboratories and requirement from the nuclear industry provided in the first phase of the RadWaste project (2010), some methods were improved and developed. A method for efficiently separation of Nb from nuclear waste especially metals for measurement of long-lived 94Nb by gamma spectrometry was developed. By systematic investigation of behaviours of technetium in sample treatment and chromatographic separation process, an effective method was developed for the determination of low level 99Tc in waste samples. An AMS approachment was investigated to measure ultra low level 237Np using 242Pu for AMS normalization, the preliminary results show a high potential of this method. Some progress on characterization of waste for decommissioning of Danish DR3 is also presented. (Author)

  5. Progress on radiochemical analysis for nuclear waste management in decommissioning

    International Nuclear Information System (INIS)

    Hou, X.

    2012-01-01

    This report summarized the progress in the development and improvement of radioanalytical methods for decommissioning and waste management completed in the NKS-B RadWaste 2011 project. Based on the overview information of the analytical methods in Nordic laboratories and requirement from the nuclear industry provided in the first phase of the RadWaste project (2010), some methods were improved and developed. A method for efficiently separation of Nb from nuclear waste especially metals for measurement of long-lived 94Nb by gamma spectrometry was developed. By systematic investigation of behaviours of technetium in sample treatment and chromatographic separation process, an effective method was developed for the determination of low level 99Tc in waste samples. An AMS approachment was investigated to measure ultra low level 237Np using 242Pu for AMS normalization, the preliminary results show a high potential of this method. Some progress on characterization of waste for decommissioning of Danish DR3 is also presented. (Author)

  6. On the presence of fictitious solar neutrino flux variations in radiochemical experiments

    International Nuclear Information System (INIS)

    Vladimirskii, B.M.; Bruns, A.V.

    2004-01-01

    The currently available data on solar neutrino flux variation in radiochemical experiments and Cherenkov measurements have so far defied a simple interpretation. Some of the results concerning these variations are indicative of their relationship to processes on the solar surface. It may well be that a poorly understood, uncontrollable factor correlating with solar activity indices affects the neutrino flux measurements. This factor is assumed to modulate the detection efficiency on different detectors in different ways. To test this assumption, we have analyzed all available radiochemical measurements obtained with the Brookhaven (1970-1994, 108 runs), GALLEX (1991-1997, 65 runs), and SAGE (1989-2000, 80 runs) detectors for possible instability of the detection efficiency. We consider the heliophysical situation at the final stage of the run, the last 7-27 days, when the products of the neutrino reaction with the target material had already been accumulated. All of the main results obtained previously by other authors were found to be reproduced for chlorine-argon measurements. The neutrino flux anticorrelates with the sunspot numbers only for an odd solar cycle. A similar behavior is observed for the critical frequencies of the E-ionosphere. The neutrino flux probably correlates with the A p magnetic activity index only for an even solar cycle. The predominance of a certain sign of the radial interplanetary magnetic field (IMF) in the last 14 (or 7) days of the run has the strongest effect on the recorded neutrino flux. The effect changes sign when the polarity of the general solar magnetic field is reversed and is most pronounced for the shortest runs (less than 50 days). The dependence of the flux on IMF polarity completely disappears if the corresponding index is taken for the first rather than the last days of the run. The IMF effect on the recorded neutrino flux was also found for short runs in the gallium-germanium experiment, but this effect for a given

  7. Investigation of Chemical and Radiochemical Fingerprints of Water Resources in Siwa Oasis, Western Desert, Egypt

    International Nuclear Information System (INIS)

    El-Sayed, S.A.; Allam, Kh.A.; Salama, M.H.; El Begawy, H.

    2017-01-01

    Water resources in Siwa oasis, Egypt; included the Nubian sandstone aquifer system (NSSAS), Tertiary carbonate aquifer system (TCAS) as well as springs and lakes. Existing chemical and radiochemical fingerprints of these resources in the central and western parts of the oasis were examined based on the analyses of 30 water samples collected in 2015. In each sample, the analyzed chemical and radioisotopic constituents were Cl"-, SO_4"2"- , CO_3"2"-, HCO"3 "-, Na"+, K"+, Ca"2"+ and Mg"2"+, Al, B, Ba, Cd, Co, Fe, Cu, Mn, Mo, Ni, Pb, Sr, V, Zn, Si and Cr, "2"2"6 Ra, "2"3"2Th and "4"0K. Other physical properties included ph and TDS were measured in the field. The chemical analysis was carried out following the ASTM methods, while the radiochemical measurements were done using a hyper pure germanium (HPGe) gamma ray spectrometry. Results of this work may be advantage ous to promote the hydrologic database in the oasis, where levels of the natural radioactivity in groundwater resources were established for the first time. Water resources were classified based on their contents of TDS into fresh water for the NSSAS, brackish to salty water for TCAS, brackish water for springs and brine water for lakes. The artesian water of the NSSAS and TCAS and water of the springs were alkaline, while the water of the lakes was acidic. Chemical characters of the ground water of the NSSAS reflected a little response to the processes of water-rock interactions, and the vice versa was observed for the groundwater of the TCAS. The ground water of the NSSAS was dominated by HCO"3"-Na genetic type characterizing the meteoric origin of water. The ground water of the TCAS was characterized by the presence of three genetic types of water (SO"4"-Na, Cl-Mg, and Cl-CA water), indicating the modification of the recharged water from the underlain NSSAS due to the effects of water sediment interactions and mixing with trapped ancient sea water. The chemical properties of spring water were, greatly

  8. Application of radiochemical methods for development of new biological preparation designed for soil bioremediation

    International Nuclear Information System (INIS)

    Kim, A.A.; Djuraeva, G.T.; Djumaniyazova, G.I.; Yadgarov, Kh.T.

    2006-01-01

    developed complex of radiochemical methods allowed to determine the PCB-destructive activity of bacteria at initial screening, selection and investigation of strains of soil bacteria. Stability of the positive influence of biological preparations is defined by behaviour of introduced population in soil and by status of soil microbial community. We found the good survival rate of bacteria of genus Bacillus (up to 10 8 -10 9 cells / g of soil) from biological preparation which has been introduced in contaminated by HCCH and PCBs soil in dynamics during one year. Besides the introduction of association of active bacteria strains-destructors of organochlorine compounds in contaminated soil makes the positive effect on development of soil microflora - stimulates the development of the useful (ammonifiers, oligonutophiles, nitrogen fixers and actinomyces) and suppresses development of a harmful microflora (micromycetes). We found that microbial processes in the soil contaminated by organochlorine compounds proceeded more intensively at addition of biofertilizer. Hence, biofertilizer appeared suitable organic substrate for stimulation of introduced and natural microflora of contaminated soil. Thus artificial enrichment (introduction) of contaminated soils by the microbial preparation designed on the basis of associations of bacteria - destructors of pesticides can be perspective and economic way of elimination of residual amounts of organochlorine pesticides in soil. Biofertilizer can be recommended as additional organic substrate for stimulation of introduced and natural microflora of contaminated soils. The combined application of bacterial preparation and biofertilizer can be recommended as most efficient way for biodegradation of organochlorine compounds. (author)

  9. "No one does this for fun": Contextualization and process writing in an organic chemistry laboratory course

    Science.gov (United States)

    Gay, Andrea

    This study investigated the introduction of curriculum innovations into an introductory organic chemistry laboratory course. Pre-existing experiments in a traditional course were re-written in a broader societal context. Additionally, a new laboratory notebook methodology was introduced, using the Decision/Explanation/Observation/Inference (DEOI) format that required students to explicitly describe the purpose of procedural steps and the meanings of observations. Experts in organic chemistry, science writing, and chemistry education examined the revised curriculum and deemed it appropriate. The revised curriculum was introduced into two sections of organic chemistry laboratory at Columbia University. Field notes were taken during the course, students and teaching assistants were interviewed, and completed student laboratory reports were examined to ascertain the impact of the innovations. The contextualizations were appreciated for making the course more interesting; for lending a sense of purpose to the study of chemistry; and for aiding in students' learning. Both experts and students described a preference for more extensive connections between the experiment content and the introduced context. Generally, students preferred the DEOI method to journal-style laboratory reports believing it to be more efficient and more focused on thinking than stylistic formalities. The students claimed that the DEOI method aided their understanding of the experiments and helped scaffold their thinking, though some students thought that the method was over-structured and disliked the required pre-laboratory work. The method was used in two distinct manners; recursively writing and revising as intended and concept contemplation only after experiment completion. The recursive use may have been influenced by TA attitudes towards the revisions and seemed to engender a sense of preparedness. Students' engagement with the contextualizations and the DEOI method highlight the need for

  10. Radiochemical neutron activation analysis based multi-elemental analysis of high purity gallium

    International Nuclear Information System (INIS)

    Tashimova, F.A.; Sadikov, I.I; Salimov, M.I.; Zinov'ev, V.G.

    2006-01-01

    Full text: Gallium is one of the widely used materials in semiconductor and optoelectronics industry. Gallium is used to produce infrared detectors, piezoelectric sensors, high- and low-temperature transistors for space and defense technology. One of the most important requirements for semiconductor materials of gallium compounds is an excessive high purity for layers and films. Information on impurities (type of an impurity, concentration, character of distribution) is important as for better understanding of the physical and chemical processes taking place in formed semiconductor structures and for the 'know-how' of devices on their basis. The object of this work is to develop radiochemical neutron activation technique for analysis of high purity gallium. Irradiation of 0.1 g of gallium sample in neutron flux of 5·10 13 cm -2 s -1 for 5 hours will result in induced activity of more than 10 8 Bq, due to 72 Ga radionuclide, half-life of which is 14.1 hours. Therefore to perform instrumental NAA of gallium long period (10 day) cooling is required, and high sensitive determination of elements producing short- and long-lived radionuclides (T 1/2 72 Ga. We have studied the behavior of gallium in extraction-chromatographic system 'TBP-HCl'. The experiments have shown that higher factor of distribution (D) and capacity on gallium can be achieved when 'TBP-4M HCl' system is used. However more than 10 trace elements have high D and thus they cannot be separated from 72 Ga. To resolve the problem and increase the number of separated trace elements we have used preliminary satisfaction of chromatographic column with tellurium, which has D higher than the most of elements in 'TBP-4M HCl' system and thus suppresses extraction of elements. Distribution profile of gallium along the column and elution curve of 25 trace elements have been measured. Chemical yields of separated elements measured by using radiotracers are more than 93%. On the basis of the carried out researches

  11. Radiochemical studies on the separation of iodine-131 and radioiodination of some organic compounds

    International Nuclear Information System (INIS)

    Mohamed, M.A.I.

    2010-01-01

    its retardation factor (R f ). The second technique is the purification of the labeled compounds by means of high pressure liquid chromatography (HPLC). On the reverse phase RP-18, column eluted with an appropriate solvent where each compound is identified by its retention time (R t ).Chapter III :It deals with the idea of separation of iodine-131 from tellurium targets using the dry distillation method. The factors affecting the production and separation of 131 I were studied such as the oven temperature; the distillation time and the sodium hydroxide concentration, the following flow sheet summarizes the production process. The quality control tests were carried out on the final product (Na 131 I). They were 99.9%, 98.7% for radionuclidic purity and radiochemical purity, respectively and the chemical purity of Te in the final radioiodine was 0.8μg/ml.

  12. AUTOMATED PROCESS MONITORING: APPLYING PROVEN AUTOMATION TECHNIQUES TO INTERNATIONAL SAFEGUARDS NEEDS

    International Nuclear Information System (INIS)

    O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Devol, Timothy A.; Egorov, Oleg; Clements, John P.

    2008-01-01

    Identification and quantification of specific alpha- and beta-emitting radionuclides in complex liquid matrices is highly challenging, and is typically accomplished through laborious wet chemical sample preparation and separations followed by analysis using a variety of detection methodologies (e.g., liquid scintillation, gas proportional counting, alpha energy analysis, mass spectrometry). Analytical results may take days or weeks to report. Chains of custody and sample security measures may also complicate or slow the analytical process. When an industrial process-scale plant requires the monitoring of specific radionuclides as an indication of the composition of its feed stream or of plant performance, radiochemical measurements must be fast, accurate, and reliable. Scientists at Pacific Northwest National Laboratory have assembled a fully automated prototype Process Monitor instrument capable of a variety of tasks: automated sampling directly from a feed stream, sample digestion/analyte redox adjustment, chemical separations, radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results could be immediately transmitted to on- or off-site locations. The development of a rapid radiochemical Process Monitor for 99Tc in Hanford tank waste processing streams, capable of performing several measurements per hour, will be discussed in detail. More recently, the automated platform was modified to perform measurements of 90Sr in Hanford tank waste stimulant. The system exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs

  13. Results of laboratory and in-situ measurements for the description of coupled thermo-hydro-mechanical processes in clays

    Energy Technology Data Exchange (ETDEWEB)

    Goebel, Ingeborg; Alheid, Hans-Joachim [BGR Hannover, Stilleweg 2, D-30655 Hannover (Germany); Jockwer, Norbert [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Theodor-Heuss-Str. 4, 38122 Braunschweig (Germany); Mayor, Juan Carlos [ENRESA, Emilio Vargas 7, E-Madrid (Spain); Garcia-Sineriz, Jose Luis [AITEMIN, c/ Alenza, 1 - 28003 Madrid (Spain); Alonso, Eduardo [International Center for Numerical Methods in Engineering, CIMNE, Edificio C-1, Campus Norte UPC, C/Gran Capitan, s/n, 08034 Barcelona (Spain); Weber, Hans Peter [NAGRA, Hardstrasse 73, CH-5430 Wettingen (Switzerland); Ploetze, Michael [ETHZ, Eidgenoessische Technische Hochschule Zuerich, ETH Zentrum, HG Raemistrasse 101, CH-8092 Zuerich (Switzerland); Klubertanz, Georg [COLENCO Power Engineering Ltd, CPE, Taefern Str. 26, 5405 Baden-Daettwil (Switzerland); Ammon, Christian [Rothpletz, Lienhard, Cie AG, Schifflaendestrasse 35, 5001 Aarau (Switzerland)

    2004-07-01

    The Heater Experiment at the Mont Terri Underground Laboratory aims at producing a validated model of thermo-hydro-mechanically (THM) coupled processes. The experiment consists of an engineered barrier system where in a vertical borehole, a heater is embedded in bentonite blocks, surrounded by the host rock, Opalinus Clay. The experimental programme comprises permanent monitoring before, during, and after the heating phase, complemented by geotechnical, hydraulic, and seismic in-situ measurements as well as laboratory analyses of mineralogical and rock mechanics properties. After the heating, the experiment was dismantled for further investigations. Major results of the experimental findings are outlined. (authors)

  14. FORTRAN computer programs to process Savannah River Laboratory hydrogeochemical and stream-sediment reconnaissance data

    International Nuclear Information System (INIS)

    Zinkl, R.J.; Shettel, D.L. Jr.; D'Andrea, R.F. Jr.

    1980-03-01

    FORTRAN computer programs have been written to read, edit, and reformat the hydrogeochemical and stream-sediment reconnaissance data produced by Savannah River Laboratory for the National Uranium Resource Evaluation program. The data are presorted by Savannah River Laboratory into stream sediment, ground water, and stream water for each 1 0 x 2 0 quadrangle. Extraneous information is eliminated, and missing analyses are assigned a specific value (-99999.0). Negative analyses are below the detection limit; the absolute value of a negative analysis is assumed to be the detection limit

  15. Validity limits of fuel rod performance calculations from radiochemical data at operating LWRs

    International Nuclear Information System (INIS)

    Zaenker, H.; Nebel, D.

    1986-01-01

    There are various calculational models for the assessment of the fuel rod performance on the basis of the activities of gaseous and volatile fission products in the reactor coolant. The most important condition for the applicability of the calculational models is that a steady state release of the fission products into the reactor coolant takes place. It is well known that the models are not applicable during or shortly after reactor transients. The fact that 'unsteady states' caused by the fuel defection processes themselves can also occur in rare cases at steady reactor operation has not been taken into account so far. A test of validity is suggested with the aid of which the applicability of the calculational models can be checked in any concrete case, and the misleading of the reactor operators by gross misinterpretation of the radiochemical data can be avoided. The criteria of applicability are the fission product total activity, the slope tan α in the relationship lg (R/sub i//B/sub i/) proportional to lg lambda/sub i/ for the gaseous and volatile fission products, and the activity of the nonvolatile isotope 239 Np. (author)

  16. Application of radiochemical methods to investigate mercury in water-ecosystems

    International Nuclear Information System (INIS)

    Kraemer, H.J.

    1975-01-01

    Two topics have been picked out of the vast scope of possible questions on mercury ecology in this work: 1) Development for a method of enrichment of mercury from surface water and neutron activation analytical determination of the influence of dissolved Hg compounds on the water/fish part-process taking course in the water-ecosystem with the help of radiochemical tracer methods. The developed enrichment method, adsorbents on aniline sulphur resin basis, was applied to the activation analytical Hg determination in model solutions with a specified content as well as in water of the Rhine, where a Hg content of 1.1 +- 0.2 x 10 -3 ppm was determined. 2) The uptake (and yield) of Hg (NO 3 ) 2 and CH 3 HgCl from fish was traced using radioactive tracers Hg 197 and Hg 203. The measured accumulation and yield kinetics and observed influence due to additions enable the development of model to interpret the interaction between fish and dissolved Hg compounds. (RB) [de

  17. Automation of column-based radiochemical separations. A comparison of fluidic, robotic, and hybrid architectures

    Energy Technology Data Exchange (ETDEWEB)

    Grate, J.W.; O' Hara, M.J.; Farawila, A.F.; Ozanich, R.M.; Owsley, S.L. [Pacific Northwest National Laboratory, Richland, WA (United States)

    2011-07-01

    Two automated systems have been developed to perform column-based radiochemical separation procedures. These new systems are compared with past fluidic column separation architectures, with emphasis on using disposable components so that no sample contacts any surface that any other sample has contacted, and setting up samples and columns in parallel for subsequent automated processing. In the first new approach, a general purpose liquid handling robot has been modified and programmed to perform anion exchange separations using 2 mL bed columns in 6 mL plastic disposable column bodies. In the second new approach, a fluidic system has been developed to deliver clean reagents through disposable manual valves to six disposable columns, with a mechanized fraction collector that positions one of four rows of six vials below the columns. The samples are delivered to each column via a manual 3-port disposable valve from disposable syringes. This second approach, a hybrid of fluidic and mechanized components, is a simpler more efficient approach for performing anion exchange procedures for the recovery and purification of plutonium from samples. The automation architectures described can also be adapted to column-based extraction chromatography separations. (orig.)

  18. Radiochemical tools at the experimental lakes area (ELA) in Ontario, Canada

    International Nuclear Information System (INIS)

    Pfitzner, J.; Brunskill, G.

    1998-01-01

    Full text: For over 20 years, Canadian research scientists have used radiochemical tracers added to remote and pristine lakes to study physical, chemical, and biological processes that could not be easily quantified by other methods. Lakes have also been manipulated by experimentally altering the hydrological cycle, chemical composition, and species of fish in selected lakes, and using companion lakes as controls. Varying additions of organic carbon, N, and P have been done, and the exchange rate of carbon dioxide between the atmosphere and water was estimated using radon evasion rates from radium spikes in the lake water. Multinuclide spikes were done to follow the path of mine waste elements through the food chain and sediment accumulation. Lakes were experimentally acidified with HCl and HNO 3 and H 2 SO 4 to simulate acid rain, and to study natural buffering capacity of the hydrological cycle. Some of this research has been used to legislate pollution control in the St. Laurence Great Lakes and across Canada and USA. ELA research team spirit has survived several forest fires, bear attacks on the kitchen, massive cut-backs in funding and reduction in staff of Fisheries and Ocean Canada

  19. Contamination, decontamination and radiochemical safety analyses of the RA reactor (Report 1966)

    International Nuclear Information System (INIS)

    Maksimovic, Z.

    1966-12-01

    This contract is concerned with development of methods for detection of fission products i the heavy water and quantitative radiochemical analysis for detecting one fission product which enables reliable verification of heavy water contamination by fission products and estimation of contamination level. Qualitative and quantitative radiometry measurements of fission products in water are shown on page 4. Page 6 shows study of contamination and decontamination of water on the laboratory level. Experiments have shown that the majority of fission products was adsorbed on the uranium oxide and that the iodine isotopes are partly in water (non-adsorbed). Gamma spectrometry analyses showed 131 I moves to distillate with the initial quantities of distilled water. decontamination factors compared to the total activity of fission products in distillator and distillate are not higher than ∼10 3 . Decontamination of water contaminated by uranium oxide and fission products in the distillation device of the RA reactor is shown on page 8. Experiments demanded special preparation due to high activity of uranium (1.7 g of uranium irradiated in the reactor for 10 days at neutron flux 1.10 13 n.cm 2 /s. Prior preparations for transport and dissolution of irradiated metal uranium as well as sampling were needed. Distillation was done under lower pressure and temperature to avoid possible contamination of the environment bu fission products and iodine. Decontamination factors are shown in Table. Contamination and decontamination of stainless steel on the laboratory level are described on page 5. It was found that the deposition of activity on the stainless steel plates is inhomogeneous showing that the uranium oxide and fission products are deposited on the rough metal surfaces. According to literature data and our laboratory studies decontamination was done by nitric acid solution (2MHNO 3 ). Since the heavy water system of the RA reactor was made of stainless teel (except the

  20. Preliminary probe of quality indicators and quality specification in total testing process in 5753 laboratories in China.

    Science.gov (United States)

    Fei, Yang; Kang, Fengfeng; Wang, Wei; Zhao, Haijian; He, Falin; Zhong, Kun; Wang, Zhiguo; Chen, Wenxiang

    2016-08-01

    The aim of the study was to promote the establishment and implementation of quality indicators (QIs) in clinical laboratories, catch up with the state of art, and provide preliminary quality specifications for established QIs. Clinical laboratories from different provinces in China were included in this QIs survey in 2015. All participants were asked to collect data related to QIs and complete QIs questionnaires. Defect percentages and sigma values were calculated for each QI. The 25th percentile, median, and the 75th percentile of defect percentages and TATs were calculated as optimum, desirable and minimum quality specifications. While 25th, median, and 75th of sigma values were calculated as minimum, desirable and optimum quality specifications, respectively. Five thousand seven hundred and fifty-three clinical laboratories from 28 provinces in China participated in this survey. Median defect percentages of pre-examination QIs varied largely from 0.01% (incorrect sample container) to 0.57% (blood culture contamination) with sigma values varied from 4.0σ to 5.1σ. Median defect percentages of examination phase QIs were all really high. The most common problem in examination phase was test uncovered by inter-laboratory comparison (86.67%). Defect percentages of critical values notification and timely critical values notification were all 0.00% (6.0σ). While the median of defect percentages of incorrect laboratory reports was only 0.01% (5.4σ). Improvements are needed in all phases of total testing process (TTP) in laboratories in China, especially in examination phase. More attention should be paid when microbiology specimens are collected and results are reported. Quality specifications can provide directions for laboratories to make effort for.

  1. Comparison of different thin layer detection techniques to determine the radiochemical purity of radiopharmaceuticals

    International Nuclear Information System (INIS)

    Hammermaier, A.; Reich, E.; Boegl, W.

    1985-01-01

    Ten radiopharmaceuticals frequently used in clinical treatment were examined as to their radiochemical purity by paper and thin layer chromatography or electrophoresis, respectively. It is known that radiochemical impurities may result in an unnecessary exposure of the patients to be examined. Other than determining the radiochemical purity of several radiopharmaceuticals, a comparison of the different measuring methods of distributing activity on radiochromatograms or electropherograms is intended by this study. For this, the activity distribution in the developed radiochromatograms was assessed by four different measuring methods (TLC-linear analyzer, TLC-scanner with NaI(Tl) detector, TLC-scanner with gas flow counter and NaI(Tl) well-typ counter). As shown by the above analysis, only the TLC-linear analyzer and the NaI(Tl) well-typ counter (measurement of chromatograms or electropherograms cut into strips) are generally suitable methods for determining the radiochemical purity of radiochemicals, the TLC-scanner with gas flow counter is usable in most cases, while TLC-scanner with NaI(Tl) detector is yielding unsatisfactory results. (orig.) [de

  2. Development of Statistical Process Control Methodology for an Environmentally Compliant Surface Cleaning Process in a Bonding Laboratory

    Science.gov (United States)

    Hutchens, Dale E.; Doan, Patrick A.; Boothe, Richard E.

    1997-01-01

    Bonding labs at both MSFC and the northern Utah production plant prepare bond test specimens which simulate or witness the production of NASA's Reusable Solid Rocket Motor (RSRM). The current process for preparing the bonding surfaces employs 1,1,1-trichloroethane vapor degreasing, which simulates the current RSRM process. Government regulations (e.g., the 1990 Amendments to the Clean Air Act) have mandated a production phase-out of a number of ozone depleting compounds (ODC) including 1,1,1-trichloroethane. In order to comply with these regulations, the RSRM Program is qualifying a spray-in-air (SIA) precision cleaning process using Brulin 1990, an aqueous blend of surfactants. Accordingly, surface preparation prior to bonding process simulation test specimens must reflect the new production cleaning process. The Bonding Lab Statistical Process Control (SPC) program monitors the progress of the lab and its capabilities, as well as certifies the bonding technicians, by periodically preparing D6AC steel tensile adhesion panels with EA-91 3NA epoxy adhesive using a standardized process. SPC methods are then used to ensure the process is statistically in control, thus producing reliable data for bonding studies, and identify any problems which might develop. Since the specimen cleaning process is being changed, new SPC limits must be established. This report summarizes side-by-side testing of D6AC steel tensile adhesion witness panels and tapered double cantilevered beams (TDCBs) using both the current baseline vapor degreasing process and a lab-scale spray-in-air process. A Proceco 26 inches Typhoon dishwasher cleaned both tensile adhesion witness panels and TDCBs in a process which simulates the new production process. The tests were performed six times during 1995, subsequent statistical analysis of the data established new upper control limits (UCL) and lower control limits (LCL). The data also demonstrated that the new process was equivalent to the vapor

  3. Analytical methods for determination of radiochemical and radionuclidic purity of radiopharmaceuticals containing sup(99m)Tc and sup(113m)In. Part of a coordinated programme on radiopharmaceuticals

    International Nuclear Information System (INIS)

    Galatzeanu, I.

    1974-01-01

    The obtained results on radiochemical and radionuclidic purities determination of sup(99m)Tc and sup(113m)In-radiopharmaceuticals proved to be a good tool for small hospital units and laboratories in satisfying their duty to improve the quality control. The complicated behaviour of technetium in aqueous solutions during the preparation of radiopharmaceuticals, needs further research work to elucidate the mechanisms of interaction of reduced species with media and their disproportionation

  4. Using performance tasks employing IOM patient safety competencies to introduce quality improvement processes in medical laboratory science education.

    Science.gov (United States)

    Golemboski, Karen; Otto, Catherine N; Morris, Susan

    2013-01-01

    In order to contribute to improved healthcare quality through patient-centered care, laboratory professionals at all levels of practice must be able to recognize the connection between non-analytical factors and laboratory analysis, in the context of patient outcomes and quality improvement. These practices require qualities such as critical thinking (CT), teamwork skills, and familiarity with the quality improvement process, which will be essential for the development of evidence-based laboratory science practice. Performance tasks (PT) are an educational strategy which can be used to teach and assess CT and teamwork, while introducing Medical Laboratory Science (MLS) students at both baccalaureate and advanced-practice levels to the concepts of quality improvement processes and patient outcomes research. PT presents students with complex, realistic scenarios which require the incorporation of subject-specific knowledge with competencies such as effective team communication, patient-centered care, and successful use of information technology. A PT with assessment rubric was designed for use in a baccalaureate-level MLS program to teach and assess CT and teamwork competency. The results indicated that, even when students were able to integrate subject-specific knowledge in creative ways, their understanding of teamwork and quality improvement was limited. This indicates the need to intentionally teach skills such as collaboration and quality system design. PT represent one of many strategies that may be used in MLS education to develop essential professional competencies, encourage expert practice, and facilitate quality improvement.

  5. The Turnover Process at Chalk River Laboratories from Operations to Decommissioning

    International Nuclear Information System (INIS)

    Pottelberg, Paul; Tremblay, Roger

    2016-01-01

    Canadian Nuclear Laboratories (CNL) has 200 facilities that account for approximately 2 million square feet of building space. Currently there are 23 facilities undergoing various stages of Decommissioning. An additional 30 facilities are scheduled to be turned over to Decommissioning in 2016. CNL is currently restructuring to transition to a Government Owned/Contractor Operated (GoCo) organization and there will be a focus to accelerate the Decommissioning of legacy facilities on site. In the past, facilities were shutdown and left in various configurations with limited documentation or limited staff knowledge of the status of the facility at the start of Decommissioning. Recently, guidelines have been developed to ensure that any facility being turned over is put into a proper and documented safe shutdown configuration. This paper will look at CNL's process for turnover of facilities from Operations to Decommissioning and identify some of the key Lessons Learned. The turnover of nuclear facilities, administrative and support buildings, components or areas from Operations to Decommissioning needs to be documented and managed to ensure Health, Safety, Security and Environmental (HSSE) risks are identified, eliminated or effectively controlled. At CNL, the turnover document Table of Contents is: Introduction and Purpose; Facility Boundaries; Known Deficiencies; Facility Status; Shutdown Status; Hazards; System/Equipment; Drawings/Maps/Records; Significant Environmental Aspects (SEAs); Interface; and other Transfer Documentation. The transfer documentation specifically covers: - Defined boundaries of the facility, building, component or area at the time of turnover; - Identification of all deficiencies associated with the facility, building, component or area and the person, after turnover, who will be responsible for correcting them; - Confirmation of the status of the facility, building, component or area at the time of turnover with respect to: - The status

  6. Tracer studies of flotation in the laboratory and in mineral processing plant

    International Nuclear Information System (INIS)

    Niemi, A.J.; Thereska, J.; Plasari, E.; Kacaj, M.

    1993-01-01

    Radioisotope tracers have a proven application for the extraction of residence time distributions and the evaluation of flotation rates in industry. This paper shows how values of the rate factor k are scaled up on the basis of flotation in the laboratory and tracer tests in plant. The procedure is illustrated by a theoretical study and by experimental data. The information obtained can be introduced into models of larger flotation systems. (author)

  7. Method of determination of radiochemical purity of gallium-67 citrate injection

    International Nuclear Information System (INIS)

    Wang Quanji

    1985-01-01

    A simple method is used to compare the effect of five developing agents on the radiochemical purity of neutral products of 67 GaCit and on Rsub(f) values. Two preferable developing agents are recommended as suitable for the identification of 67 GaCit injection in its production. The effect of six pH values of different developing agents on radiochemical purity, Rsub(f) and chromatogram are compared for the neutral products. The results of the experiments show that the ascending paper chromatography with 1:2:4 pyridine/ethanol/water and 85:15 methanol/water is preferable for the determination of the radiochemical purity of 67 GaCit. The other developing agents also can be used if there are not any impurities except gallium radioisotopes

  8. Microfluidic cartridges for DNA purification and genotyping processed in standard laboratory instruments

    Science.gov (United States)

    Focke, Maximilian; Mark, Daniel; Stumpf, Fabian; Müller, Martina; Roth, Günter; Zengerle, Roland; von Stetten, Felix

    2011-06-01

    Two microfluidic cartridges intended for upgrading standard laboratory instruments with automated liquid handling capability by use of centrifugal forces are presented. The first microfluidic cartridge enables purification of DNA from human whole blood and is operated in a standard laboratory centrifuge. The second microfluidic catridge enables genotyping of pathogens by geometrically multiplexed real-time PCR. It is operated in a slightly modified off-the-shelf thermal cycler. Both solutions aim at smart and cost-efficient ways to automate work flows in laboratories. The DNA purification cartridge automates all liquid handling steps starting from a lysed blood sample to PCR ready DNA. The cartridge contains two manually crushable glass ampoules with liquid reagents. The DNA yield extracted from a 32 μl blood sample is 192 +/- 30 ng which corresponds to 53 +/- 8% of a reference extraction. The genotyping cartridge is applied to analyse isolates of the multi-resistant Staphyloccus aureus (MRSA) by real-time PCR. The wells contain pre-stored dry reagents such as primers and probes. Evaluation of the system with 44 genotyping assays showed a 100% specificity and agreement with the reference assays in standard tubes. The lower limit of detection was well below 10 copies of DNA per reaction.

  9. How do laboratory technicians perceive their role in the tuberculosis diagnostic process? A cross-sectional study among laboratory technicians in health centers of Central Java Province, Indonesia.

    Science.gov (United States)

    Widjanarko, Bagoes; Widyastari, Dyah Anantalia; Martini, Martini; Ginandjar, Praba

    2016-01-01

    Detection of acid-fast bacilli in respiratory specimens serves as an initial pulmonary tuberculosis (TB) diagnosis. Laboratories are the essential and fundamental part of all health systems. This study aimed to describe how laboratory technicians perceived their own self and work. This included perceived self-efficacy, perceived role, perceived equipment availability, perceived procedures, perceived reward and job, and perceived benefit of health education, as well as level of knowledge and attitudes related to work performance of laboratory technicians. This was a cross-sectional quantitative study involving 120 laboratory technicians conducted in Central Java. Interviews and observation were conducted to measure performance and work-related variables. Among 120 laboratory technicians, 43.3% showed fairly good performance. They complied with 50%-75% of all procedures, including sputum collection, laboratory tools utilization, sputum smearing, staining, smear examination, grading of results, and universal precaution practice. Perceived role, perceived self-efficacy, and knowledge of laboratory procedures were significantly correlated to performance, besides education and years of working as a laboratory technician. Perceived equipment availability was also significantly correlated to performance after the education variable was controlled. Most of the laboratory technicians believed that they have an important role in TB patients' treatment and should display proper self-efficacy in performing laboratory activities. The result may serve as a basic consideration to develop a policy for enhancing motivation of laboratory technicians in order to improve the TB control program.

  10. E-health, phase two: the imperative to integrate process automation with communication automation for large clinical reference laboratories.

    Science.gov (United States)

    White, L; Terner, C

    2001-01-01

    The initial efforts of e-health have fallen far short of expectations. They were buoyed by the hype and excitement of the Internet craze but limited by their lack of understanding of important market and environmental factors. E-health now recognizes that legacy systems and processes are important, that there is a technology adoption process that needs to be followed, and that demonstrable value drives adoption. Initial e-health transaction solutions have targeted mostly low-cost problems. These solutions invariably are difficult to integrate into existing systems, typically requiring manual interfacing to supported processes. This limitation in particular makes them unworkable for large volume providers. To meet the needs of these providers, e-health companies must rethink their approaches, appropriately applying technology to seamlessly integrate all steps into existing business functions. E-automation is a transaction technology that automates steps, integration of steps, and information communication demands, resulting in comprehensive automation of entire business functions. We applied e-automation to create a billing management solution for clinical reference laboratories. Large volume, onerous regulations, small margins, and only indirect access to patients challenge large laboratories' billing departments. Couple these problems with outmoded, largely manual systems and it becomes apparent why most laboratory billing departments are in crisis. Our approach has been to focus on the most significant and costly problems in billing: errors, compliance, and system maintenance and management. The core of the design relies on conditional processing, a "universal" communications interface, and ASP technologies. The result is comprehensive automation of all routine processes, driving out errors and costs. Additionally, compliance management and billing system support and management costs are dramatically reduced. The implications of e-automated processes can extend

  11. Radiolabeling, quality control and radiochemical purity assessment of 99mTc-HYNIC-TOC

    International Nuclear Information System (INIS)

    Melero, Laura T.U.H.; Araujo, Elaine B.; Mengatti, Jair

    2009-01-01

    Somatostatine receptors are widely expressed by several tumors, especially of the neuroendocrine origin. In vivo images of these tumors using radiolabeled somatostatine analogues became a useful clinical tool in oncology. The aim of this work was the radiolabeling of the somatostatine analogue HYNIC-TOC with 99mTc as well as the evaluation of the radiochemical stability and quality control of labeled complex. 99mTc-HYNIC-TOC was produced by labeling conditions using 20 μg of peptide, 20 mg of tricine and 10 mg of EDDA as coligands, 1110 MBq of 99mTc (99Mo-99mTc IPEN-TEC generator) and 15 μg of SnCl 2 .2H 2 O. The reaction proceeds for 10 minutes at boiling water bath. Radiochemical purity of labeled preparation was evaluated by different chromatographic systems: ITLC-SG in methanol:ammonium acetate (1:1); TLC-SG in sodium citrate buffer 0.1 N pH 5.0 and methylethylketone, and HPLC employing column C-18, 5 μm, 4.6 mm x 250 mm, UV (220 nm), radioactivity detectors, 1 mL/minute flow of acetonitrile and trifluoroacetic acid solution 0.1 %. Labeled compound has been found radiochemically stable for 5 hours and radiochemical purity was higher than 90 %. The thin layer chromatographic systems enabled the separation of radiochemical species presented in the labeled mixture as well as HPLC system. The labeling procedure studied resulted in high radiochemical yield and easy preparation. Future works include the preparation of a lyophilized reagent to make feasible the preparation of 99mTc-HYNIC-TOC at nuclear medicine services in order to study the clinical potential of the radiopharmaceutical in diagnostic and staging of neuroendocrine tumors. (author)

  12. Radiolabeling, quality control and radiochemical purity assessment of {sup 99m}Tc-HYNIC-TOC

    Energy Technology Data Exchange (ETDEWEB)

    Melero, Laura T.U.H.; Araujo, Elaine B.; Mengatti, Jair [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2009-07-01

    Somatostatine receptors are widely expressed by several tumors, especially of the neuroendocrine origin. In vivo images of these tumors using radiolabeled somatostatine analogues became a useful clinical tool in oncology. The aim of this work was the radiolabeling of the somatostatine analogue HYNIC-TOC with 99mTc as well as the evaluation of the radiochemical stability and quality control of labeled complex. 99mTc-HYNIC-TOC was produced by labeling conditions using 20 {mu}g of peptide, 20 mg of tricine and 10 mg of EDDA as coligands, 1110 MBq of 99mTc (99Mo-99mTc IPEN-TEC generator) and 15 {mu}g of SnCl{sub 2}.2H{sub 2}O. The reaction proceeds for 10 minutes at boiling water bath. Radiochemical purity of labeled preparation was evaluated by different chromatographic systems: ITLC-SG in methanol:ammonium acetate (1:1); TLC-SG in sodium citrate buffer 0.1 N pH 5.0 and methylethylketone, and HPLC employing column C-18, 5 {mu}m, 4.6 mm x 250 mm, UV (220 nm), radioactivity detectors, 1 mL/minute flow of acetonitrile and trifluoroacetic acid solution 0.1 %. Labeled compound has been found radiochemically stable for 5 hours and radiochemical purity was higher than 90 %. The thin layer chromatographic systems enabled the separation of radiochemical species presented in the labeled mixture as well as HPLC system. The labeling procedure studied resulted in high radiochemical yield and easy preparation. Future works include the preparation of a lyophilized reagent to make feasible the preparation of 99mTc-HYNIC-TOC at nuclear medicine services in order to study the clinical potential of the radiopharmaceutical in diagnostic and staging of neuroendocrine tumors. (author)

  13. Evaluation of the health effects of occupational exposure of analytic laboratory workers processing illicit drug investigation files.

    Science.gov (United States)

    Bentur, Y; Bentur, L; Rotenberg, M; Tepperberg, M; Leiba, R; Wolf, E Udi

    2013-05-01

    The Analytic Laboratory of Israel Police processes illicit drug files. In recent years, workers of this laboratory have complained of health problems. Limited information exists on the effect of occupational exposure to illicit drugs; biomonitoring was never done. To assess health effects and systemic absorption of illicit drugs in workers of the Analytic Laboratory occupationally exposed to illicit drugs. A prospective cohort study using health and occupational questionnaires, clinical assessments, and monitoring of urinary excretion of illicit drugs was conducted. The study included three blocks of one week each. At each week workers were assessed at the beginning (baseline), and the assessments were repeated at the end of the three working days. Urine specimens were analyzed for illicit drugs in an independent laboratory. Demographic, clinical, occupational, and laboratory data were subjected to descriptive analysis, and paired Student's t-test, chi-square analysis, and repeated measures model. Twenty-seven workers (age, 39.2 ± 8.3 years; 77.8% females) were included, yielding 122 paired samples. The following parameters were reduced at the end of shift compared with baseline: diastolic blood pressure (71.2 ± 11.2 and 77.2 ± 13.6 mmHg, respectively, p health complaints included headache, fatigue, and dry eyes. No illicit drug was detected in the urine specimens. It is suggested that the health concerns of the laboratory workers were not related to the absorption of illicit drugs; environmental conditions (e.g. inadequate ventilation and respirable dust) can contribute to these concerns.

  14. Use of reference materials for quality control of elemental analysis by neutron activation with radiochemical separation

    International Nuclear Information System (INIS)

    Woittiez, J.R.W.

    1990-01-01

    This paper describes the use of certified reference materials to monitor the long-term quality of radiochemical separations. The practical limitations which determine the actual design of the quality control are discussed. The hypothesis that the high yield of the radiochemical separation will be constant with time has been checked and validated for the elements Zn, Fe, Co, Cd, Mo and to a lesser extent for W and Th using NBS SRM 1577A, BCR CRM 274 and IAEA RM A-11. This validation could not be made for the elements Cr, Au, and Ag. Especially for Cr there is a serious lack of appropiate certified reference materials. (orig.)

  15. Radiochemical procedures for determination of selected members of the uranium and thorium series

    International Nuclear Information System (INIS)

    Smithson, G.L.

    1979-01-01

    The radiochemical procedures contained in this manual are adaptations of those developed and published by many radiochemists. In many cases the identity of the originator is not clear and usually modifications in the original procedure have been made by subsequent workers. Nearly all of the basic radiochemical techniques and separations in use today were developed during the Manhattan Project and can be found in U.S.A.E.C. reports published from 1945 to 1953. This manual contains methods for the determination of Pb-210, Po-210; Ra-226, Ra-228, Th-228, Th-230 and Th-232. (auth)

  16. Critical evaluation of the determination of zirconium and hafnium by instrumental and radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Burger, Mario; Kraehenbuehl, Urs

    1991-01-01

    Neutron activation analysis (instrument or radiochemical) is suitable for the determination of zirconium and hafnium in samples of geochemical origin only when sufficient attention is paid to inter-fering nuclides. The size of the necessary correction for INAA depends on the composition of the sample; this problem is discussed. The radio-chemical technique which is recommended involves separation of the samples, precipitations and anion-exchange separation. Results are given for various standard reference materials and for meteorites. (author). 12 refs.; 1 fig.; 9 tabs

  17. On the methodology of radiochemical neutron activation analysis of noble metals

    International Nuclear Information System (INIS)

    Chai, C.F.; Ma, S.L.; Mao, X.Y.; Liao, K.N.; Liu, W.C.

    1986-01-01

    Two different radiochemical procedures were developed: chelate ion resin exchange and amine solvent extraction. Two kinds of new Chinese chelate resins (NANKAI-3926 and BEI-5) and a new long-chain primary amine N 1923 were compared with Srafion NMRR and the tertiary amine N 235 in absorption performance of noble metals, respectively. Influences of various experimental conditions, e.g. sample digestion, acidity, equilibrium time, as well as elution of noble metals, on analytical sensitivity and chemical yield were discussed. Combining with neutron activation, the radiochemical separation procedures developed were used to determine the noble metal contents in the geological samples from Permina/Triassic boundary in South China. (author)

  18. Abyssal sediment erosion from the Central Indian Basin: Evidence from radiochemical and radiolarian studies

    Digital Repository Service at National Institute of Oceanography (India)

    Banakar, V.K.; Gupta, S.M.; Padmavati, V.K.

    ) 167-173 167 Elsevier Science Publishers B.V., Amsterdam Letter Section Abyssal sediment erosion in the Central Indian Basin: Evidence from radiochemical and radiolarian studies V.K. Banakar, S.M. Gupta and V.K. Padmavathi National Institute... of Oceanography, Dona-Paula, Goa-403 004, India (Revision accepted September 17, 1990) ABSTRACT Banakar, V.K., Gupta, S.M. and Padmavathi, V.K., 1991. Abyssal sediment erosion from the Central Indian Basin: Evi- dence from radiochemical and radiolarian studies...

  19. Use of ethyl-α-isonitrosoacetoacetate in the rapid estimation and radiochemical separation of gold

    International Nuclear Information System (INIS)

    Sawant, A.D.; Haldar, B.C.

    1978-01-01

    The use of ethyl-α-isonitrosoacetoacetate in the rapid estimation and radiochemical separation of gold is reported. As low as 5.00 mg of Au can be estimated with an accuracy better than 1%. Decontamination values against platinum metals and other metals usually associated with Au are greater than 10 5 . Isotopes and results are tabulated. The time required for radiochemical separation is around 20 min and the recovery of Au is better than 80%. γ-activities were measured with a single channel analyser and NaI(Tl) detector. β-activities were counted on a thin end-window type GM counter. (T.I.)

  20. Kit preparation of 153Sm-EDTMP and factors affecting radiochemical purity and stability

    International Nuclear Information System (INIS)

    Ferro-Flores, G.; Tendilla, J.I.; Lopez-Gomez, M.A.; Aguilar-Hernandez, F.; Gonzalez-Zavala, M.A.; Parades-Gutierrez, L.; Avila-Ramirez, E.

    1996-01-01

    A fast kit method was developed for the production of 153 Sm-EDTMP in two steps avoiding the use of nitric acid, evaporation and sterilization of the final solution by autoclave. Methods of analysis for the determination of chemical and radiochemical purity in the radiopharmaceutical solution were established. Factors affecting radiochemical purity and stability of the complex as the molar ratio of EDTMP/Sm, concentration of phosphate buffer and neutralization of EDTMP prior kit preparation were also analyzed. The use of this radiopharmaceutical in rabbits and patients showed selective skeletal uptake. (author). 5 refs., 4 figs., 3 tabs

  1. Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

    International Nuclear Information System (INIS)

    Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B.

    2017-01-01

    The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, 3 H, 14 C, 55 Fe, 59 Ni, 63 Ni, 90 Sr, 93 Zr, 94 Nb, 99 Tc, 129 I, 235 U, 238 U, 238 Pu, 239 + 240 Pu, 241 Pu, 242 Pu, 241 Am, 242 Cm e 243 + 244 Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

  2. Tests of an environmental and personnel safe cleaning process for Brookhaven National Laboratory accelerator and storage ring components

    International Nuclear Information System (INIS)

    Foerster, C.L.; Lanni, C.; Lee, R.; Mitchell, G.; Quade, W.

    1997-01-01

    A large measure of the successful operation of the National Synchrotron Light Source (NSLS) at Brookhaven National Laboratory (BNL) for over a decade can be attributed to the cleaning of its ultrahigh vacuum (UHV) components during and after construction. A new UHV cleaning process, which has to be environmentally and personnel safe, is needed to replace the harsh, unfriendly process which is still in use. Dow Advanced Cleaning Systems was contracted to develop a replacement process without the use of harsh chemicals and which must clean vacuum surfaces as well as the existing process. Acceptance of the replacement process was primarily based on photon stimulated desorption (PSD) measurements of beam tube samples run on NSLS beam line U10B. One meter long beam tube samples were fabricated from aluminum, 304 stainless steel, and oxygen-free copper. Initially, coupon samples were cleaned and passed preliminary testing for the proposed process. Next, beam tube samples of each material were cleaned, and the PSD measured on beam line U10B using white light with a critical energy of 487 eV. Prior to cleaning, the samples were contaminated with a mixture of cutting oils, lubricants, vacuum oils, and vacuum grease. The contaminated samples were then baked. Samples of each material were also cleaned with the existing process after the same preparation. Beam tube samples were exposed to between 10 22 and 10 23 photons per meter for a PSD measurement. Desorption yields for H 2 , CO, CO 2 , CH 4 , and H 2 O are reported for both the existing cleaning and for the replacement cleaning process. Preliminary data, residual gas scans, and PSD results are given and discussed. The new process is also compared with new cleaning methods developed in other laboratories. After modification, the new UHV cleaning process was accepted by BNL

  3. Validation experiment of a numerically processed millimeter-wave interferometer in a laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Kogi, Y., E-mail: kogi@fit.ac.jp; Higashi, T.; Matsukawa, S. [Department of Information Electronics, Fukuoka Institute of Technology, Fukuoka 811-0295 (Japan); Mase, A. [Art, Science and Technology Center for Cooperative Research, Kyushu University, Kasuga, Fukuoka 816-0811 (Japan); Kohagura, J.; Yoshikawa, M. [Plasma Research Center, University of Tsukuba, Tsukuba, Ibaraki 305-8577 (Japan); Nagayama, Y.; Kawahata, K. [National Institute for Fusion Science, Toki, Gifu 509-5202 (Japan); Kuwahara, D. [Tokyo University of Agriculture and Technology, Koganei, Tokyo 184-8588 (Japan)

    2014-11-15

    We propose a new interferometer system for density profile measurements. This system produces multiple measurement chords by a leaky-wave antenna driven by multiple frequency inputs. The proposed system was validated in laboratory evaluation experiments. We confirmed that the interferometer generates a clear image of a Teflon plate as well as the phase shift corresponding to the plate thickness. In another experiment, we confirmed that quasi-optical mirrors can produce multiple measurement chords; however, the finite spot size of the probe beam degrades the sharpness of the resulting image.

  4. Laboratory plant for the separation of cesium from waste solutions of the PUREX process

    International Nuclear Information System (INIS)

    Richter, M.; Eckert, B.; Riemenschneider, J.; Mallon, C.; Mann, D.

    1983-01-01

    A laboratory plant for the separation of cesium from a fission product waste solution of the fuel reprocessing is described. The plant consists of two stages. In the first stage cesium is adsorbed on ammonium molybdatophosphate (AMP). Then the adsorbent is dissolved. From the solution cesium is adsorbed on a cationic ion exchanger in the second stage. Then AMP can be reproduced from this solution. For the elution of cesium in the second stage a NH 4 NO 3 solution (3 m) is used. Flow sheet, construction and the control device of the plant are described and the results of tests with a model solution are given. (author)

  5. Radioactive wastes management in a radiochemistry laboratory

    International Nuclear Information System (INIS)

    Silva, Ana C.A.; Pereira, Wagner de S; Py Junior, Delcy de A.; Antunes, Ivan M.; Kelecom, Alphonse

    2009-01-01

    The Laboratorio de Monitoracao Ambiental (AMB) of the Unidade de Tratamento de Minerio (UTM) belonging to the Industrias Nucleares do Brasil is a chemical, radiochemical and radiometric laboratory, that analyses the natural radionuclides present in samples coming from the various installation of Industrias Nucleares do Brasil (INB). To minimize the radiological environmental impact, that laboratory has adopted a washing system of the chapel exhausting, that recirculate the washing water. These water can accumulate the radionuclides coming from the samples, that are liberated together the exhaustion gases from the chapels. Also, the water coming from the analyses and the sample releases (environmental and of the process) represent the liquid effluents of the AMB. The release of this effluent must pass by chemical and radiological criteria. From the radiological viewpoint, that release must be based on the Brazilian Nuclear Energy Commission (CNEN) regulations. This work try to establish the monitoring frequency, the radionuclides to be analysed, the form of liberation of those effluents, and the analytical techniques to be used. The radionuclides to be analysed will be U-nat, Ra-226 and Pb-210, of the uranium series, and the Th-232 and Ra-228, of the thorium series. The effluents must be monitored either before the release or, at least, twice a year. The effluents considered radioactive wastes, will be send to waste dam by the radioprotection service, or to the effluent treatment for controlled liberation for the environment

  6. Deep repository - Engineered barrier system. Erosion and sealing processes in tunnel backfill materials investigated in laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Sanden, Torbjoern; Boergesson, Lennart; Dueck, Ann; Goudarzi, Reza; Loennqvist, Margareta (Clay Technology AB, Lund (Sweden))

    2008-12-15

    SKB in Sweden and Posiva in Finland are developing and plan to implement similar disposal concepts for the final disposal of spent nuclear fuel. Co-operation and joint development work between Posiva and SKB with the overall objective to develop backfill concepts and techniques for sealing and closure of the repository have been going on for several years. The investigation described in this report is intended to acquire more knowledge regarding the behavior of some of the candidate backfilling materials. Blocks made of three different materials (Friedland clay, Asha 230 or a bentonite/ballast 30/70 mixture) as well as different bentonite pellets have been examined. The backfill materials will be exposed to an environment simulating that in a tunnel, with high relative humidity and water inflow from the rock. The processes and properties investigated are: 1. Erosion properties of blocks and pellets (Friedland blocks, MX-80 pellets, Cebogel QSE pellets, Minelco and Friedland granules). 2. Displacements of blocks after emplacement in a deposition drift (Blocks of Friedland, Asha 230 and Mixture 30/70). 3. The ability of these materials to seal a leaking in-situ cast plug cement/rock but also other fractures in the rock (MX-80 pellets). 4. The self healing ability after a piping scenario (Blocks of Friedland, Asha 230 Mixture 30/70 and also MX-80 pellets). 5. Swelling and cracking of the compacted backfill blocks caused by relative humidity. The erosion properties of Friedland blocks were also investigated in Phase 2 of the joint SKBPosiva project 'Backfilling and Closure of the Deep Repository, BACLO, which included laboratory scale experiments. In this phase of the project (3) some completing tests were performed with new blocks produced for different field tests. These blocks had a lower density than intended and this has an influence on the erosion properties measured. The erosion properties of MX-80 pellets were also investigated earlier in the project but

  7. How do laboratory technicians perceive their role in tuberculosis diagnostic process: a cross-sectional study among laboratory technicians in health centers of Central Java Province, Indonesia

    Directory of Open Access Journals (Sweden)

    Widjanarko B

    2016-09-01

    Full Text Available Bagoes Widjanarko,1 Dyah Anantalia Widyastari,2 Martini Martini,3 Praba Ginandjar3 1Department of Health Education and Behavior Sciences, Faculty of Public Health, Diponegoro University, Semarang, Indonesia; 2Institute for Population and Social Research, Mahidol University, Salaya, Thailand; 3Department of Epidemiology, Faculty of Public Health, Diponegoro University, Semarang, Indonesia Purpose: Detection of acid-fast bacilli in respiratory specimens serves as an initial pulmonary tuberculosis (TB diagnosis. Laboratories are the essential and fundamental part of all health systems. This study aimed to describe how laboratory technicians perceived their own self and work. This included perceived self-efficacy, perceived role, perceived equipment availability, perceived procedures, perceived reward and job, and perceived benefit of health education, as well as level of knowledge and attitudes related to work performance of laboratory technicians.Methods: This was a cross-sectional quantitative study involving 120 laboratory technicians conducted in Central Java. Interviews and observation were conducted to measure performance and work-related variables.Results: Among 120 laboratory technicians, 43.3% showed fairly good performance. They complied with 50%–75% of all procedures, including sputum collection, laboratory tools utilization, sputum smearing, staining, smear examination, grading of results, and universal precaution practice. Perceived role, perceived self-efficacy, and knowledge of laboratory procedures were significantly correlated to performance, besides education and years of working as a laboratory technician. Perceived equipment availability was also significantly correlated to performance after the education variable was controlled.Conclusion: Most of the laboratory technicians believed that they have an important role in TB patients’ treatment and should display proper self-efficacy in performing laboratory activities. The

  8. Chemical and Radiochemical Composition of Thermally Stabilized Plutonium Oxide from the Plutonium Finishing Plant Considered as Alternate Feedstock for the Mixed Oxide Fuel Fabrication Facility

    International Nuclear Information System (INIS)

    Tingey, Joel M.; Jones, Susan A.

    2005-01-01

    Eighteen plutonium oxide samples originating from the Plutonium Finishing Plant (PFP) on the Hanford Site were analyzed to provide additional data on the suitability of PFP thermally stabilized plutonium oxides and Rocky Flats oxides as alternate feedstock to the Mixed Oxide Fuel Fabrication Facility (MFFF). Radiochemical and chemical analyses were performed on fusions, acid leaches, and water leaches of these 18 samples. The results from these destructive analyses were compared with nondestructive analyses (NDA) performed at PFP and the acceptance criteria for the alternate feedstock. The plutonium oxide materials considered as alternate feedstock at Hanford originated from several different sources including Rocky Flats oxide, scrap from the Remote Mechanical C-Line (RMC) and the Plutonium Reclamation Facility (PRF), and materials from other plutonium conversion processes at Hanford. These materials were received at PFP as metals, oxides, and solutions. All of the material considered as alternate feedstock was converted to PuO2 and thermally stabilized by heating the PuO2 powder at 950 C in an oxidizing environment. The two samples from solutions were converted to PuO2 by precipitation with Mg(OH)2. The 18 plutonium oxide samples were grouped into four categories based on their origin. The Rocky Flats oxide was divided into two categories, low- and high-chloride Rocky Flats oxides. The other two categories were PRF/RMC scrap oxides, which included scrap from both process lines and oxides produced from solutions. The two solution samples came from samples that were being tested at Pacific Northwest National Laboratory because all of the plutonium oxide from solutions at PFP had already been processed and placed in 3013 containers. These samples originated at the PFP and are from plutonium nitrate product and double-pass filtrate solutions after they had been thermally stabilized. The other 16 samples originated from thermal stabilization batches before canning at

  9. Fundamental processes in the expansion, energization, and coupling of single- and multi-Ion plasmas in space: Laboratory simulation experiments

    Science.gov (United States)

    Szuszczewicz, E. P.; Bateman, T. T.

    1996-01-01

    We have conducted a laboratory investigation into the physics of plasma expansions and their associated energization processes. We studied single- and multi-ion plasma processes in self-expansions, and included light and heavy ions and heavy/light mixtures to encompass the phenomenological regimes of the solar and polar winds and the AMPTE and CRRES chemical release programs. The laboratory experiments provided spatially-distributed time-dependent measurements of total plasma density, temperature, and density fluctuation power spectra with the data confirming the long-theorized electron energization process in an expanding cloud - a result that was impossible to determine in spaceborne experiments (as e.g., in the CRRES program). These results provided the missing link in previous laboratory and spaceborne programs. confirming important elements in our understanding of such solar-terrestrial processes as manifested in expanding plasmas in the solar wind (e.g., CMES) and in ionospheric outflow in plasmaspheric fluctuate refilling after a storm. The energization signatures were seen in an entire series of runs that varied the ion species (Ar', Xe', Kr' and Ne'), and correlative studies included spectral analyses of electrostatic waves collocated with the energized electron distributions. In all cases wave energies were most intense during the times in which the suprathermal populations were present, with wave intensity increasing with the intensity of the suprathermal electron population. This is consistent with theoretical expectations wherein the energization process is directly attributable to wave particle interactions. No resonance conditions were observed, in an overall framework in which the general wave characteristics were broadband with power decreasing with increasing frequency.

  10. Application of radiochemical neutron activation and atomic absorption spectrometry methods for the study of nutrition-pollution interactions in children

    Energy Technology Data Exchange (ETDEWEB)

    Tran Bang Diep [Institute for Nuclear Science and Technique, VAEC, P.O. Box 5T-160, Hanoi (Viet Nam)]. E-mail: tranfbangdiepj@yahoo.com; Tran Dai Nghiep [Institute for Nuclear Science and Technique, VAEC, P.O. Box 5T-160, Hanoi (Viet Nam)]. E-mail: tdnghiep@vaec.gov.vn

    2005-07-01

    The application of radiochemical neutron activation analysis (RNAA) and atomic absorption spectrometry (AAS) is expected to aid in understanding and evaluating the effects of environmental pollution on the nutritional status of children already exposed to marginal malnutrition. Samples of placenta, of low-weight and control newborns groups, were collected for determination of nutritional elements and pollutants. The mean ratios of pollutants and nutrients such as Cd/Zn, Hg/Se and Pb/Ca were evaluated for both groups. All these ratios in the placenta of the low-weight newborns are higher than that of the healthy group. The degree of the nutrient-pollutant interaction is evaluated by quantity R, with mercury considered as the most active pollutant while calcium the most active nutrient among the involved elements in process of the interaction. (author)

  11. Application of radiochemical neutron activation and atomic absorption spectrometry methods for the study of nutrition-pollution interactions in children

    International Nuclear Information System (INIS)

    Tran Bang Diep; Tran Dai Nghiep

    2005-01-01

    The application of radiochemical neutron activation analysis (RNAA) and atomic absorption spectrometry (AAS) is expected to aid in understanding and evaluating the effects of environmental pollution on the nutritional status of children already exposed to marginal malnutrition. Samples of placenta, of low-weight and control newborns groups, were collected for determination of nutritional elements and pollutants. The mean ratios of pollutants and nutrients such as Cd/Zn, Hg/Se and Pb/Ca were evaluated for both groups. All these ratios in the placenta of the low-weight newborns are higher than that of the healthy group. The degree of the nutrient-pollutant interaction is evaluated by quantity R, with mercury considered as the most active pollutant while calcium the most active nutrient among the involved elements in process of the interaction. (author)

  12. Development of a radiochemical neutron activation analysis procedure for determination of rhenium in biological and environmental samples at ultratrace level

    International Nuclear Information System (INIS)

    Kucera, J.; Lucanikova, M.; Czech Technical Univ., Prague

    2006-01-01

    Radiochemical neutron activation procedures using liquid-liquid extraction with tetraphenylarsonium chloride in chloroform from 1M HCl and solid extraction with ALIQUAT 336 incorporated in a polyacrylonitrile binding matrix from 0.1M HCl were developed for accurate determination of rhenium in biological and environmental samples at the sub-ng x g -1 level. Concentrations of Re in the range of 0.1 to 2.4 ng x g -1 were determined in several botanical reference materials (RM), while in a RM of road dust a value of ∼ 10 ng x g -1 was found. Significantly elevated values of Re, up to 90 ng x g -1 were found in seaweed (brown algae). Results for Re in the brown algae Fucus vesiculosus in which elevated 99 Tc values had previously been determined suggested possible competition between Re and Tc in the accumulation process. (author)

  13. Radiochemical synthesis of a carbon-supported Pt–SnO2 bicomponent nanostructure exhibiting enhanced catalysis of ethanol oxidation

    International Nuclear Information System (INIS)

    Okazaki, Tomohisa; Seino, Satoshi; Nakagawa, Takashi; Kugai, Junichiro; Ohkubo, Yuji; Akita, Tomoki; Nitani, Hiroaki; Yamamoto, Takao A.

    2015-01-01

    Carbon-supported Pt–SnO 2 electrocatalysts with various Sn/Pt molar ratios were prepared by an electron beam irradiation method. These catalysts were composed of metallic Pt particles approximately 5 nm in diameter together with low crystalline SnO 2 . The contact between the Pt and SnO 2 in these materials varied with the amount of dissolved oxygen in the precursor solutions and it was determined that intimate contact between the Pt and SnO 2 significantly enhanced the catalytic activity of these materials during the ethanol oxidation reaction. The mechanism by which the contact varies is discussed based on the radiochemical reduction process. - Highlights: • Ethanol oxidation catalysis was enhanced by Sn-addition, far less than ever reported. • Pt–SnO 2 contact is crucial to the catalysis enhancement, alloying of Sn is not necessary. • Nano-scaled intimate contact between Pt and SnO 2 was directly observed

  14. The laboratory-type data input and processing subsystem of the country-wide environmental radiation monitoring system in Hungary

    International Nuclear Information System (INIS)

    Kanyar, B.; Fulop, N.; Glavatszkih, N.; Nemeth, A.

    1996-01-01

    The countrywide radiation monitoring activity in Hungary is shared among the national networks as agriculture, environmental protection and public health ones. They are mostly involved in the environmental sampling and laboratory type determinations of the radioactive pollution, meanwhile the organisations mainly from the Army and Civil Defence are responsible to the early warning system. A moderately effective collaboration is established only around the Nuclear Power Plant Paks. Based on more than 10 years experience in collaboration around the NPP the Hungarian Atomic Energy Commission initiated some centralism in the countrywide monitoring activity as well. As the first step the National Research Institute for Radiobiology and Radiohygiene has been charged to establish an Information Center for laboratory-type data collection, processing, analysis and informing regularly the proper organizations on the results. The Information Centre is equipped with a computer type of SUN SPARCserver-20 and the laboratories are planned to be linked on line by PC stations. The main user programs for data collection, control and restricted processing are written in INGRES data manager software. The semiprocessed results can be transformed in a readable form for general statistical etc. packages

  15. Decreasing laboratory turnaround time and patient wait time by implementing process improvement methodologies in an outpatient oncology infusion unit.

    Science.gov (United States)

    Gjolaj, Lauren N; Gari, Gloria A; Olier-Pino, Angela I; Garcia, Juan D; Fernandez, Gustavo L

    2014-11-01

    Prolonged patient wait times in the outpatient oncology infusion unit indicated a need to streamline phlebotomy processes by using existing resources to decrease laboratory turnaround time and improve patient wait time. Using the DMAIC (define, measure, analyze, improve, control) method, a project to streamline phlebotomy processes within the outpatient oncology infusion unit in an academic Comprehensive Cancer Center known as the Comprehensive Treatment Unit (CTU) was completed. Laboratory turnaround time for patients who needed same-day lab and CTU services and wait time for all CTU patients was tracked for 9 weeks. During the pilot, the wait time from arrival to CTU to sitting in treatment area decreased by 17% for all patients treated in the CTU during the pilot. A total of 528 patients were seen at the CTU phlebotomy location, representing 16% of the total patients who received treatment in the CTU, with a mean turnaround time of 24 minutes compared with a baseline turnaround time of 51 minutes. Streamlining workflows and placing a phlebotomy station inside of the CTU decreased laboratory turnaround times by 53% for patients requiring same day lab and CTU services. The success of the pilot project prompted the team to make the station a permanent fixture. Copyright © 2014 by American Society of Clinical Oncology.

  16. Report on the Progress of Weld Development of Irradiated Materials at the Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Feng, Zhili [ORNL; Miller, Roger G. [ORNL; Chen, Jian [ORNL; Tang, Wei [ORNL; Clark, Scarlett R. [ORNL; Gibson, Brian T. [ORNL; Vance, Mark Christopher [ORNL; Frederick, Greg [Electric Power Research Institute (EPRI); Tatman, Jonathan K. [Electric Power Research Institute (EPRI); Sutton, Benjamin J. [Electric Power Research Institute (EPRI)

    2018-04-01

    This report summarizes recent welding activities on irradiated alloys in the advanced welding facility at the Radiochemical Engineering Development Center of Oak Ridge National Laboratory and the development of post-weld characterization capabilities and procedures that will be critical for assessing the ability of the advanced welding processes housed within the facility to make successful repairs on irradiated alloys. This facility and its capabilities were developed jointly by the U.S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program and the Electric Power Research Institute, Long Term Operations Program (and the Welding and Repair Technology Center), with additional support from Oak Ridge National Laboratory. The significant, on-going effort to weld irradiated alloys with high Helium concentrations and comprehensively analyze the results will eventually yield validated repair techniques and guidelines for use by the nuclear industry in extending the operational lifetimes of nuclear power plants.

  17. Three-dimensional FDEM numerical simulation of failure processes observed in Opalinus Clay laboratory samples

    Directory of Open Access Journals (Sweden)

    Omid Mahabadi

    2014-12-01

    Full Text Available This study presents the first step of a research project that aims at using a three-dimensional (3D hybrid finite-discrete element method (FDEM to investigate the development of an excavation damaged zone (EDZ around tunnels in a clay shale formation known as Opalinus Clay. The 3D FDEM was first calibrated against standard laboratory experiments, including Brazilian disc test and uniaxial compression test. The effect of increasing confining pressure on the mechanical response and fracture propagation of the rock was quantified under triaxial compression tests. Polyaxial (or true triaxial simulations highlighted the effect of the intermediate principal stress (σ2 on fracture directions in the model: as the intermediate principal stress increased, fractures tended to align in the direction parallel to the plane defined by the major and intermediate principal stresses. The peak strength was also shown to vary with changing σ2.

  18. Cation exchange process for recovery of plutonium from laboratory solutions containing chloride

    International Nuclear Information System (INIS)

    Gray, L.W.

    1978-10-01

    A cation exchange technique was developed for the separation of plutonium from laboratory solutions containing either Pu(III) or Pu(III)--Pu(IV) mixtures in acidic solutions containing chloride ions. The procedure consists of adjusting the acid concentration to less than one molar and adjusting the valence of the plutonium ion to the (III) state, if necessary. The adjusted solution is fed to a cation exchange column and washed with distilled water to remove residual chlorides from the column. Plutonium is then eluted from the column with 5M nitric acid containing 0.34M sulfamic acid. This procedure was used to separate plutonium from 1.2M chloride solution on a production-scale column. Typical plutonium recovery was 99.97%, while greater than 96% of the original chloride was rejected

  19. Virtual Earth System Laboratory (VESL): A Virtual Research Environment for The Visualization of Earth System Data and Process Simulations

    Science.gov (United States)

    Cheng, D. L. C.; Quinn, J. D.; Larour, E. Y.; Halkides, D. J.

    2017-12-01

    The Virtual Earth System Laboratory (VESL) is a Web application, under continued development at the Jet Propulsion Laboratory and UC Irvine, for the visualization of Earth System data and process simulations. As with any project of its size, we have encountered both successes and challenges during the course of development. Our principal point of success is the fact that VESL users can interact seamlessly with our earth science simulations within their own Web browser. Some of the challenges we have faced include retrofitting the VESL Web application to respond to touch gestures, reducing page load time (especially as the application has grown), and accounting for the differences between the various Web browsers and computing platforms.

  20. The Effect of a Laboratory Approach Based on Predict-Observation-Explain (POE Strategy on the Development of Students’ Science Process Skills and Views about Nature of Science

    Directory of Open Access Journals (Sweden)

    Kadir Bilen

    2012-06-01

    Full Text Available The purpose of this study was to investigate the effects of a laboratory instruction prepared based on “Predict-Observation-Explain” (POE strategy compared to a verification laboratory approach on the development of pre-service science teachers’ science skill processes and their views of nature of sceince in a general biology laboratory course. The participants of this study consisted of 122 pre-service teachers who took the General Biology Laboratory at the department of science education at Pamukkale University during the fall semester of 2007-2008 academic year. Data was collected through Science Process Skills Test (SPST and Nature of Science Questionnaire. Results indicated that there was a statistically significant difference between the verification laboratory approach and the laboratory approach based on the POE strategy on the development of students’ science process skills [F=10.41, p

  1. Oak Ridge National Laboratory Melton Valley Storage Tanks Waste filtration process evaluation

    International Nuclear Information System (INIS)

    Walker, B.W.; McCabe, D.J.

    1997-01-01

    The purpose of this filter study was to evaluate cross-flow filtration as effective solid-liquid separation technology for treating Oak Ridge National Laboratory wastes, outline operating conditions for equipment, examine the expected filter flow rates, and determine proper cleaning.The Gunite Tanks at the Oak Ridge National Laboratory contain heels which are a mixture of sludge, wash water, and bentonite clay. The tanks are to be cleaned out with a variety of flushing techniques and the dilute mixture transferred to another storage tank. One proposal is to transfer this mixture into existing Melton Valley Storage Tanks (MVST), which already contain a large amount of sludge and supernate. The mixed aqueous phase will then be transferred to new MVST, which are prohibited from containing insoluble solids. To separate the solid from the liquid and thereby prevent solids transfer into the new MVST, a technique is needed that can cleanly separate the sludge and bentonite clay from the supernate. One proposed method for solid liquid separation is cross-flow filtration. Cross-flow filtration has been used at the Savannah River and West Valley sites for treatment of tank waste, and is being tested for applicability at other sites. The performance of cross-flow filters with sludge has been tested, but the impact of sludge combined with bentonite clay has not. The objective of this test was to evaluate the feasibility of using cross-flow filters to perform the solid liquid separation required for the mixture of Gunite and MVST tank wastes

  2. A Monazite of Bangka Processing Laboratory Work is Undertaken to Recover Rare Earth Oxides for 1 kg/day Capacity

    International Nuclear Information System (INIS)

    Hafni-Lissa-Nuri; Faizal-Riza; Susilaningtyas; Sugeng-Waluyo; Erni-Rifandriyah-Arief

    2004-01-01

    This laboratory work is collaboration P2BGGN-BATAN and PT. Timah Tbk. to obtain monazite data process for use equipment calculation and economic pilot scales. A RE 2 O 3 can be treated to become an individual elements (Ce, Pr, Nd, Pm, Sm, Eu, etc.) and can be used as a raw materials in the industries of electronics, magnetics, ceramics, steels and glass optic etc. RE 2 O 3 which are gained from processing of 100 kg monazite with -325 mesh in size distribution and 1 kg/day capacity will be the sample for PT Timah marketing activity. The process is done with use equipments laboratory scale that were designed last year. The equipment processes are decomposition, dissolution, precipitation tank and calcinator. Total RE 2 O 3 production are 45 kg and total recovery RE 2 O 3 71,696 % ; Th 2,129 % ; U and P 2 O 5 0 %, Purify products RE 2 O 3 93,59 % and Th 1143 ppm. Based on the assessment of Chemex Inc Canada, the product of RE 2 O 3 contains are about >55,32 % RE 2 O 3 and 16 ppm Th. U and Th content within specification product of RE 2 O 3 depends to buyer/request. (author)

  3. Distribution of plutonium in organs of extrapulmonary pool in remote periods after the beginning of inhalation in workers of radiochemical plant

    International Nuclear Information System (INIS)

    Suslova, K.G.; Khokhryakov, V.F.; Tokarskaya, Z.B.; Kudryavtseva, T.I.; Nifatov, A.P.

    2000-01-01

    Influence of the health state and some dosimetric factors on the distribution of systemic Pu for workers of radiochemical plants is studied. Data were obtained on results of radiochemical analysis of soft tissue and bone samples taken at autopsy from 591 workers of the radiochemical plant. Alpha activity was measured with a low background alpha-radiometer. The patho-morphological state of the liver was taken into account. It is shown that the health state and the grade of the pathological process have an effect upon distribution of systemic Pu in humans. Skeleton to liver ratio is 50.3 : 42.3 = 1.2 for the practically healthy people. As the state of the health worsens and the pathology becomes more scenic, resulting in the fatty degeneration in the hepatocytes, the fractions of Pu deposition in liver decreases, while the fraction in the skeleton increases in the same degree. The individuals with serious liver diseases (cancer, massive metastases in the liver, cirrhosis, alcoholism) have got the ratio the skeleton : the liver = 77.9 : 14.9 = 5.5. The correlation between the state of the state of the health, some domestic factor and the distribution of systemic Pu was studied using the multifactorial regression analysis. These results indicated that Pu redistribution between the liver and the skeleton is the reciprocal process. Under pathological processes the element released from the liver is transported to the skeleton. The intensity of Pu translocation from the liver to the skeleton is higher under pathological processes (28 % for 1 - 2 years) than under the normal life conditions (1.4 % y -1 ). It should be assumed that for the persons with different heavy chronic diseases the skeleton and liver exposure doses may differ from the calculated ones, if the doses are evaluated from the models that do not take into account the plutonium recycling in systemic organs under the pathological processes [ru

  4. Single patient doses of {sup 99m}Tc-HDP: Assessment of radiochemical purity, sterility and extractables from a polypropylene syringe over six hours

    Energy Technology Data Exchange (ETDEWEB)

    Parkes, S.L.; Varelis, P. [St George Hospital, Kogarah, NSW (Australia). Department of Nuclear Medicine

    1997-12-01

    Full text: The purpose of this investigation was to determine the radiochemical purity (RCP), sterility and extractables for {sup 99m}Tc oxidronate ({sup 99m}Tc-HDP) stored in polypropylene syringes over < six-hour period. The radiochemical purity was determined using a two-strip ITLC procedure, performed at time 0, 1, 2, 4, 6 hours. The sterility and endotoxin levels were tested by a NATA accredited laboratory, after allowing the radiopharmaceutical to stand at room temperature for six hours in the syringes. Plasticisers and other likely compounds that could be extracted from the syringes into the aqueous solution were determined by high pressure liquid chromatography (HPLC) diode array detection. This analysis involved shaking normal saline in a syringe over night and then injecting an aliquot of this solution onto a C18 analytical column and monitoring the effluent at 200 and 253 nm. The radiochemical purity of {sup 99m}Tc-HDP did not significantly change over the course of the study and remained above the recommended RCP for this radiopharmaceutical. Furthermore, at six hours the RCP of {sup 99m}Tc-HDP stored in both the manufacturer`s vial and a syringe were identical. Sterility testing of {sup 99m}Tc-HDP stored in syringes showed no microbial growth and less than 10 endotoxin units/mL (pass). The HPLC analysis did not show the presence of any extraneous compounds in the aqueous solution. Single patient doses of {sup 99m}Tc-HDP stored in polypropylene syringes over a six-hour period fulfill all the quality control requirements for administration to humans.

  5. On the radiochemical purity of elementary 35S with high specific activity

    International Nuclear Information System (INIS)

    Todorovsky, D.S.; Kostadinov, K.N.; Efremova, Yu.N.

    1979-01-01

    Radiochemical composition and chemical changes with increasing storage time of benzene solutions and of solid species of elementary 35 S with high specific activity are studied. The dependence of the stability on the specific activity and the radioactive concentration is shown and some tentative limits are given for permissible storage periods. (author)

  6. Determination of the radiochemical purity of phosphorus-32 and tritium-labeled diisopropylphosphorofluoridate (DFP)

    International Nuclear Information System (INIS)

    Christopher, R.E.; Sheppard, G.

    1975-01-01

    A method is described for the determination of the radiochemical purity of labeled diisopropylphosphorofluoridate (DFP), based on the irreversible inhibition reaction with the enzyme α-chymotrypsin. The nature of the impurities in commercially available 32 P- and 3 H-labeled DFP is discussed

  7. Radiochemical assay for determination of dihydropyrimidinase activity using reversed-phase high-performance liquid chromatography

    NARCIS (Netherlands)

    van Kuilenburg, A. B.; van Lenthe, H.; van Gennip, A. H.

    1999-01-01

    A radiochemical assay was developed to measure the activity of dihydropyrimidinase (DHP) in human liver homogenates. The method is based on the separation of radiolabeled dihydrouracil from N-carbamyl-beta-alanine by HPLC with on-line detection of radioactivity combined with detection of 14CO2 by

  8. Rapid and sensitive enzymatic-radiochemical assay for the determination of triglycerides

    International Nuclear Information System (INIS)

    Khoo, J.C.; Miller, E.; Goldberg, D.I.

    1987-01-01

    An enzymatic-radiochemical method suitable for the determination of triglyceride levels of cells in culture is described. The method is based on the enzymatic hydrolysis of triglycerides to free fatty acids which then complex with 63 Ni. The method is rapid, accurate, and inexpensive. The procedure extends the sensitivity of triglyceride measurement to as low as 0.25 nanomoles

  9. Triphenyl phosphine oxide as a substoichiometric radiochemical reagent: Determination of thallium

    International Nuclear Information System (INIS)

    Reddy, P.C.; Polaiah, B.; Rangamannar, B.

    1991-01-01

    A rapid radiochemical method has been developed for the determination of microgram amounts of thallium based on the substoichiometric extraction of its ocmplex with triphenylphosphine oxide into benzene from 6 M sulphuric acid. 10-90 μg of thallium was determined with an average error of 2.06%. The effect of diverse metal ions on the extraction was studied. (orig.)

  10. Evaluation of radiochemical purities of some radiopharmaceuticals in Shiraz Namazi teaching hospital

    Directory of Open Access Journals (Sweden)

    Hossein Sadeghpour

    2015-03-01

    Full Text Available Many radiopharmaceuticals, as a special group of drugs, are eventually prepared at the nuclear medicine departments of the hospitals. Therefore, their quality control procedures such as sterility tests, radionuclide, radiochemical and chemical purity should be carried out in the hospitals. In this study, radiochemical purity for more than 300 preparations of three different radiopharmaceutical formulations from commercial kits were tested using instant thin layer chromatography. The formulations 99mTc-DTPA, 99mTc-MDP and 99mTc-MIBI were obtained from Pars Isotope Co. Several paper chromatographic systems including standard and factory recommended thin layer chromatography systems were used in this study. In addition different equipments for detection of radioactivity in paper chromatography like gamma camera and dose calibrator were used. The results showed that the most observed impurities were hydrolyzed reduced technetium (HR-Tc. There were no significant differences between calculated 99mTc-MIBI radiochemical purities when the radioactive detection device was gamma camera instead of dose calibrator. In case of 99mTc-DTPA and 99mTc-MDP, there were significant differences in detection of HR-Tc. On the contrary, no significant differences in free pertechnetate were observed when package insert procedures for quality control were used instead of those recommended in the references. Finally, we observed that the package insert procedures for quality control can offer higher radiochemical purities.

  11. Radiochemical separation and alpha-spectrometric determination of Americium in different matrixes

    International Nuclear Information System (INIS)

    Radenkovic, M.; Joksic, J.; Paligoric, D.

    2009-01-01

    A method of separation and alpha-spectrometric determination of americium, developed in VINCA Institute of Nuclear Sciences is described in the paper. The procedure is convenient to be used for 241 Am determination in environmental matrixes as well as samples of human origin if a very small concentrations are expected, using 243 Am as a tracer for radiochemical yield recovery. (author) [sr

  12. Application of radiochemical determination methods in cleanability research of building materials

    International Nuclear Information System (INIS)

    Maeaettae, Jenni; Kymaelaeinen, Hanna-Riitta; Sjoeberg, Anna-Maija

    2011-01-01

    During recent years increasing effort has been made to modify surface properties with easy-to-clean or self-cleaning characteristics, and concomitantly there is a need to be able to quantify cleanability. Methodology is a complex issue, including aspects of selection and characterization of the surface materials, the soiling materials (contaminants), soiling and cleaning methods, and the detection methods. Different biological, chemical, physical and visual methods have been included in studies of surface cleanability. One challenge has been to obtain quantitative information about soiling. The radiochemical methods, gamma spectrometry (NaI(Tl)-crystal) and liquid scintillation counting, have been shown to be suitable for evaluating cleanability of different surface materials and different soiling material types, providing quantitative information about the amount of soiling material both on and beneath the surface. Due to the different labelled soiling components, the interaction of the surface with different soiling material types can be evaluated. Radiochemical methods have unique benefits particularly for examining porous materials and surfaces. However, they are suitable only for highly controlled studies because of the hazards. Different features and details of radiochemical methods are discussed with the view to aid planning of future cleanability studies. - Highlights: → Radiochemical methods can be used for cleanability studies. → These methods give quantitative information about the amount of soiling material. → These methods are suitable particularly for examining porous materials. → These methods are suitable for highly controlled studies because of the hazards.

  13. The radiochemical purity of radiotracers as the criterion of their usefulness in investigations of hydrocarbons distillation

    International Nuclear Information System (INIS)

    Kolaczkowski, M.

    1976-01-01

    Among numerous analytic techniques of separation and analysis of radioactive products gas radiochromatography has proved to be particularly suitable. Organic bromides labelled with 82 Br-radionuclide are investigated. The analytic gas chromatographs equipped with appropriately constructed radiochromatographic attachments are used. The results of radiochemical purity determination of radiotracers are compared for various techniques. (author)

  14. Analytical and radiochemical methods in the stability study of the MIBI-Sm

    International Nuclear Information System (INIS)

    Isaac, M.; Leyva, R.; Gamboa, R.; Turino, D.

    1997-01-01

    99mT c-MIBI is a radiopharmaceutical imaging agent useful for assessing myocardial perfusion. This paper presents the stability results obtained in the radiochemical purity and others parameters in the quality control of 5 batch during more than 2 years

  15. Protein binding studies with radiolabeled compounds containing radiochemical impurities. Equilibrium dialysis versus dialysis rate determination

    DEFF Research Database (Denmark)

    Honoré, B

    1987-01-01

    The influence of radiochemical impurities in dialysis experiments with high-affinity ligands is investigated. Albumin binding of labeled decanoate (97% pure) is studied by two dialysis techniques. It is shown that equilibrium dialysis is very sensitive to the presence of impurities resulting...

  16. The Design-to-Analysis Process at Sandia National Laboratories Observations and Recommendations; TOPICAL

    International Nuclear Information System (INIS)

    BURNS, SHAWN P.; HARRISON, RANDY J.; DOBRANICH, DEAN

    2001-01-01

    The efficiency of the design-to-analysis process for translating solid-model-based design data to computational analysis model data plays a central role in the application of computational analysis to engineering design and certification. A review of the literature from within Sandia as well as from industry shows that the design-to-analysis process involves a number of complex organizational and technological issues. This study focuses on the design-to-analysis process from a business process standpoint and is intended to generate discussion regarding this important issue. Observations obtained from Sandia staff member and management interviews suggest that the current Sandia design-to-analysis process is not mature and that this cross-organizational issue requires committed high-level ownership. A key recommendation of the study is that additional resources should be provided to the computer aided design organizations to support design-to-analysis. A robust community of practice is also needed to continuously improve the design-to-analysis process and to provide a corporate perspective

  17. Preparing a laboratory for radioanalytical emergency response

    International Nuclear Information System (INIS)

    Bennett, J.; Webb, C.J.; Isch, S.

    2011-01-01

    As the state of the nation's ability to respond to a radiological event is examined, it has become apparent that both capacity and capability are lacking. Department of Homeland Security National Planning Scenario 11 is designed to address the planning activities for the response to an attack using radiological dispersal devices. The scenario details show that the cleanup activity will take several years, and that there will be between 360 000 and 1 000 000 environmental samples in the first year. Based on existing capacity and capabilities it would take four to six years to analyze the samples generated at the lower end of the sample range. The Environmental Protection Agency (EPA) has been given responsibility for the remediation activities following a radiological event, and has awarded cooperative agreements to several laboratories to start the process of developing capacity and capabilities. The Connecticut Department of Public Health Laboratory (DPHL) was awarded one of the cooperative agreements. The DPHL has started activities to further those goals by investigating and implementing procedures to ensure that samples with activity higher than normal background can be processed safely, as well as implementing more rapid methods for radiochemical analysis. The DPHL already served as the primacy radiochemistry laboratory for several New England states and thus had a solid foundation to build upon. The DPHL has taken a process flow approach in preparing for radiological emergency response and recommends that radioanalytical laboratories that are reviewing their roles in such a response: - Ensure that their Nuclear Regulatory Commission licenses allow for appropriate radioisotope types and activities; - Develop procedures and processes to ensure that samples with higher activities can be processed safely, with due regard for sample screening and aliquanting samples; - Provide for enhanced radioanalytical contamination control, with careful consideration of sample

  18. Laboratory investigation of nonlinear flow characteristics in rough fractures during shear process

    Science.gov (United States)

    Rong, Guan; Yang, Jie; Cheng, Long; Zhou, Chuangbing

    2016-10-01

    To understand the influence of shear behavior on the transporting properties of fluid through a single fracture, splitting fractures were made in the laboratory and shear flow tests were carried out under constant normal load conditions. The applied normal stress is in the range of 0.5-3.0 MPa. Before the physical test, the fracture's morphology is measured for identification of the roughness. At each shear step, we performed 5-8 high precise hydraulic tests with different hydraulic gradient. The relationship between pressure gradient and volume flow rate demonstrates to be nonlinear and fits very well with Forchheimer's and Izbash's laws. The linear and nonlinear coefficients in Forchheimer's law are quite sensitive to shear deformation (closure or dilation), experienced 1-2 and 1-3 orders of magnitude reduction during shear, respectively. An empirical equation is proposed to quantify the relationship between linear coefficient and nonlinear coefficient based on the experimental observations. The two coefficients in Izbash's law are quantified. The m value is in the range between 1.06 and 1.41 and the λ value experiences a reduction of 1-2 orders of magnitude during shear. In addition, the studied critical Reynolds number exhibits a decreasing and increasing variation corresponding to shear contraction and shear dilation of rock fracture. For all the cases in this study, the critical Reynolds number ranges between 1.5 and 13.0.

  19. Decommissioning of the MTR-605 process water building at the Idaho National Engineering Laboratory. Final report

    International Nuclear Information System (INIS)

    Browder, J.H.; Wills, E.L.

    1985-01-01

    Decontamination and decommissioning (D and D) of the unused radioactively contaminated portions of the MTR-605 building at the Test Reactor Area of the Idaho National Engineering Laboratory has been completed; this final report describes the D and D project. The building is a two-story concrete structure that was used to house piping systems to channel and control coolant water flow for the Materials Testing Reactor (MTR), a 40 MW (thermal) light water test reactor that was operated from 1952 until 1970 and then deactivated. D and D project objectives were to reduce potential environmental and radioactive contamination hazards to levels as low a reasonably achievable. Primary tasks of the D and D project were: to remove contaminated piping (about 400 linear ft of 36- and 30-in.-dia stainless steel pipe) and valves from the primary coolant pipe tunnels, to remove a primary coolant pump and piping, and to remove the three 8-ft-dia by 25-ft-long evaporators from the building second floor

  20. Evaluation of operating characteristics for a chabazite zeolite system for treatment of process wastewater at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Kent, T.E.; Perona, J.J.; Jennings, H.L.; Lucero, A.J.; Taylor, P.A.

    1998-02-01

    Laboratory and pilot-scale testing were performed for development and design of a chabazite zeolite ion-exchange system to replace existing treatment systems at the Process Waste Treatment Plant (PWTP) at Oak Ridge National Laboratory (ORNL). The process wastewater treatment systems at ORNL need upgrading to improve efficiency, reduce waste generation, and remove greater quantities of contaminants from the wastewater. Previous study indicated that replacement of the existing PWTP systems with an ion-exchange system using chabazite zeolite will satisfy these upgrade objectives. Pilot-scale testing of the zeolite system was performed using a commercially available ion-exchange system to evaluate physical operating characteristics and to validate smaller-scale column test results. Results of this test program indicate that (1) spent zeolite can be sluiced easily and completely from a commercially designed vessel, (2) clarification followed by granular anthracite prefilters is adequate pretreatment for the zeolite system, and (3) the length of the mass transfer zone was comparable with that obtained in smaller-scale column tests. Laboratory studies were performed to determine the loading capacity of the zeolite for selected heavy metals. These test results indicated fairly effective removal of silver, cadmium, copper, mercury, nickel, lead, and zinc from simple water solutions. Heavy-metals data collected during pilot-scale testing of actual wastewater indicated marginal removal of iron, copper, and zinc. Reduced effectiveness for other heavy metals during pilot testing can be attributed to the presence of interfering cations and the relatively short zeolite/wastewater contact time. Flocculating agents (polyelectrolytes) were tested for pretreatment of wastewater prior to the zeolite flow-through column system. Several commercially available polyelectrolytes were effective in flocculation and settling of suspended solids in process wastewater

  1. Photon-induced Processing of Interstellar Ices in the Laboratory. Focus on Their Non-thermal Desorption.

    Science.gov (United States)

    Martin-Domenech, Rafael; Munoz Caro, Guillermo; Cruz-Diaz, Gustavo A.; Oberg, Karin I.

    2018-06-01

    Some of the processes that take place in the interstellar medium (ISM)can be simulated in laboratories on Earth under astrophysically relevant conditions. For example, the energetic processing of the ice mantles that accrete on top of dust grains in the coldest regions of the ISM, leading to the production of new species and their desorption to the gas phase. In particular, observation of complex organic molecules (COMs) in cold interstellar environments stress the need for not only a solid state formation but also for non-thermal desorption mechanisms that can account for the observed abundances in regions where thermal desorption is inhibited. Laboratory Astrophysics can be used to test different non-thermal desorption processes and extract yields than can be extrapolated to the astrophysical scenario with theoretical models. 0th generation COMs like CH3OH and H2CO can be formed at very low temperatures. In this talk, we present laboratory simulations of the UV photoprocessing of a binary ice mixture composed by water (the main component of astrophysical ices) and methane. Formation of CO, CO2, CH3OH and H2CO was confirmed by IR spectroscopy and subsequent TPD. At the same time, photodesorption of CO and H2CO was detected by means of a Quadrupole Mass Spectrometer, with yields on the order of 10-4 and 10-5 molecules per incident photon, respectively. In general, photodesorption can take place through a direct mechanism, where the absorbing molecule (or its photofragments) are desorbed; or through an indirect mechanism where the absorbed energy is transferred to a surface molecule which is the one finally desorbing. In the case of photoproducts, the evolution of the photodesorption yield gives information on the photodesorption mechanism: a constant photodesorption yield is observed when the photoproducts are desorbed right after their formation; while an increasing yield is measured when the photoproducts are desorbed later after energy transfer from another

  2. The Application of the Human Engineering Modeling and Performance Laboratory for Space Vehicle Ground Processing Tasks at Kennedy Space Center

    Science.gov (United States)

    Woodbury, Sarah K.

    2008-01-01

    The introduction of United Space Alliance's Human Engineering Modeling and Performance Laboratory began in early 2007 in an attempt to address the problematic workspace design issues that the Space Shuttle has imposed on technicians performing maintenance and inspection operations. The Space Shuttle was not expected to require the extensive maintenance it undergoes between flights. As a result, extensive, costly resources have been expended on workarounds and modifications to accommodate ground processing personnel. Consideration of basic human factors principles for design of maintenance is essential during the design phase of future space vehicles, facilities, and equipment. Simulation will be needed to test and validate designs before implementation.

  3. Laboratory scale electroplating and processing of long lengths of an in situ Cu-Nb3Sn superconductors

    International Nuclear Information System (INIS)

    LeHuy, H.; Germain, L.; Roberge, R.; Foner, S.; Massachusetts Inst. of Tech., Cambridge

    1984-01-01

    A laboratory scale continuous tin electroplating system is described and used to evaluate the effect of various parameters of the alkaline and acid baths plating process. Tin electroplating is shown to be simple and reliable. With an 8 m immersion length production speeds of the order of 1 m min -1 are possible in an alkaline bath at 80degC. An acid bath gives satisfactory tinning deposits with a production speed of up to 3 m min -1 at room temperature. (author)

  4. Historic American Engineering Record, Idaho National Laboratory, Idaho Chemical Processing Plant, Fuel Reprocessing Complex

    Energy Technology Data Exchange (ETDEWEB)

    Susan Stacy; Julie Braun

    2006-12-01

    Just as automobiles need fuel to operate, so do nuclear reactors. When fossil fuels such as gasoline are burned to power an automobile, they are consumed immediately and nearly completely in the process. When the fuel is gone, energy production stops. Nuclear reactors are incapable of achieving this near complete burn-up because as the fuel (uranium) that powers them is burned through the process of nuclear fission, a variety of other elements are also created and become intimately associated with the uranium. Because they absorb neutrons, which energize the fission process, these accumulating fission products eventually poison the fuel by stopping the production of energy from it. The fission products may also damage the structural integrity of the fuel elements. Even though the uranium fuel is still present, sometimes in significant quantities, it is unburnable and will not power a reactor unless it is separated from the neutron-absorbing fission products by a method called fuel reprocessing. Construction of the Fuel Reprocessing Complex at the Chem Plant started in 1950 with the Bechtel Corporation serving as construction contractor and American Cyanamid Company as operating contractor. Although the Foster Wheeler Corporation assumed responsibility for the detailed working design of the overall plant, scientists at Oak Ridge designed all of the equipment that would be employed in the uranium separations process. After three years of construction activity and extensive testing, the plant was ready to handle its first load of irradiated fuel.

  5. Cadmium determination in biological samples using neutron activation analysis with radiochemical separations

    International Nuclear Information System (INIS)

    Munoz A, Luis; Gras R, Nuri

    2005-01-01

    Chile has 7500 km of coastline on the Southern Pacific ocean,with about 4500 km of continental coastline that contains a variety of different geographical zones.This variety means that there is a great diversity of marine resources such as fish, shellfish and seaweeds. The utilization of these resources has been increasing in recent years making this sector an economically important one. The catch as of May 2002 came to 1.9 million tons and exports of the different species amounted to US$611.5 million as of April.But this important economic resource is being threatened by the technical demands imposed by importing countries, mainly the specific requirements for sanitary certification for fishery export products, depending on the markets of destination. The chemical element cadmium is one of the most strictly controlled elements due some shellfish accumulate a large amount of this element and to its high toxicity. The Chilean standard's analytical procedures for cadmium determination in hydro biological products, which must be met by laboratories that certify and control these products for export, are now being evaluated. Through its Chemical Metrology Unit, the Chilean Nuclear Energy Commission is strongly supporting this sector by preparing the secondary reference or control materials, and it has developed and implemented nuclear analytical methods for the certification of these materials, which will be used mostly in collaborative studies. This work describes the methodology developed for the determination of cadmium in biological samples, particularly in shellfish and fish. The method is based on neutron activation analysis with radiochemical separations, using the radioisotopes 115 Cd and 115m In, generated in the samples by bombarding with neutrons in a nuclear reactor. The samples were digested at 110 o C with H 2 SO 4 and H 2 O 2 and then the radioactive cadmium element was separated from the other elements present in the samples using a Bio Rad AG 2-X8

  6. Specific features of kukersite processing in laboratory-scale and commercial retorts

    International Nuclear Information System (INIS)

    Yefimov, V.; Kundel, H.

    1991-01-01

    The yield and properties of shale oil produced by semi coking oil shale in retorts of different design depend to a great extent on the conditions of volatiles evacuation from the high temperature zone. In externally heated laboratory retorts, where oil vapours reside in the reaction zone for a relatively long period undergoing moderate cracking, no maximum oil yields are attained. The higher the organic matter content in the oil shale, the higher is the partial pressure of the oil vapours in the retort and hence the rate of their removal from the retorting zone, resulting in increased shale oil yields and lower specific yield of hydrogen in the retort off-gases. replacing the external heating mode with direct heating by a gaseous heat carrier (carbon dioxide, in particular) leads to a considerable moderation of the volatiles pyrolysis. As a result, the shale oil produced has a higher density and molecular mass, a lower calorific value and a higher content of phenols. The presence of water vapours in the heat carrier gas also has a positive effect upon the yield of shale oil and phenols. The properties of the oil and gas produced by semi coking kukersite in the presence of free calcium oxide are similar to those of cracked products. The presence of free calcium oxide has the same effect as higher temperatures or longer residence time of the volatiles in the retorting zone: it leads to reduced yields of shale oil and phenols, to a lower density of the oil and higher yields of hydrogen and gaseous hydrocarbons. This should be taken into consideration on evaluating the efficiency of semi coking oil shale in the retorts with solid heat carrier, which contains free calcium oxide

  7. Laboratory Studies of the Optical Properties and Condensation Processes of Cosmic Dust Particles

    Science.gov (United States)

    Abbas, Mian M.; Craven, Paul D.; Spann, James F.; Tankosic, Dragana; Six, N. Frank (Technical Monitor)

    2002-01-01

    A laboratory facility for levitating single isolated dust particles in an electrodynamics balance has been developing at NASA/Marshall Space Flight Center for conducting a variety of experimental, of astrophysical interest. The objective of this research is to employ this innovative experimental technique for studies of the physical and optical properties of the analogs of cosmic grains of 0.2-10 micron size in a chamber with controlled pressure/temperatures simulating astrophysical environments. In particular, we will carry out three classes of experiments to investigate the microphysics of the analogs of interstellar and interplanetary dust grains. (1) Charge characteristics of micron size single dust grains to determine the photoelectric efficiencies, yields, and equilibrium potentials when exposed to UV radiation. These measurements will provide the much-needed photoelectric emission data relating to individual particles as opposed to that for the bulk materials available so far. (2) Infrared optical properties of dust particles obtained by irradiating the particles with radiation from tunable infrared diode lasers and measuring the scattered radiation. Specifically, the complex refractive indices, the extinction coefficients, the scattering phase functions, and the polarization properties of single dust grains of interest in interstellar environments, in the 1-25 micron spectral region will be determined. (3) Condensation experiments to investigate the deposition of volatile gases on colder nucleated particles in dense interstellar clouds and lower planetary atmospheres. The increase in the mass or m/q ratio due to condensation on the particle will be monitored as a function of the dust particle temperature and the partial pressure of the injected volatile gas. The measured data wild permit determination of the sticking efficiencies of volatile gases of astrophysical interest. Preliminary results based on photoelectric emission experiments on 0.2-6.6 micron

  8. The remedial investigation/feasibility study process at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1993-01-01

    Martin Marietta Energy Systems, Inc. (Energy Systems), manages and operates the Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee, under a cost-plus-award-fee contract administered by the Department of Energy's (DOE) Oak Ridge Field office (Field Office). Energy Systems' environmental restoration program is responsible for eliminating or reducing to prescribed safe levels the risks to the environment or to human health and safety posed by inactive and surplus sites and facilities that have been contaminated with radioactive, hazardous, or mixed wastes. Energy Systems subcontracted to perform the remedial investigation and feasibility study (RI/FS) at ORNL. The objective of our audit was to determine if the RI/FS at ORNL had been implemented in a manner that ensured accomplishment of the goals and objectives of the DOE Environmental Restoration Program. The audit disclosed that the subcontractor did not fully meet its contractual requirements. Specifically, environmental data produced by the subcontractor is of questionable value for meeting its contractual requirement to provide data supporting permanent remedial action. This condition occurred because neither the subcontractor nor Energy Systems adequately implemented all essential management controls, and neither Energy Systems nor DOE provided adequate contract administration. As a result, DOE has received little value for its RI/FS expenditures. We have recommended that DOE determine the allowability of an estimated $45 million of subcontractor RI/FS cost at ORNL, plus the cost of Energy Systems administering the subcontract. Furthermore, DOE will continue to pay unnecessary costs and experience cost growth and project delays until effective project management controls are implemented

  9. Laboratory process control using natural language commands from a personal computer

    Science.gov (United States)

    Will, Herbert A.; Mackin, Michael A.

    1989-01-01

    PC software is described which provides flexible natural language process control capability with an IBM PC or compatible machine. Hardware requirements include the PC, and suitable hardware interfaces to all controlled devices. Software required includes the Microsoft Disk Operating System (MS-DOS) operating system, a PC-based FORTRAN-77 compiler, and user-written device drivers. Instructions for use of the software are given as well as a description of an application of the system.

  10. Laboratory Studies of the Optical Properties and Condensation Processes of Cosmic Dust Grains

    Science.gov (United States)

    Abbas, M. M.; Craven, P. D.; Spann, J. F.; Tankosic, D.; LeClair, A.; West, E.; Sheldon, R.; Witherow, W. K.; Gallagher, D. L.; Adrian, M. L.

    2002-01-01

    A laboratory facility for conducting a variety of experiments on single isolated dust particles of astrophysical interest levitated in an electrodynamics balance has been developed at NASA/Marshall Space Flight Center. The objective of the research is to employ this experimental technique for studies of the physical and optical properties of individual cosmic dust grains of 0.1-100 micron size in controlled pressure/temperatures environments simulating astrophysical conditions. The physical and optical properties of the analogs of interstellar and interplanetary dust grains of known composition and size distribution will be investigated by this facility. In particular, we will carry out three classes of experiments to study the micro-physics of cosmic dust grains. (1) Charge characteristics of micron size single dust grains to determine the photoelectric efficiencies, yields, and equilibrium potentials when exposed to UV radiation. (2) Infrared optical properties of dust particles (extinction coefficients and scattering phase functions) in the 1-30 micron region using infrared diode lasers and measuring the scattered radiation. (3) Condensation experiments to investigate the condensation of volatile gases on colder nucleated particles in dense interstellar clouds and lower planetary atmospheres. The condensation experiments will involve levitated nucleus dust grains of known composition and initial mass (or m/q ratio), cooled to a temperature and pressure (or scaled pressure) simulating the astrophysical conditions, and injection of a volatile gas at a higher temperature from a controlled port. The increase in the mass due to condensation on the particle will be monitored as a function of the dust particle temperature and the partial pressure of the injected volatile gas. The measured data will permit determination of the sticking coefficients of volatile gases and growth rates of dust particles of astrophysical interest. Some preliminary results based on

  11. RADCHEM 2005 - Radiochemical analysis in emergency and routine situations

    International Nuclear Information System (INIS)

    Sidhu, R.

    2006-04-01

    The report describes the work performed under the NKS-B project Radchem during 2005. RadChem-2005 has been focused towards laboratory work, and each participant has worked with improvement of existing procedures or development of new procedures. In addition an intercomparison exercise on the determination of natural radionuclides in ground water has been performed. Other work performed in Radchem-2005 include: 1) Development of new procedures for the determination of Am and Cm in environmental samples; 2) Development of a procedure for age determination of Pu; 3) Rapid determination of Pu using ICP-MS; 4) Determination of U, Pu and Am in emergency situations; 5) Sequential determination of Sr, U, Pu, Am and Cm in urine; 6) Ultra low level measurements using ICP-MS. (au)

  12. Intelligent Optics Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The Intelligent Optics Laboratory supports sophisticated investigations on adaptive and nonlinear optics; advancedimaging and image processing; ground-to-ground and...

  13. Geospatial Services Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: To process, store, and disseminate geospatial data to the Department of Defense and other Federal agencies.DESCRIPTION: The Geospatial Services Laboratory...

  14. Low-level simultaneous determination of As and Sb in standard reference materials using radiochemical neutron activation analysis with isotopic 77As and 125Sb tracers

    International Nuclear Information System (INIS)

    Byrne, A.R.

    1987-01-01

    The aim of the present work was to develop an older method used in our laboratory based on selective solvent extraction of As and Sb as their iodides with toluene, and by the use of the radioisotopic tracers 77 As and 125 Sb, to improve the accuracy by better control of the radiochemical yields. 77 As was produced for each sample run by concurrent irradiation of a few mg of GeO 2 followed by a rapid separation of 77 As from 77 Ge. The radiochemically purified sample fraction containing 76+77 As and 122+125 Sb was counted on a Ge detector in good geometry. The γ-lines of the four nuclides do not mutually interfere so that a combined measurement of As and Sb may be made. The method was applied to IAEA Milk Powder A-11, Animal Muscle H-4, Bowen's Kale and some other SRMs. The results obtained are discussed in the light of literature measurements. From present and previous results, together with data by Heydorn, the presently accepted value for As in Bowen's Kale of 140 ngxg -1 may be 20% too high. (orig.)

  15. Rupture preparation process controlled by surface roughness on meter-scale laboratory fault

    Science.gov (United States)

    Yamashita, Futoshi; Fukuyama, Eiichi; Xu, Shiqing; Mizoguchi, Kazuo; Kawakata, Hironori; Takizawa, Shigeru

    2018-05-01

    We investigate the effect of fault surface roughness on rupture preparation characteristics using meter-scale metagabbro specimens. We repeatedly conducted the experiments with the same pair of rock specimens to make the fault surface rough. We obtained three experimental results under the same experimental conditions (6.7 MPa of normal stress and 0.01 mm/s of loading rate) but at different roughness conditions (smooth, moderately roughened, and heavily roughened). During each experiment, we observed many stick-slip events preceded by precursory slow slip. We investigated when and where slow slip initiated by using the strain gauge data processed by the Kalman filter algorithm. The observed rupture preparation processes on the smooth fault (i.e. the first experiment among the three) showed high repeatability of the spatiotemporal distributions of slow slip initiation. Local stress measurements revealed that slow slip initiated around the region where the ratio of shear to normal stress (τ/σ) was the highest as expected from finite element method (FEM) modeling. However, the exact location of slow slip initiation was where τ/σ became locally minimum, probably due to the frictional heterogeneity. In the experiment on the moderately roughened fault, some irregular events were observed, though the basic characteristics of other regular events were similar to those on the smooth fault. Local stress data revealed that the spatiotemporal characteristics of slow slip initiation and the resulting τ/σ drop for irregular events were different from those for regular ones even under similar stress conditions. On the heavily roughened fault, the location of slow slip initiation was not consistent with τ/σ anymore because of the highly heterogeneous static friction on the fault, which also decreased the repeatability of spatiotemporal distributions of slow slip initiation. These results suggest that fault surface roughness strongly controls the rupture preparation process

  16. Processing of fallopian tube, ovary, and endometrial surgical pathology specimens: A survey of U.S. laboratory practices.

    Science.gov (United States)

    Samimi, Goli; Trabert, Britton; Duggan, Máire A; Robinson, Jennifer L; Coa, Kisha I; Waibel, Elizabeth; Garcia, Edna; Minasian, Lori M; Sherman, Mark E

    2018-03-01

    Many high-grade serous carcinomas initiate in fallopian tubes as serous tubal intraepithelial carcinoma (STIC), a microscopic lesion identified with specimen processing according to the Sectioning and Extensive Examination of the Fimbria protocol (SEE-Fim). Given that the tubal origin of these cancers was recently recognized, we conducted a survey of pathology practices to assess processing protocols that are applied to gynecologic surgical pathology specimens in clinical contexts in which finding STIC might have different implications. We distributed a survey electronically to the American Society for Clinical Pathology list-serve to determine practice patterns and compared results between practice types by chi-square (χ2) tests for categorical variables. Free text comments were qualitatively reviewed. Survey responses were received from 159 laboratories (72 academic, 87 non-academic), which reported diverse specimen volumes and percentage of gynecologic samples. Overall, 74.1% of laboratories reported performing SEE-Fim for risk-reducing surgical specimens (82.5% academic versus 65.7% non-academic, p STIC or early cancer precursors. Published by Elsevier Inc.

  17. Development of the University of Washington Biofuels and Biobased Chemicals Process Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Gustafson, Richard [University of Washington

    2014-02-04

    The funding from this research grant enabled us to design and build a bioconversion steam explosion reactor and ancillary equipment such as a high pressure boiler and a fermenter to support the bioconversion process research. This equipment has been in constant use since its installation in 2012. Following are research projects that it has supported: • Investigation of novel chip production method in biofuels production • Investigation of biomass refining following steam explosion • Several studies on use of different biomass feedstocks • Investigation of biomass moisture content on pretreatment efficacy. • Development of novel instruments for biorefinery process control Having this equipment was also instrumental in the University of Washington receiving a $40 million grant from the US Department of Agriculture for biofuels development as well as several other smaller grants. The research that is being done with the equipment from this grant will facilitate the establishment of a biofuels industry in the Pacific Northwest and enable the University of Washington to launch a substantial biofuels and bio-based product research program.

  18. Comparative Study of Laboratory-Scale and Prototypic Production-Scale Fuel Fabrication Processes and Product Characteristics

    International Nuclear Information System (INIS)

    2014-01-01

    An objective of the High Temperature Gas Reactor fuel development and qualification program for the United States Department of Energy has been to qualify fuel fabricated in prototypic production-scale equipment. The quality and characteristics of the tristructural isotropic coatings on fuel kernels are influenced by the equipment scale and processing parameters. Some characteristics affecting product quality were suppressed while others have become more significant in the larger equipment. Changes to the composition and method of producing resinated graphite matrix material has eliminated the use of hazardous, flammable liquids and enabled it to be procured as a vendor-supplied feed stock. A new method of overcoating TRISO particles with the resinated graphite matrix eliminates the use of hazardous, flammable liquids, produces highly spherical particles with a narrow size distribution, and attains product yields in excess of 99%. Compact fabrication processes have been scaled-up and automated with relatively minor changes to compact quality to manual laboratory-scale processes. The impact on statistical variability of the processes and the products as equipment was scaled are discussed. The prototypic production-scale processes produce test fuels that meet fuel quality specifications.

  19. The status of medical laboratory towards of AFRO-WHO accreditation process in government and private health facilities in Addis Ababa, Ethiopia.

    Science.gov (United States)

    Mesfin, Eyob Abera; Taye, Bineyam; Belay, Getachew; Ashenafi, Aytenew

    2015-01-01

    The World Health Organization Regional Office for Africa (WHO AFRO) introduces a step wise incremental accreditation approach to improving quality of laboratory and it is a new initiative in Ethiopia and activities are performed for implementation of accreditation program. Descriptive cross sectional study was conducted in 30 laboratory facilities including 6 laboratory sections to determine their status towards of accreditation using WHO AFRO accreditation checklist and 213 laboratory professionals were interviewed to assess their knowledge on quality system essentials and accreditation in Addis Ababa Ethiopia. Out of 30 laboratory facilities 1 private laboratory scored 156 (62%) points, which is the minimum required point for WHO accreditation and the least score was 32 (12.8%) points from government laboratory. The assessment finding from each section indicate that 2 Clinical chemistry (55.2% & 62.8%), 2 Hematology (55.2% & 62.8%), 2 Serology (55.2% & 62.8%), 2 Microbiology (55.2% & 62.4%), 1 Parasitology (62.8%) & 1 Urinalysis (61.6%) sections scored the minimum required point for WHO accreditation. The average score for government laboratories was 78.2 (31.2%) points, of these 6 laboratories were under accreditation process with 106.2 (42.5%) average score, while the private laboratories had 71.2 (28.5%) average score. Of 213 respondents 197 (92.5%) professionals had a knowledge on quality system essentials whereas 155 (72.8%) respondents on accreditation. Although majority of the laboratory professionals had knowledge on quality system and accreditation, laboratories professionals were not able to practice the quality system properly and most of the laboratories had poor status towards the WHO accreditation process. Thus government as well as stakeholders should integrate accreditation program into planning and health policy.

  20. Hydrologic testing in wells near the Idaho Chemical Processing Plant at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Johnson, G.S.; Olsen, J.H.; Ralston, D.R.

    1994-01-01

    The Snake River Plain aquifer beneath the INEL is often viewed as a 2-dimensional system, but may actually possess 3-dimensional properties of concern. A straddle-packer system is being used by the State's INEL Oversight Program to isolate specific aquifer intervals and define the 3-dimensional chemical and hydrologic characteristics of the aquifer. The hydrologic test results from wells USGS 44, 45, and 46 near the Idaho Chemical Processing Plant indicate that: (1) Vertical variation in static head is less than 0.3 feed, (2) barometric efficiencies are between 25 and 55 percent, and (3) the system responds to distant pumping as a multi-layered, but interconnected system. 3 refs., 7 figs., 3 tabs

  1. Dynamics and structure of ignition process in plasma. Ignition dynamics and structure of laboratory plasmas

    International Nuclear Information System (INIS)

    Nagasaki, Kazunobu; Takamura, Shuichi; Razzak, Md. Abdur; Uesugi, Yoshihiko; Yoshimura, Yasuo; Cappa, Alvaro

    2008-01-01

    The dynamics and structure of plasma production are stated by the results of two experiments such as the radio frequency thermal plasmas produced by inductively coupled plasma technique at atmospheric pressure and the second harmonic ECH. The first experiment results explained transition from the electrostatic discharge mode of forming streamer to the induced discharge mode after forming the discharge channel that the streamer connected to in the azimuth direction. The other experiment explained the dynamics which the initial plasma produced at the ECH resonance point spread in the direction of radius. The divergence and transition related to the nonlinear process were observed independently existing the magnetic field or incident power. The experiment devices, conditions, results, and modeling are reported. (S.Y.)

  2. Scientific and technical conference. Problems and horizons of development of chemical and radiochemical control in nuclear energetics. Collection of summaries of reports

    International Nuclear Information System (INIS)

    2001-01-01

    During scientific and technical conference on problems of development of chemical and radiochemical control in nuclear energetics following themes were considered: the problems of methodological and instrumental assurance of chemical and radiochemical control at working nuclear power plants and nuclear energetic units; modern conceptions of automation systems construction of chemical and radiochemical control on the basis of intellectual measuring channels; the ways of decision of generally system problems of organization and management of chemical and radiochemical control using computed technologies; the problems of certification of chemical and radiochemical methods of measuring in nuclear energetics [ru

  3. Design and development of a rotary calciner for radiochemical waste

    International Nuclear Information System (INIS)

    Pande, D.P.; Sutar, V.D.; Sengar, P.B.S.

    1997-01-01

    Present experience and knowledge in handling of radioactive waste has led to identification of major thrust areas in the development of the treatment processes. In order to reduce evaporation and volatility losses in the vitrification facility, it is advantageous to carry out evaporation and calcination steps in another equipment like rotary calciner. Efforts have been directed for the engineering development of a Rotary Ball Kiln calciner. This paper highlights the important design features of the Rotary Ball Kiln Calciner for the radioactive waste. In this work, an attempt has been made to systematically evaluate the influence of process and design parameters. The results obtained on calcination will provide a design basis and rational methodology for the optimum utilization of these processes and equipment for volume reduction and calcination of the liquid waste

  4. The quality of microorganism on coal bed methane processing with various livestock waste in laboratory scale

    Science.gov (United States)

    Marlina, E. T.; Kurnani, Tb. B. A.; Hidayati, Y. A.; Rahmah, K. N.; Joni, I. M.; Harlia, E.

    2018-02-01

    Coal-bed Methane (CBM) is a form of natural gas extracted from coal and has been developed as future energy source. Organic materials are required as nutrition source for methanogenic microbes. The addition of cattle waste in the formation of CBM on coal media can be utilized as organic materials as well as methanogenic microbe sources. This research covered study of total amount of anaerobic microbes, methane production, protozoa, fungi and endoparasites. Descriptive approach is conducted for this study. Media used for culturing methanogens is Nutrient Agar in powder form and Lactose Broth with the addition of rumen fluid. The technique for counting microbes is through Total Plate Count in anaerobic Hungate tube, methane was analyzed using Gas Chromatography (GC), while identification of protozoa, fungi and endoparasites based on its morphology is conducted before and after anaerobic fermentation process. Incubation period is 30 days. The results showed that growth of anaerobic microbes from dairy cattle waste i.e. biogas sludge is 3.57×103 CFU/ml and fresh feces is 3.38 × 104 CFU/ml, growth of anaerobic microbes from beef cattle waste i.e. biogas sludge is 7.0 × 105 CFU/ml; fresh feces is 7.5 x 104 CFU/ml; and rumen contents of about 1.33 × 108 CFU/ml. Methane production in dairy cattle waste in sludge and fresh feces amounted to 10.57% and 2.39%, respectively. Methane production in beef cattle waste in sludge accounted for 5.95%; in fresh feces it is about 0.41%; and rumen contents of 4.92%. Decreasing of protozoa during fermentation to 84.27%, dominated by Eimeria sp. Decreasing of fungi to 16%, dominated by A. Niger, A. Flavus, A. Fumigatus and Monilia sitophila. Decreasing of endoparasitic worms to 15%, dominated by Strongylus sp. and Fasciola sp. The growth of anaerobic microbes and methane production indicated that dairy cattle waste and beef cattle waste have potential as source of methanogenic microbes, meanwhile the decreasing amount of protozoa

  5. Chemical Reactor Automation as a way to Optimize a Laboratory Scale Polymerization Process

    Science.gov (United States)

    Cruz-Campa, Jose L.; Saenz de Buruaga, Isabel; Lopez, Raymundo

    2004-10-01

    The automation of the registration and control of variables involved in a chemical reactor improves the reaction process by making it faster, optimized and without the influence of human error. The objective of this work is to register and control the involved variables (temperatures, reactive fluxes, weights, etc) in an emulsion polymerization reaction. The programs and control algorithms were developed in the language G in LabVIEW®. The designed software is able to send and receive RS232 codified data from the devices (pumps, temperature sensors, mixer, balances, and so on) to and from a personal Computer. The transduction from digital information to movement or measurement actions of the devices is done by electronic components included in the devices. Once the programs were done and proved, chemical reactions of emulsion polymerization were made to validate the system. Moreover, some advanced heat-estimation algorithms were implemented in order to know the heat caused by the reaction and the estimation and control of chemical variables in-line. All the information gotten from the reaction is stored in the PC. The information is then available and ready to use in any commercial data processor software. This work is now being used in a Research Center in order to make emulsion polymerizations under efficient and controlled conditions with reproducible results. The experiences obtained from this project may be used in the implementation of chemical estimation algorithms at pilot plant or industrial scale.

  6. Testing a Dual Process Model of Gender-Based Violence: A Laboratory Examination.

    Science.gov (United States)

    Berke, Danielle S; Zeichner, Amos

    2016-01-01

    The dire impact of gender-based violence on society compels development of models comprehensive enough to capture the diversity of its forms. Research has established hostile sexism (HS) as a robust predictor of gender-based violence. However, to date, research has yet to link men's benevolent sexism (BS) to physical aggression toward women, despite correlations between BS and HS and between BS and victim blaming. One model, the opposing process model of benevolent sexism (Sibley & Perry, 2010), suggests that, for men, BS acts indirectly through HS to predict acceptance of hierarchy-enhancing social policy as an expression of a preference for in-group dominance (i. e., social dominance orientation [SDO]). The extent to which this model applies to gender-based violence remains untested. Therefore, in this study, 168 undergraduate men in a U. S. university participated in a competitive reaction time task, during which they had the option to shock an ostensible female opponent as a measure of gender-based violence. Results of multiple-mediation path analyses indicated dual pathways potentiating gender-based violence and highlight SDO as a particularly potent mechanism of this violence. Findings are discussed in terms of group dynamics and norm-based violence prevention.

  7. Instrumental and laboratory assessment of stressful remodelling processes in bone tissue at total hip replacement

    Directory of Open Access Journals (Sweden)

    E.V. Karjakina

    2010-06-01

    Full Text Available Research objective is to estimate stressful remodelling features of bone tissue according to the densitometry data and to the level of biochemical markers of bone resorption and formation in total hip replacement (THR. Bone tissue mineral density (BTMD, condition of calcium-phosphoric metabolism and biochemical markers of bone formation (osteocalcin and bone isoenzyme of alkaline phosphatase and resorption (С-terminal bodypeptide of the I type collagen have been determined in 52 patients with coxarthrosis of ll-lll stages with marked joint dysfunction before and after THR. The control group included 24 donors. The data were considered to be reliable when the probability index was р<0,05. The reliable (р<0,05 change of BTMD was determined only in 3-6 months after the operation, whereas the change of biochemical markers of remodeling had already been done after 1,5-3 months, allowing to define the group of patients with obvious negative bone balance: strong predominance of resorption processes without compensation of the subsequent adequate osteogenesis, that subsequently could lead to significant bone tissue deficiency in the area adjacent to the endoprosthesis. Changes of indices of calcium-phosphoric metabolism were not certain during the investigation term. ln conclusion it is to state that biochemical markers of remodeling in comparison with BTMD allow to estimate objectively features of adaptive bone tissue remodeling after THR in earlier periods and to define group of patients with sharp intensification of metabolism and obvious negative bone balance

  8. The effects of dissociation on information processing for analogue trauma and neutral stimuli: a laboratory study.

    Science.gov (United States)

    Olsen, Shira A; Beck, J Gayle

    2012-01-01

    This study investigated the effects of high and low levels of dissociation on information processing for analogue trauma and neutral stimuli. Fifty-four undergraduate females who reported high and low levels of trait dissociation were presented with two films, one depicting traumatic events, the other containing neutral material. Participants completed a divided attention task (yielding a proxy measure of attention), as well as explicit memory (free-recall) and implicit memory (word-stem completion) tasks for both films. Results indicated that the high DES group showed less attention and had poorer recall for the analogue trauma stimuli, relative to the neutral stimuli and the low DES group. These findings suggest that high levels of trait dissociation are associated with reductions in attention and memory for analogue trauma stimuli, relative to neutral stimuli and relative to low trait dissociation. Implications for the role of cognitive factors in the etiology of negative post-trauma responses are discussed. Copyright © 2011 Elsevier Ltd. All rights reserved.

  9. Laboratory testing results of kinetics and processing technology of the polymetallic sulphide concentrate Blagojev Kamen – Serbia

    Directory of Open Access Journals (Sweden)

    Milorad Ćirković

    2016-06-01

    Full Text Available This work presents the laboratory testing results of kinetics the oxidation process and sample processing of the sulphide polymetallic concentrate Blagojev Kamen. The aim of investigation is recovery of these types of raw material, present in large quantities in the peripheral parts of already used primary mineral deposits of copper, because of their high economic potential due to the content of a large number of metals and especially precious metals. Characterization of this raw material is based on the chemical analyses, XRD results, DTA analysis, etc. For these investigations, the sulphide concentrate with the following content was used in %: Cu – 2.3; Fe – 19.8; S – 27.19; Zn – 9.13; As – 0.167; Pb – 15.63; SiO2 – 17.93; CaO – 0.97; Al2O3 – 1.43; Ag – 480 g/t; Au – 659 g/t. Kinetic investigations of oxidation processes were carried out under the isothermal conditions within the temperature range of 400 to 625 oC. The Sharp's model was used for determination the kinetics parameters, and determined values of activation energy are 67 kJ/mole for the first period, and 47 kJ/mole for the second period. Pyrometallurgical treatment of this type of polymetallic concentrate, in the laboratory conditions, was carried out using the oxidative roasting and, then the reduction smelting was done in the Taman's furnace. Gold from 90.5 to 97.95% and silver from 77.28 to 93.37% are moved into the raw lead (smelting product. Gold from 1.1 to 3.92% and silver from 4.35 to 8.42% are moved into the polymetallic copper matte. Gold from 0.58 to 1.6% and silver from 2.45 to 6.82% are moved into the slag.

  10. Improved laboratory assays of Pu and U for SRP purification and finishing processes

    International Nuclear Information System (INIS)

    Holland, M.K.; Dorsett, R.S.

    1986-01-01

    Significant improvements have been made in routine assay techniques for uranium and plutonium as part of an effort to improve accountability at the Savannah River Plant (SRP). Emphasis was placed on input/output accountability points and key physical inventory tanks associated with purification and finishing processes. Improvements were made in existing assay methods; new methods were implemented; and the application of these methods was greatly expanded. Prior to assays, samples were validated via density measurements. Digital density meters precise to four, five, and six decimal places were used to meet specific requirements. Improved plutonium assay techniques are now in routine use: controlled-potential coulometry, ion-exchange coulometry, and Pu(III) diode-array spectrophotometry. A new state-of-the-art coulometer was fabricated and used to ensure maximum accuracy in verifying standards and in measuring plutonium in product streams. The diode-array spectrophotometer for Pu(III) measurements was modified with fiber optics to facilitate remote measurements; rapid, precise measurements made the technique ideally suited for high-throughput assays. For uranium assays, the isotope-dilution mass spectrometric (IDMS) method was converted to a gravimetric basis. The IDMS method and the existing Davies-Gray titration (gravimetric basis) have met accountability requirements for uranium. More recently, a Pu(VI) diode-array spectrophotometric method was used on a test basis to measure plutonium in shielded-cell input accountability samples. In addition, tests to measure uranium via diode-array spectrophotometry were initiated. This rapid, precise method will replace IDMS for certain key sample points

  11. Status of microwave process development for RH-TRU [remote-handled transuranic] wastes at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    White, T.L.; Youngblood, E.L.; Berry, J.B.; Mattus, A.J.

    1990-01-01

    The Oak Ridge National Laboratory (ORNL) Waste Handling and Packaging Plant is developing a microwave process to reduce and solidify remote-handled transuranic (RH-TRU) liquids and sludges presently stored in large tanks at ORNL. Testing has recently begun on an in-drum microwave process using nonradioactive RH-TRU surrogates. The microwave process development effort has focused on an in-drum process to dry the RH-TRU liquids and sludges in the final storage container and then melt the salt residues to form a solid monolith. A 1/3-scale proprietary microwave applicator was designed, fabricated, and tested to demonstrate the essential features of the microwave design and to provide input into the design of the full-scale applicator. The microwave fields are uniform in one dimension to reduce the formation of hot spots on the microwaved wasteform. The final wasteform meets the waste acceptance criteria for the Waste Isolation Pilot Plant, a federal repository for defense transuranic wastes near Carlsbad, New Mexico. 7 refs., 1 fig., 1 tab

  12. First results of in-can microwave processing experiments for radioactive liquid wastes at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    White, T.L.; Youngblood, E.L.; Berry, J.B.; Mattus, A.J.

    1990-01-01

    The Oak Ridge National Laboratory (ORNL) Waste Handling and Packaging Plant is developing a microwave process to reduce and solidify remote-handled transuranic (RH-TRU) liquids and sludges presently stored in large tanks at ORNL. Testing has recently begun on an in drum microwave process using nonradioactive RH-TRU surrogates. The microwave process development effort has focused on an in-drum process to dry the RH-TRU liquids and sludges in the final storage container and then melt the salt residues to form a solid monolith. A 1/3-scale proprietary microwave applicator was designed, fabricated, and tested to demonstrate the essential features of the microwave design and to provide input into the design of the full-scale applicator. Conductivity cell measurements suggest that the microwave energy heats near the surface of the surrogate over a wide range of temperatures. The final wasteform meets the waste acceptance criteria for the Waste Isolation Pilot Plant, a federal repository for defense transuranic wastes near Carlsbad, New Mexico. 7 refs., 3 figs., 1 tab

  13. Startup of the remote laboratory-scale waste-treatment facility

    International Nuclear Information System (INIS)

    Knox, C.A.; Siemens, D.H.; Berger, D.N.

    1981-01-01

    The Remote Laboratory-Scale Waste-Treatment Facility was designed as a system to solidify small volumes of radioactive liquid wastes. The objectives in operating this facility are to evaluate solidification processes, determine the effluents generated, test methods for decontaminating the effluents, and provide radioactive solidified waste products for evaluation. The facility consists of a feed-preparation module, a waste-solidification module and an effluent-treatment module. The system was designed for remote installation and operation. Several special features for remotely handling radioactive materials were incorporated into the design. The equipment was initially assembled outside of a radiochemical cell to size and fabricate the connecting jumpers between the modules and to complete some preliminary design-verification tests. The equipment was then disassembled and installed in the radiochemical cell. When installation was completed the entire system was checked out with water and then with a nonradioactive simulated waste solution. The purpose of these operations was to start up the facility, find and solve operational problems, verify operating procedures and train personnel. The major problems experienced during these nonradioactive runs were plugging of the spray calciner nozzle and feed tank pumping failures. When these problems were solved, radioactive operations were started. This report describes the installation of this facility, its special remote design feature and the startup operations

  14. Assessing Clinical Laboratory Quality: A College of American Pathologists Q-Probes Study of Prothrombin Time INR Structures, Processes, and Outcomes in 98 Laboratories.

    Science.gov (United States)

    Howanitz, Peter J; Darcy, Theresa P; Meier, Frederick A; Bashleben, Christine P

    2015-09-01

    The anticoagulant warfarin has been identified as the second most frequent drug responsible for serious, disabling, and fatal adverse drug events in the United States, and its effect on blood coagulation is monitored by the laboratory test called international normalized ratio (INR). To determine the presence of INR policies and procedures, INR practices, and completeness and timeliness of reporting critical INR results in participants' clinical laboratories. Participants reviewed their INR policies and procedure requirements, identified their practices by using a questionnaire, and studied completeness of documentation and timeliness of reporting critical value INR results for outpatients and emergency department patients. In 98 participating institutions, the 5 required policies and procedures were in place in 93% to 99% of clinical laboratories. Fifteen options for the allowable variations among duplicate results from different analyzers, 12 different timeliness goals for reporting critical values, and 18 unique critical value limits were used by participants. All required documentation elements were present in 94.8% of 192 reviewed INR validation reports. Critical value INR results were reported within the time frame established by the laboratory for 93.4% of 2604 results, but 1.0% of results were not reported. Although the median laboratories successfully communicated all critical results within their established time frames and had all the required validation elements based in their 2 most recent INR calculations, those participants at the lowest 10th percentile were successful in 80.0% and 85.7% of these requirements, respectively. Significant opportunities exist for adherence to INR procedural requirements and for practice patterns and timeliness goals for INR critical results' reporting.

  15. In-Process Analysis Program for the Isolock sampler at the Gunite and Associated Tanks, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1998-05-01

    The In-Process Analysis Program documents the requirements for handling, transporting, and analyzing waste slurry samples gathered by the Bristol Isolock slurry sampler from the Gunite and Associated Tanks at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Composite samples will be gathered during sludge retrieval operations, labeled, transported to the appropriate laboratory, and analyzed for physical and radiological characteristics. Analysis results will be used to support occupational exposure issues, basic process control management issues, and prediction of radionuclide flow

  16. Trace determination of uranium and thorium in biological samples by radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Benedik, Ljudmila; Repinc, Urska; Byrne, Anthony R.; Stegnar, Peter

    2002-01-01

    Radiochemical neutron activation analysis (RNAA) is an excellent method for determining uranium and thorium; it offers unique possibilities for their ultratrace analysis using selective radiochemical separations. Regarding the favourably sensitive nuclear characteristics of uranium and of thorium with respect to RNAA, but the different half-lives of their induced nuclides, two different approaches were used. In the first approach uranium and thorium were determined separately via 239 U, 239 Np and 233 Pa. In the second approach these elements were 239 239 233 determined simultaneously in a single sample using U and/or Np and Pa. Isolation of induced nuclides was based on separation by extraction and/or anion exchange chromatography. Chemical yields were measured in each sample aliquot using added 235 U, 238 Np and 231 Pa radioisotopic tracers. (author)

  17. Slifers revisited: a method for determining yields independent of radiochemical measurements

    International Nuclear Information System (INIS)

    Rambo, J.T.

    1976-01-01

    It would be very desirable if an independent method other than radiochemical measurement were available to determine the yields of low-yield events in the alluviums and tuffs of areas 2, 9, and 10 at the Nevada Test Site. The successful application of slifers to the measurement of yields from high-yield events suggests that under some conditions they may also be usable with low-yield events. This view is supported by the evidence discussed here, which is based on direct experience with slifer yield measurements for low-yield events in porous media. Suggested methods for improving slifer yield determinations and a method for determining yields independent of radiochemical measurements are offered

  18. Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B., E-mail: rpgm@cdtn.br, E-mail: reisas@cdtn.br, E-mail: gfk@cdtn.br, E-mail: esct@cdtn.br, E-mail: tco@cdtn.br, E-mail: ama@cdtn.br, E-mail: francom@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, {sup 3}H, {sup 14}C, {sup 55}Fe, {sup 59}Ni, {sup 63}Ni, {sup 90}Sr, {sup 93}Zr, {sup 94}Nb, {sup 99}Tc, {sup 129}I, {sup 235}U, {sup 238}U, {sup 238}Pu, {sup 239}+{sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 242}Cm e {sup 243}+{sup 244}Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

  19. Requirement of radiochemical recovery determination for gross alpha and gross beta estimation in drinking water

    International Nuclear Information System (INIS)

    Raveendran, Nanda; Rao, D.D.; Hegde, A.G.

    2010-01-01

    Presence of radionuclides in drinking water which emits Alpha and Beta particles are the potential sources of internal exposure in drinking water. Gross alpha and gross beta determination in drinking water and packaged drinking water (PDW) as per BIS (Bureau of Indian standards) standards is discussed here. The methods have been tested to account for losses in the radiochemical procedures using radionuclides such as 137 Cs, 90 Sr, 226 Ra, 239 Pu, 243 Am, 232 U. The methods have also been validated in an IAEA proficiency test conducted during 2009. Monitoring of gross alpha and gross beta activity observed in drinking water/packaged drinking water from various states of India were within the limits set by BIS. Average radiochemical recoveries of 84% and 63% were obtained for gross α and gross β respectively. (author)

  20. Radiochemical neutron activation analysis for trace elements of basic ingredients of pan

    International Nuclear Information System (INIS)

    Zaidi, J.H.; Arif, M.; Fatima, I; Qureshi, I.H.

    2002-01-01

    Extensive use of pan, by one-tenth of world's population, entails the evaluation of trace element contents in its ingredients. Radiochemical neutron activation analysis (RNAA) was developed and successfully employed to determine the concentration of 36 trace elements (essential, toxic and nonessential) in its four basic ingredients, leaf of betel pepper, betel nut, catechu and lime. The radiochemical separation methodology has significantly improved the detection limits of most of these elements due to suppression of Compton background. Base-line values of certain toxic and essential elements in these ingredients is provided. The daily intake of essential and toxic elements through pan was estimated and compared with the recommended values. The cumulative intake of Mn is four times higher than the recommended value and that of toxic elements is well below the tolerance limits. (author)

  1. Leakage evaluation in the PCV (Primary Containment Vessel) using chemical and radiochemical data

    International Nuclear Information System (INIS)

    Maeda, Katsuji; Nagasawa, Katsumi

    1998-01-01

    Keeping the reliability of nuclear power plant operation, the primary coolant leakage in the PCV is strictly restricted by the Technical Specifications. It is very important to detect an indication of leakage and estimate the source of leakage to provide countermeasures. Usually the indication of leakage will be detected by increase of drain flow in the PCV sump. There are some possibilities of leakage sources in the PCV, such as reactor water, main steam, condensate, feedwater and closed cooling water. The leakage source contain different chemical and radiochemical species. This means that the leakage source can be presumed and detected by using chemical information from the PCV atmosphere and sump water. To detect the leakage indication and the source quickly and exactly, the PCV Leakage Detection Expert System has been developed. This paper describes how to evaluate the leakage indication and source in the PCV by using chemical and radiochemical data. (author)

  2. Rapid radiochemical methods for preparation of sup(99m)Tc labelled compounds

    International Nuclear Information System (INIS)

    Narasimhan, D.V.S.; Banodkar, S.M.; Kothari, K.; Mani, R.S.

    1981-01-01

    Several inorganic and organic compounds incorporating sup( 99 m)Tc are being extensively used for imaging various body organs. The preparation of these sup( 99 m)Tc compounds with the necessary purity requirements is carried out by controlled reduction of sup( 99 m)Tc-pertechnetate using Sn(II) ions as the reducing agent followed by complexation with various active ingredients. The authors here present procedures developed at Radiopharmaceuticals Section of BARC for preparing sup( 99 m)Tc-diphosphonate, sup( 99 m)Tc-glucoheptonate, sup( 99 m)Tc-albumin microspheres and sup( 99 m)Tc-phytate with high radiochemical purity. The paper also describes procedures for the preparation of freeze-dried kits for single step preparation of these compounds. The paper also describes the authors' experience with various analytical procedures for the determination of radiochemical purity of these preparations. (author)

  3. Study of performance characteristics of a radiochemical method to determine uranium in biological samples

    International Nuclear Information System (INIS)

    Puga, Maria J.; Cerchietti, Maria L.R.; Prudenzo, J.E.; Arguelles, Maria G.

    2005-01-01

    In this paper is described a methodology to calculate detection limit (Ld), quantification level (Lq) and minimum detectable activity (MDA) in a radiochemical method for determination of uranium in urine samples. The concentration is measured by fluorimetry and alpha gross activity using liquid scintillation counting (LSC). The calculation of total propagated uncertainty on a spike sample is presented. Furthermore, the major sources of uncertainty and percentage contribution in both measurements are assessed. (author)

  4. New radiochemical methods for determination of 237Np a 241Pu using extraction chromatography (Presentation)

    International Nuclear Information System (INIS)

    Strisovska, J.

    2013-01-01

    Thesis was focused on the development of a new methodology for the separation of anthropogenic transuranium radionuclides 237 Np a 241 Pu from different kinds of matrices. The analytical methods used in this study were based on extraction chromatography and were optimized according to the sample type. The proposed radiochemical procedure is a combination of two algorithms, which represent the separation of radionuclides by using extraction chromatographic sorbents TEVA resin and TRU resin supplied by Eichrom Technologies LLC. 239 Np a 237 Np were selectively captured on sorbent TEVA resin in oxidation state 4+. TRU resin was used for purification of plutonium fraction from interfering americium radionuclide. 242 Pu and 239 Np radionuclides as tracers have been used to monitor the radiochemical yields of separation. Before every radiochemical separation tracer radionuclide 239 Np was obtained by separation from the parent radionuclide 2 43 Am, which is in radioactive equilibrium to 239 Np. The average yield of chemical separation was 69,3% for 239 Np at 277 keV energy line and 65,9% at 228 keV energy line. The NPL AH-B08069 (2008) samples which consist of the mixture of alpha-radionuclides were used for the modification and optimization of separation method used for separation of Np and Pu in model samples. This method provided high radiochemical yields of 239,240 Pu (95,0 ± 3,5)% and 237 Np (87,9 ± 3,0)%.. Reliability of the method was verified by applying our modified separation procedures on reference materials IAEA-375 and IAEA-414 supplied by International Atomic Energy Agency. A good agreement between the results is obtained by this procedure and the certified values were found. Samples of contaminated soils from the area of Nuclear power plant A-1 Jaslovske Bohunice which is stored temporarily before disposal were analyzed using developed separation procedure. Specific activity of investigated radionuclides was determined in these samples. (author)

  5. A radiochemical technique for the determination of mercury in drinking water

    International Nuclear Information System (INIS)

    Ahmad, S.; Chaudhri, M.S.; Qureshi, I.H.

    1982-01-01

    A radiochemical method for the separation and determination of mercury in drinking water has been developed. The radionuclides of mercury formed after neutron irradiation of the sample were separated by liquid/liquid extraction using PAN and TBA mixture in chloroform from aqueous nitric acid medium. Quantitative extraction of mercury was achieved in a single step and the equilibrium was attained within five minutes. (orig.)

  6. Determination of mercury in biologycal samples by radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Suc, N.V.

    1989-01-01

    The radiochemical neutron activation analysis was applied to determine contents of mercury in biological samples. Samples were digested in mixing of H 2 SO 4 and HNO 3 acid. After extraction of mercury by Ni-Ditiodietylphosphoric acid in carbontetrachloride, mercury was back extracted by 5% KI solution. Contents of mercury from five samples of fish was determined by this method. The accuracy of the method was checked by comparing it with NBS standard samples and results are good agreement

  7. Radiochemical determination and separation or total radium, 226Ra and 224Ra

    International Nuclear Information System (INIS)

    Suarez, J. A.; Gonzalez, J. A.; Pablo, M. A. de

    1987-01-01

    Radiochemical purification and separation of radium has been carried out and the determination of total radium solubilized in aqueous samples has been studied assuming that all the alpha emitters of the sample have their origin in the 226Ra and elements of its desintegration chain. Also, the activities of 22Ra and 226 Ra have been evaluated separately doing a measurement after the chemical separation of the radium and another one 10 days after. (Author) 9 refs

  8. Analysis of the radiochemical purity of 18F-FDG by HPLC

    International Nuclear Information System (INIS)

    Chen Liguang; Tang Anwu; He Shanzhen; Chen Yulong

    2001-01-01

    The radiochemical purity (RCP) of 18 F-FDG is analyzed by HPLC. Eighty-five percent acetonitrile is used as the eluting solution. Carbon hydrate column is used as separation column. The t R of 18 F - is 6.50 min and 18 F-FDG is 9.00 min. HPLC take less time and has higher sensitivity than TLC for the same sample at the same time. So HPLC excels TLC in analyzing RCP of 18 F-FDG

  9. Synthesis of N-[methyl-11C]hydromorphone by using multivariate strategies for optimization of radiochemical yields

    International Nuclear Information System (INIS)

    Rimland, Annika; Bergson, Goeran; Obenius, Ulf; Sjoeberg, Stefan; Langstroem, Bengt

    1987-01-01

    The synthesis of N-[methyl- 11 C]hydromorphone has been performed by using [ 11 C]methyl iodide and desmethyl hydromorphone in a mixture of dimethylsulphoxide and dimethylformamide as solvent. Optimization of the radiochemical yield by varying the reaction conditions was performed by using multivariate strategies. The labelled hydromorphone was obtained in 72% radiochemical yield in the alkylation reaction with [ 11 C]-methyl iodide, counted from the end of the [ 11 C]methyl iodide synthesis. N-[Methyl- 11 C]hydromorphone was obtained as a ready injectable pharmaceutical solution with a total synthesis time of 40 min and in a 10% total radiochemical yield, with a radiochemical purity > 99.5%, according to HPLC analysis. (author)

  10. Processing summary report: Fabrication of cesium and strontium heat and radiation sources

    International Nuclear Information System (INIS)

    Holton, L.K. Jr.; Surma, J.E.; Allen, R.P.

    1989-02-01

    The Pacific Northwest Laboratory (PNL), has produced 30 isotopic heat sources (canisters) for the Federal Republic of Germany (FRG) to be used as part of a repository testing program in the Asse Salt Mine. PNL program work involved the filling, closure, and decontamination of the 30 canisters. The canisters were fabricated (filled) in three separate processing campaigns using the radioactive liquid-fed ceramic melter to produce a borosilicate glass. Within the borosilicate glass matrix radiochemical constituents ( 137 Cs and 90 Sr) were immobilized to yield a product with a predetermined decay heat and surface radiation exposure rate

  11. Radiochemical problems of radiation chemical synthesis in n, γ-field of nuclear reactor

    International Nuclear Information System (INIS)

    Mironov, V.P.; Frejdus, N.V.; Bugaenko, L.T.; Kalyazin, E.P.; Petryaev, E.P.

    1981-01-01

    A wide applicability of products of radiation chemical synthesis (RCS), using n, γ-irradiation, is limited by possible contamination of the latter with long-lived radioactive isotopes of chemical elements included in the composition of the reagent and compounds syntesized (chemically non-separable radionuclides - CNR). A technique of the determination of the limit accumulation CNR on the basis of radiation chemical parameters of the synthesis (radiation-chemical yield, the dose rate absorbed, singleness of purpose of RCS etc.) and radiochemical parameters of formation and accumulation of CNR (radiochemical yields of CNR in the products of radiolysis, neutron fluence, the reagent purity etc.) is suggested. The radiochemical evaluation of CNR accumulation (tritium and carbon-14), formed at the expense of activation with neutrons of chemical elements of water and organic substances, consisting of hydrogen, carbon and oxygen has shown that at relatively low yields of final products (> or approximately 3 molecules/100 eV) no accumulation of radionuclides in concentrations reaching the average admissible concentration takes place [ru

  12. Radiochemical aging of an epoxy network; Vieillissement radiochimique d'un reseau epoxyde

    Energy Technology Data Exchange (ETDEWEB)

    Devanne, Th

    2003-05-01

    This thesis is to give a better understanding of the radiochemical aging of a thermoset resin under gamma irradiation. The conditions of aging are gamma irradiation under air with a dose rate of 2 kGy/h at 120 C. The requested lifetime is four years, it means a dose of 70 MGy. The first step of this work was the choice of a resistive epoxy resin. This choice was made thanks to the literature data. The high glass transition temperature and the high amount of aromatic groups were the main criteria of the final choice. After this choice, thermal and mechanical properties were followed under thermal and radiochemical aging: i) under thermal aging, after 600 hours at 220 C, the glass transition temperature remained unchanged. But, from a mechanical point of view, properties at break dramatically decreased. This embrittlement was assigned to a critical oxidized layer. The thickness of this layer was estimated about 30 {mu}m. ii) the same kind of embrittlement was observed under radiochemical aging. Moreover, it appeared a decrease of the glass transition temperature when increasing the dose of irradiation. This indicates that the main degradation mechanism is chain scission under anaerobic atmosphere. We, then, proposed a mechanistic model associated with a kinetic model to predict the evolution of the glass transition temperature depending on the irradiation conditions. Parameters of the kinetic model were determined by solid NMR and ESR experiments. Comparison between experimental and calculated values at 120 C is satisfactory, a global good agreement was found. (author)

  13. Influence of Storage Temperature on Radiochemical Purity of 99mTc-Radiopharmaceuticals.

    Science.gov (United States)

    Uccelli, Licia; Boschi, Alessandra; Martini, Petra; Cittanti, Corrado; Bertelli, Stefania; Bortolotti, Doretta; Govoni, Elena; Lodi, Luca; Romani, Simona; Zaccaria, Samanta; Zappaterra, Elisa; Farina, Donatella; Rizzo, Carlotta; Giganti, Melchiore; Bartolomei, Mirco

    2018-03-15

    The influence of effective room temperature on the radiochemical purity of 99m Tc-radiopharmaceuticals was reported. This study was born from the observation that in the isolators used for the preparation of the 99m Tc-radiopharmaceuticals the temperatures can be higher than those reported in the commercial illustrative leaflets of the kits. This is due, in particular, to the small size of the work area, the presence of instruments for heating, the continuous activation of air filtration, in addition to the fact that the environment of the isolator used for the 99m Tc-radiopharmaceuticals preparation and storage is completely isolated and not conditioned. A total of 244 99m Tc-radiopharmaceutical preparations (seven different types) have been tested and the radiochemical purity was checked at the end of preparation and until the expiry time. Moreover, we found that the mean temperature into the isolator was significantly higher than 25 °C, the temperature, in general, required for the preparation and storage of 99m Tc-radiopharmaceuticals. Results confirmed the radiochemical stability of radiopharmaceutical products. However, as required in the field of quality assurance, the impact that different conditions than those required by the manufacturer on the radiopharmaceuticals quality have to be verified before human administration.

  14. Investigation of quantitative separation of thorium, uranium, neptunium and plutonium from complex radiochemical mixtures

    International Nuclear Information System (INIS)

    Ushatskij, V.N.; Preobrazhenskaya, L.D.; Kolychev, V.B.; Gugel', E.S.

    1979-01-01

    Quantitative separation of actinides and their radiochemical purification with the aid of TBP with subsequent separation of thorium and quantitative separation of U, Np and Pu with the aid of D2EHPA have been studied. The method has been developed for quantitative extraction-chromatographic separation and radiochemical purification of nanogram amounts of U, Pu and microgram amounts of Th and Np from complex radiochemical mixtures containing both fragment radioisotopes and non-radioactive macrocomponents ( Fe,Al,Mg,Mn, Na and others). The method calls for application of one-extraction-chromatographic column with TBP and one column with D2EHPA. Thorium is separated at the first stage since it does not form complexes in a chloride solution during washing of the sorption column with 6. OM HCl. Npsup((4)) and Pusup((3)) required for separation are stabilized with the aid of hydrazine and hydroxylamine mixture. The yield of each of the above-cited actinide elements during the complete two-stage separation and at the stage of their separation varies within the range of 98.5-99.3%

  15. The virtual product-process design laboratory to manage the complexity in the verification of formulated products

    DEFF Research Database (Denmark)

    Conte, Elisa; Gani, Rafiqul; Malik, Tahir I.

    2011-01-01

    -Process Design laboratory (virtual PPD-lab) software is based on this decomposition strategy for the design of formulated liquid products. When the needed models are available in the software, the solution of formulation design/verification problems is straightforward, while when models are not available...... mixtures need to be predicted. This complexity has to be managed through decomposition of the problem into sub-problems. Each sub-problem is solved and analyzed and, from the knowledge gained, an overall evaluation of the complex chemical system representing the product is made. The virtual Product...... in the software library, they need to be developed and/or implemented. The potential of the virtual PPD-lab in managing the complexity in the verification of formulated products, after the needed models have been developed and implemented, is highlighted in this paper through a case study from industry dealing...

  16. Final deactivation project report on the Integrated Process Demonstration Facility, Building 7602 Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-09-01

    The purpose of this report is to document the condition of the Integrated Process Demonstration Facility (Building 7602) at Oak Ridge National Laboratory (ORNL) after completion of deactivation activities by the High Ranking Facilities Deactivation Project (HRFDP). This report identifies the activities conducted to place the facility in a safe and environmentally sound condition prior to transfer to the U.S. Department of Energy (DOE) Environmental Restoration EM-40 Program. This report provides a history and description of the facility prior to commencing deactivation activities and documents the condition of the building after completion of all deactivation activities. Turnover items, such as the Post-Deactivation Surveillance and Maintenance (S ampersand M) Plan, remaining hazardous and radioactive materials inventory, radiological controls, Safeguards and Security, and supporting documentation provided in the Office of Nuclear Material and Facility Stabilization Program (EM-60) Turnover package are discussed

  17. Robofurnace: A semi-automated laboratory chemical vapor deposition system for high-throughput nanomaterial synthesis and process discovery

    International Nuclear Information System (INIS)

    Oliver, C. Ryan; Westrick, William; Koehler, Jeremy; Brieland-Shoultz, Anna; Anagnostopoulos-Politis, Ilias; Cruz-Gonzalez, Tizoc; Hart, A. John

    2013-01-01

    Laboratory research and development on new materials, such as nanostructured thin films, often utilizes manual equipment such as tube furnaces due to its relatively low cost and ease of setup. However, these systems can be prone to inconsistent outcomes due to variations in standard operating procedures and limitations in performance such as heating and cooling rates restrict the parameter space that can be explored. Perhaps more importantly, maximization of research throughput and the successful and efficient translation of materials processing knowledge to production-scale systems, relies on the attainment of consistent outcomes. In response to this need, we present a semi-automated lab-scale chemical vapor deposition (CVD) furnace system, called “Robofurnace.” Robofurnace is an automated CVD system built around a standard tube furnace, which automates sample insertion and removal and uses motion of the furnace to achieve rapid heating and cooling. The system has a 10-sample magazine and motorized transfer arm, which isolates the samples from the lab atmosphere and enables highly repeatable placement of the sample within the tube. The system is designed to enable continuous operation of the CVD reactor, with asynchronous loading/unloading of samples. To demonstrate its performance, Robofurnace is used to develop a rapid CVD recipe for carbon nanotube (CNT) forest growth, achieving a 10-fold improvement in CNT forest mass density compared to a benchmark recipe using a manual tube furnace. In the long run, multiple systems like Robofurnace may be linked to share data among laboratories by methods such as Twitter. Our hope is Robofurnace and like automation will enable machine learning to optimize and discover relationships in complex material synthesis processes

  18. Robofurnace: A semi-automated laboratory chemical vapor deposition system for high-throughput nanomaterial synthesis and process discovery

    Energy Technology Data Exchange (ETDEWEB)

    Oliver, C. Ryan; Westrick, William; Koehler, Jeremy; Brieland-Shoultz, Anna; Anagnostopoulos-Politis, Ilias; Cruz-Gonzalez, Tizoc [Department of Mechanical Engineering, University of Michigan, Ann Arbor, Michigan 48109 (United States); Hart, A. John, E-mail: ajhart@mit.edu [Department of Mechanical Engineering, University of Michigan, Ann Arbor, Michigan 48109 (United States); Department of Mechanical Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States)

    2013-11-15

    Laboratory research and development on new materials, such as nanostructured thin films, often utilizes manual equipment such as tube furnaces due to its relatively low cost and ease of setup. However, these systems can be prone to inconsistent outcomes due to variations in standard operating procedures and limitations in performance such as heating and cooling rates restrict the parameter space that can be explored. Perhaps more importantly, maximization of research throughput and the successful and efficient translation of materials processing knowledge to production-scale systems, relies on the attainment of consistent outcomes. In response to this need, we present a semi-automated lab-scale chemical vapor deposition (CVD) furnace system, called “Robofurnace.” Robofurnace is an automated CVD system built around a standard tube furnace, which automates sample insertion and removal and uses motion of the furnace to achieve rapid heating and cooling. The system has a 10-sample magazine and motorized transfer arm, which isolates the samples from the lab atmosphere and enables highly repeatable placement of the sample within the tube. The system is designed to enable continuous operation of the CVD reactor, with asynchronous loading/unloading of samples. To demonstrate its performance, Robofurnace is used to develop a rapid CVD recipe for carbon nanotube (CNT) forest growth, achieving a 10-fold improvement in CNT forest mass density compared to a benchmark recipe using a manual tube furnace. In the long run, multiple systems like Robofurnace may be linked to share data among laboratories by methods such as Twitter. Our hope is Robofurnace and like automation will enable machine learning to optimize and discover relationships in complex material synthesis processes.

  19. A unique laboratory test rig reduces the need for offshore tests to combat calcium naphthenate deposition in oilfield process equipment.

    Energy Technology Data Exchange (ETDEWEB)

    Mediaas, Heidi; Grande, Knut; Hustad, Britt-Marie; Hoevik, Kim Reidar; Kummernes, Hege; Nergaard, Bjoern; Vindstad, Jens Emil

    2006-03-15

    Producing and refining high-TAN crude oils introduces a number of challenges, among which calcium naphthenate deposition in process facilities is the most serious production issue. Until recently, the only option for studying chemicals and process parameters in order to prevent naphthenate deposition has been field tests. Statoil has now developed a small scale pilot plant where these experiments can be performed in the laboratory at Statoil's Research and Technology Center in Trondheim, Norway. The results from the pilot plant are in full agreement with the extensive naphthenate experience obtained from almost 9 years operation of the Heidrun oilfield. The design and operational procedures for this test facility are based on the recent discovery by Statoil and ConocoPhillips of the ARN acid. The ARN acid is a prerequisite for calcium naphthenate deposition. The new continuous flow pilot plant, the Naphthenate Rig, is used to develop new environmental friendly naphthenate inhibitors and to optimize process operating conditions. Since it operates on real crudes the need for field tests in qualifying new naphthenate inhibitors is reduced. To the best of our knowledge, the rig is the first of its kind in the world. (Author)

  20. Risk-based analysis for prioritization and processing in the Los Alamos National Laboratory 94-1 program

    International Nuclear Information System (INIS)

    Boerigter, S.T.; DeMuth, N.S.; Tietjen, G.

    1996-10-01

    A previous report, open-quotes Analysis of LANL Options for Processing Plutonium Legacy Materials,close quotes LA-UR-95-4301, summarized the development of a risk-based prioritization methodology for the Los Alamos National Laboratory (LANL) Plutonium Facility at Technical Area-55 (TA-55). The methodology described in that report was developed not only to assist processing personnel in prioritizing the remediation of legacy materials but also to evaluate the risk impacts of schedule modifications and changes. Several key activities were undertaken in the development of that methodology. The most notable was that the risk assessments were based on statistically developed data from sampling containers in the vault and evaluating their condition; the data from the vault sampling programs were used as the basis for risk estimates. Also, the time-dependent behavior of the legacy materials was explicitly modeled and included in the risk analysis. The results indicated that significant reductions in program risk can be achieved by proper prioritization of the materials for processing