Auxiliary/Master microprocessor CAMAC Crate Controller applications

International Nuclear Information System (INIS)

Barsotti, E.

1975-01-01

The need for further sophistication of an already complex serial CAMAC control system at Fermilab led to the development of an Auxilary/Master CAMAC Crate Controller. The controller contains a Motorola 6800 microprocessor, 2K bytes of RAM, and 8K bytes of PROM memory. Bussed dataway lines are time shared with CAMAC signals to provide memory expansion and direct addressing of peripheral devices without the need of external cabling. The Auxiliary/Master Crate Controller (A/MCC) can function as either a Master, i.e., stand alone, crate controller or as an Auxiliary controller to Fermilab's Serial Crate Controller (SCC). Two modules, one single- and one double-width, make up an A/MCC. The microprocessor has one nonmaskable and one maskable vectored interrupt. Time sharing the dataway between SCC programmed and block transfer generated dataway cycles and A/MCC operations still allows a 99 percent microprocessor CPU busy time. Since the conception of the A/MCC, there has been an increasing number of control system-related projects proposed which would not have been possible or would have been very difficult to implement without such a device. The first such application now in use at Fermilab is a stand-alone control system for a mass spectrometer experiment in the Main Ring Internal Target Area. This application in addition to other proposed A/MCC applications, both stand-alone and auxiliary, is discussed

Method for assay of radioactivity in waste soil

International Nuclear Information System (INIS)

Bramlitt, E.T.; Willhoite, S.B.

1991-01-01

Contaminated soil is a result of many nuclear operations. During facility decommissioning or site cleanup, it may be packaged for disposal. The waste soil must be assayed for contaminants to follow transport regulations and waste handling facility requirements. Methods used for assay include the following: (1) sampling the ground before excavation and assuming ground data apply to soil when packaged; (2) analyzing samples taken from the soil added to a package; (3) counting radiation at the exterior of the package; and (4) measuring neutron absorption by packaged waste soil. The Defense Nuclear Agency (DNA) worked with Eberline Instruments Corporation (EIC) to develop an automated assay method for the waste stream in a plutonium-contaminated soil cleanup at Johnston Atoll in the North Pacific Ocean. The perfected method uses a personal computer, an electronic weighing scale, and a programmable radiation counter. Computer programs get weight and radiation counts at frequent intervals as packages fill, calculate activity in the waste, and produce reports. The automated assay method is an efficient one-person routine that steadfastly collects data and produces a comprehensive record on packaged waste

Nondestructive radioassay for waste management: an assessment

Energy Technology Data Exchange (ETDEWEB)

Lehmkuhl, G.D.

1981-06-01

Nondestructive Assay (NDA) for Transuranic Waste Management is used to mean determining the amount of transuranic (TRU) isotopes in crates, drums, boxes, cans, or other containers without having to open the container. It also means determining the amount of TRU in soil, bore holes, and other environmental testing areas without having to go through extensive laboratory wet chemistry analyses. it refers to radioassay techniques used to check for contamination on objects after decontamination and to determine amounts of TRU in waste processing streams without taking samples to a laboratory. Gednerally, NDA instrumentation in this context refers to all use of radioassay which does not involve taking samples and using wet chemistry techniques. NDA instruments have been used for waste assay at some sites for over 10 years and other sites are just beginning to consider assay of wastes. The instrumentation used at several sites is discussed in this report. Almost all these instruments in use today were developed for special nuclear materials safeguards purposes and assay TRU waste down to the 500 nCi/g range. The need for instruments to assay alpha particle emitters at 10 nCi/g or less has risen from the wish to distinguish between Low Level Waste (LLW) and TRU Waste at the defined interface of 10 nCi/g. Wastes have historically been handled as TRU wastes if they were just suspected to be transuranically contaminated but their exact status was unknown. Economic and political considerations make this practice undesirable since it is easier and less costly to handle LLW. This prompted waste generators to want better instrumentation and led the Transuranic Waste Management Program to develop and test instrumentation capable of assaying many types of waste at the 10 nCi/g level. These instruments are discussed.

Low-Level Waste Drum Assay Intercomparison Study

International Nuclear Information System (INIS)

Greutzmacher, K.; Kuzminski, J.; Myers, S. C.

2003-01-01

Nuclear waste assay is an integral element of programs such as safeguards, waste management, and waste disposal. The majority of nuclear waste is packaged in drums and analyzed by various nondestructive assay (NDA) techniques to identify and quantify the radioactive content. Due to various regulations and the public interest in nuclear issues, the analytical results are required to be of high quality and supported by a rigorous Quality Assurance (QA) program. A valuable QA tool is an intercomparison program in which a known sample is analyzed by a number of different facilities. While transuranic waste (TRU) certified NDA teams are evaluated through the Performance Demonstration Program (PDP), low-level waste (LLW) assay specialists have not been afforded a similar opportunity. NDA specialists from throughout the DOE complex were invited to participate in this voluntary drum assay intercomparison study that was organized and facilitated by the Solid Waste Operations and the Safeguards Science and Technology groups at the Los Alamos National Laboratory and by Eberline Services. Each participating NDA team performed six replicate blind measurements of two 55-gallon drums with relatively low-density matrices (a 19.1 kg shredded paper matrix and a 54.4 kg mixed metal, rubber, paper and plastic matrix). This paper presents the results from this study, with an emphasis on discussing the lessons learned as well as desirable follow up programs for the future. The results will discuss the accuracy and precision of the replicate measurements for each NDA team as well as any issues that arose during the effort

Developments in plutonium waste assay at AWE

International Nuclear Information System (INIS)

Miller, T J

2009-01-01

In 2002 a paper was presented at the 43rd Annual Meeting of the Institute of Nuclear Materials Management (INMM) on the assay of low level plutonium (Pu) in soft drummed waste (Miller 2002 INMM Ann. Meeting (Orlando, FL, 23-27 July 2002)). The technique described enabled the Atomic Weapons Establishment (AWE), at Aldermaston in the UK, to meet the stringent Low Level Waste Repository at Drigg (LLWRD) conditions for acceptance for the first time. However, it was initially applied to only low density waste streams because it relied on measuring the relatively low energy (60 keV) photon yield from Am-241 during growth. This paper reviews the results achieved when using the technique to assay over 10 000 waste packages and presents the case for extending the range of application to denser waste streams.

Nondestructive assay of boxed radioactive waste

International Nuclear Information System (INIS)

Gilles, W.P.; Roberts, R.J.; Jasen, W.G.

1992-12-01

This paper describes the problems related to the nondestructive assay (NDA) of boxed radioactive waste at the Hanford Site and how Westinghouse Hanford company (WHC) is solving the problems. The waste form and radionuclide content are described. The characteristics of the combined neutron and gamma-based measurement system are described

Assessment of the Microscreen phage-induction assay for screening hazardous wastes

Energy Technology Data Exchange (ETDEWEB)

Houk, V.S.; DeMarini, D.M.

1987-09-01

The Microscreen phage-induction assay, which quantitatively measures the induction of prophage lambda in Escherichia coli WP2s(lambda), was used to test 14 crude (unfractionated) hazardous industrial waste samples for genotoxic activity in the presence and absence of metabolic activation. Eleven of the 14 wastes induced prophage, and induction was observed at concentrations as low as 0.4 picograms per ml. Comparisons between the mutagenicity of these waste samples in Salmonella and their ability to induce prophage lambda indicate that the Microscreen phage-induction assay detected genotoxic activity in all but one of the wastes that were mutagenic in Salmonella. Moreover, the Microscreen assay detected as genotoxic 5 additional wastes that were not detected in the Salmonella assay. The applicability of the Microscreen phage-induction assay for screening hazardous wastes for genotoxic activity is discussed along with some of the problems associated with screening highly toxic wastes containing toxic volatile compounds.

MCNP efficiency calculations of INEEL passive active neutron assay system for simulated TRU waste assays

International Nuclear Information System (INIS)

Yoon, W.Y.; Meachum, T.R.; Blackwood, L.G.; Harker, Y.D.

2000-01-01

The Idaho National Engineering and Environmental Laboratory Stored Waste Examination Pilot Plant (SWEPP) passive active neutron (PAN) radioassay system is used to certify transuranic (TRU) waste drums in terms of quantifying plutonium and other TRU element activities. Depending on the waste form involved, significant systematic and random errors need quantification in addition to the counting statistics. To determine the total uncertainty of the radioassay results, a statistical sampling and verification approach has been developed. In this approach, the total performance of the PAN nondestructive assay system is simulated using the computer models of the assay system, and the resultant output is compared with the known input to assess the total uncertainty. The supporting steps in performing the uncertainty analysis for the passive assay measurements in particular are as follows: (1) Create simulated waste drums and associated conditions; (2) Simulate measurements to determine the basic counting data that would be produced by the PAN assay system under the conditions specified; and (3) Apply the PAN assay system analysis algorithm to the set of counting data produced by simulating measurements to determine the measured plutonium mass. The validity of this simulation approach was verified by comparing simulated output against results from actual measurements using known plutonium sources and surrogate waste drums. The computer simulation of the PAN system performance uses the Monte Carlo N-Particle (MCNP) Code System to produce a neutron transport calculation for a simulated waste drum. Specifically, the passive system uses the neutron coincidence counting technique, utilizing the spontaneous fission of 240 Pu. MCNP application to the SWEPP PAN assay system uncertainty analysis has been very useful for a variety of waste types contained in 208-ell drums measured by a passive radioassay system. The application of MCNP to the active radioassay system is also feasible

Hi-speed versatile serial crate controller for CAMAC

International Nuclear Information System (INIS)

Horelick, D.

1984-10-01

A serial crate controller, primarily for use in the SLC CAMAC control system, has been designed, and has been in use for about 2 years. The design supports a party line approach, with up to 16 crates on a single twisted pair for data transfers, plus another pair for prompt L response. The bit rate is 5 megabits/s, and complete transaction times of about 10 μs are achieved for 16-bit data transfers over cables up to 1000 feet long. One of the primary objects of the design was simplicity - there are approximately 60 chips in the two-board unit

Assessment of the microscreen phage-induction assay for screening hazardous wastes (1989)

Energy Technology Data Exchange (ETDEWEB)

Houk, V.S.; DeMarini, D.M.

1989-01-01

The Microscreen phage-induction assay, which quantitatively measures the induction of prophage Lambda in Escherichia coli WP2s(Lambda), was used to test 14 crude (unfractionated) hazardous industrial-waste samples for genotoxic activity in the presence and absence of metabolic activation. Eleven of the 14 wastes induced prophage, and induction was observed at concentrations as low as 0.4 picograms per ml. Comparisons of the mutagenic activity of these waste samples in Salmonella and their ability to induce prophage Lambda indicate that the phage-induction assay was a more-sensitive indicator of genetic damage for this group of wastes. All but one of the wastes that were mutagenic to Salmonella were detected by the phage-induction assay, and 5 wastes not mutagenic to Salmonella were genetically active in the phage assay. The enhanced ability of the phage-induction assay to detect genotoxic activity may be related to the constituents comprising these waste samples. Partial chemical characterizations of the wastes showed high concentrations of carcinogenic metals, solvents, and chlorinated compounds, most of which are detected poorly by the Salmonella assay.

The assay of encapsulated alpha-bearing waste: feasibility study

International Nuclear Information System (INIS)

Curry, R.G.

1983-09-01

This report contains a review of potentially applicable techniques for the determination of actinide isotopes in radioactive waste and a summary of results obtained with various prototype instruments. A schematic design of a complete assay station is derived with consideration given to practical aspects like remote handling, maintenance etc. and recommendations for further work are made. The place of waste assay in the overall quality assurance of packaged waste is also considered. (author)

Radioactive waste package assay facility. Volume 1. Application of assay technology

International Nuclear Information System (INIS)

Findlay, D.J.S.; Green, T.H.; Molesworth, T.V.; Staniforth, D.; Strachan, N.R.; Rogers, J.D.; Wise, M.O.; Forrest, K.R.

1992-01-01

This report, in three volumes, covers the work carried out by Taylor Woodrow Construction Ltd., and two major sub-contractors: Harwell Laboratory (AEA Technology) and Siemens Plessey Controls Ltd., on the development of a radioactive waste package assay facility, for cemented 500 litre intermediate level waste drums. In volume 1, the reasons for assay are considered together with the various techniques that can be used, and the information that can be obtained. The practical problems associated with the use of the various techniques in an integrated assay facility are identified, and the key parameters defined. Engineering and operational features are examined and provisional designs proposed for facilities at three throughput levels: 15,000, 750 and 30 drums per year respectively. The capital and operating costs for such facilities have been estimated. A number of recommendations are made for further work. 16 refs., 14 figs., 13 tabs

Expert system technology for nondestructive waste assay

International Nuclear Information System (INIS)

Becker, G.K.; Determan, J.C.

1998-01-01

Nondestructive assay waste characterization data generated for use in the National TRU Program must be of known and demonstrable quality. Each measurement is required to receive an independent technical review by a qualified expert. An expert system prototype has been developed to automate waste NDA data review of a passive/active neutron drum counter system. The expert system is designed to yield a confidence rating regarding measurement validity. Expert system rules are derived from data in a process involving data clustering, fuzzy logic, and genetic algorithms. Expert system performance is assessed against confidence assignments elicited from waste NDA domain experts. Performance levels varied for the active, passive shielded, and passive system assay modes of the drum counter system, ranging from 78% to 94% correct classifications

CC-3 CAMAC crate controller for IBM PC

International Nuclear Information System (INIS)

Khare, A.N.; Ghodgaonkar, M.D.; Bairi, B.R.

1991-01-01

The specifications and implementation details of CAMAC Crate Controller CC-3 for IBM-PC compatible as a host computer, having capability to transfer high speed data with direct memory access (DMA) scheme and logic to execute CAMAC cycles directly from the crate controller, to implement the block algorithms specified in ANSI/IEEE Std. 683-1976 (Reaff-1981) are described. The maximum data transfer rate measured with 8 bit interface of PC-AT is 240K byte per second. This work is carried out under Seventh Five Year Plan Project on Modernisation of reactor Control Instrumentation and Development of CAMAC and Fastbus Instrumentation. (author). 9 refs., 5 figs., 4 appendixes

Esculturas de Hipócrates, Galeno y Manuel Plata Azuero

Directory of Open Access Journals (Sweden)

Alberto Albornoz Plata

1996-08-01

Full Text Available

Dos agradables y emotivas sorpresas hemos experimentado en la tarde de hoy:

Bellas obras de arte son las esculturas de Hipócrates y Galeno, que parecen saludar a todos los visitantes de la Academia al penetrar al salón principal. Por eso he querido recordar brevemente lo que estos personajes representan en la historia de la Medicina mundial y nacional.

I. Hipócrates.

Hipócrates.Nació en la isla griega de Cos, en el mar Egeo, en el año 4,60 A.c. Estudió medicina en Selymbria y sus maestros fueron Gorgias de Leontini y Demócrates. Muere en Tesalia a los 85 años. Fue muy distinguido por Platón y Aristóteles y es considerado universalmente como el Padre de la Medicina.

Laennec, el famoso clínico francés del siglo XIX, lo consideró como genial por haber descrito tanto la sucusión torácica como la facies de los moribundos: ambas, en su honor, llevan el calificativo de “hipocráticas”. Hipócrates sostenía que la misma naturaleza cura las enfermedades. El “Corpus Hipocraticum”, que llegó hasta el Renacimiento por vía de los romanos y de los árabes, compendia el conocimiento médico de toda la antigüedad.

El Juramento Hipocrático es su gran legado para los médicos: todos nosotros hemos prometido cumplirlo fielmente...

Performance validation of commercially available mobile waste-assay systems: Preliminary report

International Nuclear Information System (INIS)

Schanfein, M.; Bonner, C.; Maez, R.

1997-01-01

Prior to disposal, nuclear waste must be accurately characterized to identify and quantify the radioactive content to reduce the radioactive hazard to the public. Validation of the waste-assay systems' performance is critical for establishing the credibility of the assay results for storage and disposal purposes. Canberra Nuclear has evaluated regulations worldwide and identified standard, modular, neutron- and gamma-waste-assay systems that can be used to characterize a large portion of existing and newly generated transuranic (TRU) and low-level waste. Before making claims of guaranteeing any system's performance for specific waste types, the standardized systems' performance be evaluated. 7 figs., 11 tabs

Performance validation of commercially available mobile waste-assay systems: Preliminary report

Energy Technology Data Exchange (ETDEWEB)

Schanfein, M.; Bonner, C.; Maez, R. [Los Alamos National Lab., NM (United States)] [and others

1997-11-01

Prior to disposal, nuclear waste must be accurately characterized to identify and quantify the radioactive content to reduce the radioactive hazard to the public. Validation of the waste-assay systems` performance is critical for establishing the credibility of the assay results for storage and disposal purposes. Canberra Nuclear has evaluated regulations worldwide and identified standard, modular, neutron- and gamma-waste-assay systems that can be used to characterize a large portion of existing and newly generated transuranic (TRU) and low-level waste. Before making claims of guaranteeing any system`s performance for specific waste types, the standardized systems` performance be evaluated. 7 figs., 11 tabs.

Rover waste assay system

International Nuclear Information System (INIS)

Akers, D.W.; Stoots, C.M.; Kraft, N.C.; Marts, D.J.

1997-01-01

The Rover Waste Assay System (RWAS) is a nondestructive assay system designed for the rapid assay of highly-enriched 235 U contaminated piping, tank sections, and debris from the Rover nuclear rocket fuel processing facility at the Idaho Chemical Processing Plant. A scanning system translates a NaI(Tl) detector/collimator system over the structural components where both relative and calibrated measurements for 137 Cs are made. Uranium-235 concentrations are in operation and is sufficiently automated that most functions are performed by the computer system. These functions include system calibration, problem identification, collimator control, data analysis, and reporting. Calibration of the system was done through a combination of measurements on calibration standards and benchmarked modeling. A description of the system is presented along with the methods and uncertainties associated with the calibration and analysis of the system for components from the Rover facility. 4 refs., 2 figs., 4 tabs

A CAMAC crate controller KK009 for the Pravetz-16 and IBM PC/XT personal computers

International Nuclear Information System (INIS)

Georgiev, A.; Churin, I.N.

1988-01-01

A CAMAC crate controller and a computer bus adapter for the Pravetz 16 and IBM PC/XT personal computers are described. The following features are included in the controller: operation under program control; access to CAMAC registers treated as memory locations corresponding to given N, A, F; hardware for fast LAM processing and execution of multi-crate commands; device up to 7 crates in one CAMAC system; built-in hardware for controller and crate dataway test

Ageing and recycling of plastic crates

NARCIS (Netherlands)

Vink, P.; Rotteveel, R.T.; Wisse, J.D.M.

1985-01-01

Plastic crates will deteriorate and ultimately fail due to brittle fracture if, either during use or storage, they are exposed to sunlight. The time to failure depends on the UV stability of the polymer used, but in particular also on the conditions of use, such as time of exposure, height of the

Rover waste assay system

Energy Technology Data Exchange (ETDEWEB)

Akers, D.W.; Stoots, C.M.; Kraft, N.C.; Marts, D.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1997-11-01

The Rover Waste Assay System (RWAS) is a nondestructive assay system designed for the rapid assay of highly-enriched {sup 235}U contaminated piping, tank sections, and debris from the Rover nuclear rocket fuel processing facility at the Idaho Chemical Processing Plant. A scanning system translates a NaI(Tl) detector/collimator system over the structural components where both relative and calibrated measurements for {sup 137}Cs are made. Uranium-235 concentrations are in operation and is sufficiently automated that most functions are performed by the computer system. These functions include system calibration, problem identification, collimator control, data analysis, and reporting. Calibration of the system was done through a combination of measurements on calibration standards and benchmarked modeling. A description of the system is presented along with the methods and uncertainties associated with the calibration and analysis of the system for components from the Rover facility. 4 refs., 2 figs., 4 tabs.

Radioactive waste package assay facility. Volume 3. Data processing

International Nuclear Information System (INIS)

Creamer, S.C.; Lalies, A.A.; Wise, M.O.

1992-01-01

This report, in three volumes, covers the work carried out by Taylor Woodrow Construction Ltd, and two major sub-contractors: Harwell Laboratory (AEA Technology) and Siemens Plessey Controls Ltd, on the development of a radioactive waste package assay facility, for cemented 500 litre intermediate level waste drums. Volume 3, describes the work carried out by Siemens Plessey Controls Ltd on the data-processing aspects of an integrated waste assay facility. It introduces the need for a mathematical model of the assay process and develops a deterministic model which could be tested using Harwell experimental data. Relevant nuclear reactions are identified. Full implementation of the model was not possible within the scope of the Harwell experimental work, although calculations suggested that the model behaved as predicted by theory. 34 figs., 52 refs., 5 tabs

Sòcrates l'impenetrable i l'amor platònic

OpenAIRE

Pàmias i Massana, Jordi

2013-01-01

Un investigador de la UAB ha publicat un article en què es reinterpreta un passatge del diàleg El Banquet de Plató per establir que la fortalesa del filòsof Sòcrates radica en la seva capacitat de resistir la seducció. Així, Sòcrates coneix el desig, però només l'exerceix quan es tracta de veritable amor. Aquesta nova interpretació permet apropar-nos al nucli de la doctrina de l'amor platònic.

West Valley Demonstration Project low-level and transuranic waste assay and methodology

International Nuclear Information System (INIS)

McVay, C.W.

1987-03-01

In the decontamination and decommissioning of the West Valley Nuclear Facility, waste materials are being removed and packaged in a variety of waste containers which require classification in accordance with USNRC 10 CFR 61 and DOE 5820.2 criteria. Low-Level and Transuranic waste assay systems have been developed to efficiently assay and classify the waste packages. The waste is assayed by segmented gamma scanning, passive neutron techniques, dose rate conversion, and/or radiochemical laboratory analysis. The systems are capable of handling all the waste forms currently packaged as part of the Project. The above systems produce a list of nuclides present with their concentrations and determines the classification of the waste packages based on criteria outlined in DOE Order 5820.2 and USNRC 10 CFR 61.55. 9 refs., 12 figs., 8 tabs

Evalution of NDA techniques and instruments for assay of nuclear waste at a waste terminal storage facility

International Nuclear Information System (INIS)

Blakeman, E.D.; Allen, E.J.; Jenkins, J.D.

1978-05-01

The use of Nondestructive Assay (NDA) instrumentation at a nuclear waste terminal storage facility for purposes of Special Nuclear Material (SNM) accountability is evaluated. Background information is given concerning general NDA techniques and the relative advantages and disadvantages of active and passive NDA methods are discussed. The projected characteristics and amounts of nuclear wastes that will be delivered to a waste terminal storage facility are presented. Wastes are divided into four categories: High Level Waste, Cladding Waste, Intermediate Level Waste, and Low Level Waste. Applications of NDA methods to the assay of these waste types is discussed. Several existing active and passive NDA instruments are described and, where applicable, results of assays performed on wastes in large containers (e.g., 55-gal drums) are given. It is concluded that it will be difficult to routinely achieve accuracies better than approximately 10--30% with ''simple'' NDA devices or 5--20% with more sohpisticated NDA instruments for compacted wastes. It is recommended that NDA instruments not be used for safeguards accountability at a waste storage facility. It is concluded that item accountability methods be implemented. These conclusions and recommendations are detailed in a concurrent report entitled ''Recommendations on the Safeguards Requirements Related to the Accountability of Special Nuclear Material at Waste Terminal Storage Facilities'' by J.D. Jenkins, E.J. Allen and E.D. Blakeman

Neutron and gamma-ray nondestructive examination of contact-handled transuranic waste at the ORNL TRU Waste Drum Assay Facility

International Nuclear Information System (INIS)

Schultz, F.J.; Coffey, D.E.; Norris, L.B.; Haff, K.W.

1985-03-01

A nondestructive assay system, which includes the Neutron Assay System (NAS) and the Segmented Gamma Scanner (SGS), for the quantification of contact-handled (<200 mrem/h total radiation dose rate at contact with container) transuranic elements (CH-TRU) in bulk solid waste contained in 208-L and 114-L drums has been in operation at the Oak Ridge National Laboratory since April 1982. The NAS has been developed and demonstrated by Los Alamos National Laboratory (LANL) and the Oak Ridge National Laboratory (ORNL) for use by most US Department of Energy Defense Plant (DOE-DP) sites. More research and development is required, however, before the NAS can provide complete assay results for other than routine defense waste. To date, 525 ORNL waste drums have been assayed, with varying degrees of success. The isotopic complexity of the ORNL waste creates a correspondingly complex assay problem. The NAS and SGS assay data are presented and discussed. Neutron matrix effects, the destructive examination facility, and enriched uranium fuel-element assays are also discussed

A comparative analysis of lumbar spine mechanics during barbell- and crate-lifting: implications for occupational lifting task assessments.

Science.gov (United States)

Zehr, Jackie D; Carnegie, Danielle R; Welsh, Timothy N; Beach, Tyson A C

2018-03-19

To compare the effects of object handled and handgrip used on lumbar spine motion and loading during occupational lifting task simulations. Eight male and eight female volunteers performed barbell and crate lifts with a pronated (barbell) and a neutral (crate) handgrip. The mass of barbells/crates lifted was identical across the objects and fixed at 11.6 and 9.3 kg for men and women, respectively. The initial heights of barbells/crates were individualized to mid-shank level. Body segment kinematics and foot-ground reaction kinetics were collected, and then input into an electromyography-assisted dynamic biomechanical model to quantify lumbar spine motion and loading. Lumbar compression and net lumbosacral moment magnitudes were 416 N and 17 Nm lower when lifting a barbell than when lifting a crate (p  0.392) or flexion/extension velocities (p > 0.085). Crate- and barbell-lifting tasks can be used interchangeably if assessing lifting mechanics based on peak spine motion variables. If assessments are based on the spine loading responses to task demands, however, then crate- and barbell-lifting tasks cannot be used interchangeably.

Multi-isotopic gamma-ray assay system for alpha-contaminated waste

International Nuclear Information System (INIS)

Close, D.A.; Pratt, J.C.; Caldwell, J.T.; Kunz, W.E.; Schultz, F.J.; Haff, K.W.

1983-01-01

The capability of an existing segmented gamma-ray system is being expanded for the analysis of alpha-contaminated waste drums. A cursory assay of 114 transuranic waste drums of 208-l capacity has been made. Analysis of these data indicates a detection limit better than 100 nCi/g of waste for 237 Np/ 233 Pa, 239 Pu, 241 Am, 243 Am/ 239 Np, 60 Co, 125 Sb, 134 137 Cs, and 154 Eu. A pending Code of Federal Regulation (10CFR61) stipulates that the nuclear industry quantify not only its transuranic waste, but also certain beta- and gamma-ray-emitting fission products. An assay system based on gamma-ray spectroscopy is the only system that can meet this requirement for the fission products

The effect of crate height on the behavior of female turkeys during commercial pre-slaughter transportation.

Science.gov (United States)

Di Martino, Guido; Capello, Katia; Stefani, Anna Lisa; Tripepi, Luca; Garbo, Angelica; Speri, Marina; Trolese, Matteo; Brichese, Michele; Marangon, Stefano; Bonfanti, Lebana

2017-10-01

Limited information is available on suitable height of transport crates for turkeys. We compared behaviors and physiological indicators of four groups of 10 female turkeys each confined in either conventional (38.5 cm height) or experimental (77 cm height) crates during six commercial pre-slaughter transportations for 86 km (76 ± 4 min) along two tracts with one-lane streets, crossroads, bends, roundabouts (S1 and S2) and a highway tract (H) between S1 and S2. Only 36% of birds in the higher crates maintained a standing position. In conventional versus experimental crates, the frequency of rising attempts was five/bird/hour versus less than one/bird/hour, while wing flapping was seven/bird/hour versus 20/bird/hour, and balance loss was one versus four/bird/hour. The behaviors of both groups differed significantly according to the route tract, with a lower frequency of stress-related behaviors at H. No scratches, fractures or hematomas were detected in any birds after transportation. Crate height had no significant effect on hemato-biochemical markers. These results suggest that crates enabling a standing position may increase potentially dangerous behaviors. Moreover, busy and curvy routes should be avoided, as they may contribute to increasing the frequency of stress-related behaviors. © 2017 Japanese Society of Animal Science.

Use of the CAMAC-MULTIBUS combined protocol for organizing multi-processor operation in a crate

International Nuclear Information System (INIS)

Glejbman, Eh.M.

1985-01-01

Problems of developing electronic units for large on-line systems for nuclear-physical experiments automation and developed on the base of principles of distributed control and data processing are discussed. Crates with simultaneous disposition and operation of CAMAC moduli (EUR-4100) and those realizing the MULTIBUS hardcopy log in dataway are described. It is attained due to sharing the CAMAC and the MULTIBUS hardcopy logs in the crate dataway. Application of job scheduler and executor moduli in the MULTIBUS interface permits to organize multiprocessor operation and to obtain separation of data stream as well as to increase total computational capacity in the crate

Development of a numerical experiment technique to solve inverse gamma-ray transport problems with application to nondestructive assay of nuclear waste barrels

International Nuclear Information System (INIS)

Chang, C.J.; Anghaie, S.

1998-01-01

A numerical experimental technique is presented to find an optimum solution to an undetermined inverse gamma-ray transport problem involving the nondestructive assay of radionuclide inventory in a nuclear waste drum. The method introduced is an optimization scheme based on performing a large number of numerical simulations that account for the counting statistics, the nonuniformity of source distribution, and the heterogeneous density of the self-absorbing medium inside the waste drum. The simulation model uses forward projection and backward reconstruction algorithms. The forward projection algorithm uses randomly selected source distribution and a first-flight kernel method to calculate external detector responses. The backward reconstruction algorithm uses the conjugate gradient with nonnegative constraint or the maximum likelihood expectation maximum method to reconstruct the source distribution based on calculated detector responses. Total source activity is determined by summing the reconstructed activity of each computational grid. By conducting 10,000 numerical simulations, the error bound and the associated confidence level for the prediction of total source activity are determined. The accuracy and reliability of the simulation model are verified by performing a series of experiments in a 208-ell waste barrel. Density heterogeneity is simulated by using different materials distributed in 37 egg-crate-type compartments simulating a vertical segment of the barrel. Four orthogonal detector positions are used to measure the emerging radiation field from the distributed source. Results of the performed experiments are in full agreement with the estimated error and the confidence level, which are predicted by the simulation model

Nondestructive assay of TRU waste using gamma-ray active and passive computed tomography

International Nuclear Information System (INIS)

Roberson, G.P.; Decman, D.; Martz, H.; Keto, E.R.; Johansson, E.M.

1995-01-01

The authors have developed an active and passive computed tomography (A and PCT) scanner for assaying radioactive waste drums. Here they describe the hardware components of their system and the software used for data acquisition, gamma-ray spectroscopy analysis, and image reconstruction. They have measured the performance of the system using ''mock'' waste drums and calibrated radioactive sources. They also describe the results of measurements using this system to assay a real TRU waste drum with relatively low Pu content. The results are compared with X-ray NDE studies of the same TRU waste drum as well as assay results from segmented gamma scanner (SGS) measurements

Use of the microscreen phage-induction assay to assess the genotoxicity of 14 hazardous industrial wastes

Energy Technology Data Exchange (ETDEWEB)

Houk, V.S.; DeMarini, D.M.

1988-01-01

The Microscreen phage-induction assay, which quantitatively measures the induction of prophage lambda in Escherichia coli WP2s(lambda), was used to test 14 crude (unfractionated) hazardous industrial waste samples for genotoxic activity in the presence and absence of metabolic activation. Eleven of the 14 wastes induced prophage, and induction was observed at concentrations as low as 0.4 pg per ml. Comparisons between the ability of these waste samples to induce prophage and their mutagenicity in the Salmonella reverse mutation assay indicate that the phage-induction assay detected genotoxic activity in all but one of the wastes that were mutagenic in Salmonella. Moreover, the Microscreen assay detected as genotoxic five additional wastes that were not detected in the Salmonella assay. The applicability of the Microscreen phage-induction assay for screening hazardous wastes for genotoxic activity is discussed, as are some of the problems associated with screening highly toxic wastes containing toxic volatile compounds.

Independent programmable CAMAC crate controller based on KR580IK80A microprocessor

International Nuclear Information System (INIS)

Kulik, O.V.; Andronov, M.A.

1986-01-01

The RTKAM-2 independent programmable CAMAC crate controller is designed for use as a remote terminal in systems for automation of physics research. The built-in 12K-byte RAM is automatically changed to 24-bit organization in exchanges with the crate dataway. A nonstandard 24-level priority-interrupt system allows an LAM-request routing to be accessed in 5.5 μsec. Communication with the base computer is through a two conductor line

TRU waste-assay instrumentation and application in nuclear-facility decommissioning

International Nuclear Information System (INIS)

Umbarger, C.J.

1982-01-01

The Los Alamos TRU waste assay program is developing measurement techniques for TRU and other radioactive waste materials generated by the nuclear industry, including decommissioning programs. Systems are now being fielded for test and evaluation purposes at DOE TRU waste generators. The transfer of this technology to other facilities and the commercial instrumentation sector is well in progress. 6 figures

Challenges of Non-Destructive Assay Waste Measurement

International Nuclear Information System (INIS)

Shull, A.H.

2003-01-01

Historically, the Savannah River Site (SRS) routinely produced special nuclear material (SNM), which provided stable measurement conditions for the non-destructive assay (NDA) methods. However, the main mission of SRS has changed from the production of SNM to the processing of waste and material stabilization. Currently, the purpose of processing is to recover the SNM from the waste and stabilization materials, much of which is from other DOE facilities. These missions are usually of a short duration, but require non-destructive assay (NDA) accountability measurements on materials of varying composition and geometric configuration. These missions usually have cost and time constraints, which sometimes require re-application of existing NDA methods to waste measurements. Usually, each new material or re-application of the NDA method to a different SNM campaign requires new standards and timely re-calibration of the method. These constraints provide numerous challenges for the NDA methods, particularly in the area of measurement uncertainty. This paper will discuss the challenges of these situations, mainly from a measurement and statistical point of view and provide some possible solutions to the problems encountered. Specific examples will be discussed for the segmented gamma scanner (SGS), neutron multiplicity counter (NMC) and passive neutron coincidence counter (PNCC), which are some of the most common NDA instruments at SRS

Application of neutron multiplicity counting to waste assay

Energy Technology Data Exchange (ETDEWEB)

Pickrell, M.M.; Ensslin, N. [Los Alamos National Lab., NM (United States); Sharpe, T.J. [North Carolina State Univ., Raleigh, NC (United States)

1997-11-01

This paper describes the use of a new figure of merit code that calculates both bias and precision for coincidence and multiplicity counting, and determines the optimum regions for each in waste assay applications. A {open_quotes}tunable multiplicity{close_quotes} approach is developed that uses a combination of coincidence and multiplicity counting to minimize the total assay error. An example is shown where multiplicity analysis is used to solve for mass, alpha, and multiplication and tunable multiplicity is shown to work well. The approach provides a method for selecting coincidence, multiplicity, or tunable multiplicity counting to give the best assay with the lowest total error over a broad spectrum of assay conditions. 9 refs., 6 figs.

Use of the Microscreen phage-induction assay to assess the genotoxicity of 14 hazardous industrial wastes

Energy Technology Data Exchange (ETDEWEB)

Houk, V.S.; DeMarini, D.M.

1988-01-01

The Microscreen phage-induction assay, which quantitatively measures the induction of prophage lambda in Escherichia coli WP2s lambda, was used to test 14 crude (unfractionated) hazardous industrial-waste samples for genotoxic activity in the presence and absence of metabolic activation. Eleven of the 14 wastes induced prophage, and induction was observed at concentrations as low as 0.4 picograms per ml. Comparisons between the mutagenicity of these waste samples in Salmonella and their ability to induce prophage lambda indicate that the Microscreen phage-induction assay detected genotoxic activity in all but one of the wastes that were mutagenic in Salmonella. Moreover, the Microscreen assay detected as genotoxic 5 additional wastes that were not detected in the Salmonella assay. The applicability of the Microscreen phage-induction assay for screening hazardous wastes for genotoxic activity is discussed along with some of the problems associated with screening highly toxic wastes containing toxic volatile compounds.

Application of PINS and GNAT to the assay of 55-gal containers of radioactive waste

International Nuclear Information System (INIS)

Gehrke, R.J.; Aryaeinejad, R.; Watts, K.D.; Staples, D.R.; Akers, D.W.

1994-03-01

The Portable Isotropic Neutron Spectroscopy (PINS) and Gamma Neutron Assay Technique (GNAT) assay systems that were developed with funding from the office of Research and Development (NN20), were taken to the Stored Waste Examination Pilot Plant (SWEPP) facility at the Radioactive Waste Management Complex (RWMC) and applied to the assay of surrogate and Rocky Flats Plant waste contained in 55-gal drums. PINS, a portable prompt γ neutron activation analysis technique, was able to identify key elements in both the surrogate and real waste so that three-main waste categories: metal, combustible material, and cemented chlorinated sludge wastes could be identified. GNAT, a γ, neutron assay technique for the identification and quantification of fissioning isotopes, was able to identify 240 Pu in surrogate waste in which nine 1-g nuclear accident dosimeters were inserted. GNAT was also able to identify 24O Pu in real 55-gal waste drums containing 15- and 40-g of plutonium even in the presence of high activity concentrations of 241 Am

Techniques for improving shuffler assay results for 55-gallon waste drums

International Nuclear Information System (INIS)

Rinard, P.M.; Prettyman, T.H.; Stuenkel, D.

1994-01-01

Accurate assays of the fissile contents in waste drums are needed to ensure the most proper and economical handling and disposal of the waste. An improvement of accuracy will mean fewer drums disposed as transuranic waste when they really contain low-level waste, saving both money and burial sites. Shufflers are used for assaying waste drums and are very accurate with nonmoderating matrices (such as iron). In the active mode they count delayed neutrons released after fissions are induced by irradiation neutrons from a 252 Cf source. However, as the hydrogen density from matrices such as paper or gloves increases, the accuracy can suffer without proper attention. The neutron transport and fission probabilities change with the hydrogen density, causing the neutron count rate to vary with the position of the fissile material within the drum. The magnitude of this variation grows with the hydrogen density

Plutonium assay of large waste burial containers at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Haggard, D.L.; Newman, D.F.

1987-01-01

As one phase of an upgrade program at one of the Battelle Pacific Northwest Laboratory facilities, two plutonium glovebox hoods were replaced. They were dismantled, packaged in plastic for contamination control, and loaded into waste burial boxes. All of the plutonium-contaminated waste material from the two glovebox hoods was placed into six stainless steel boxes with identification letters A through F. Boxes A through E have 104.8- x 196.2- x 119.4-cm i.d.'s. Box F has an i.d. of 154.9 x 266.7 x 192.4 cm. The loaded boxes were assayed for plutonium content using both neutron and gamma-ray techniques. The difference between the results were greater than anticipated. Because of the importance of accurate plutonium assay measurements, additional measurements of box contents were made using a variety of techniques and assumptions including downloading of boxes and measurement of individual packages. These measurements have shown that a far-field, gamma-ray assay of a loaded waste box usually provides adequate measurement of low-density plutonium content, such as that found in packages of plastic, cellulose, and clothing. Comparing the far-field assays of the loaded waste boxes to the quantities determined by the assays of the downloaded packages resulted in good agreement between the two methods for boxes with low attenuation. Based on these results, it was concluded that it was valid to use the far-field assay results for the boxes that were not downloaded

Intelligent CAMAC crate controller with CC-A2 functionality and VICbus interface

International Nuclear Information System (INIS)

Erven, W.; Holzer, J.; Kopp, H.; Loevenich, H.W.; Meiling, W.; Zwoll, K.; Bovier, J.; Re, G.; Worm, F.

1992-01-01

This paper reports that for nuclear physics experiments at the Julich Cooler Synchrotron COSY a data acquisition system is under development. With this background, and in order to enhance existing CAMAC systems, an intelligent CAMAC crate controller with CC-A2 functionality was developed. The main enhancement is the replacement of the Branch Highway with a new standard of inter-crate connection: the VICbus. The other highlights are: optional use of a Motorola 68030 microprocessor as CAMAC list-processor and optimization of CAMAC blocktransfers, optional Ethernet or Cheapernet connection. This controller is commercially available from CES, Geneva and called VCC 2117

Low-speed shredder and waste shreddability tests

International Nuclear Information System (INIS)

Darnell, G.R.; Aldrich, W.C.

1983-04-01

Most waste drums and large crates in the nuclear industry are or will be opened by hand, in gloveboxes, or with manipulators. The Transuranic Waste Treatment Facility (TWTF), which was being designed for the Idaho National Engineering Laboratory (INEL), was no exception. The TWTF's manipulator concept required 4 to 6 hours to open and route a crate or drum for further processing; a costly operation. An alternative method was sought. Four of the relatively new low-speed shredders were tested on simulated transuranic waste packaged in 55-gal drums and 4- x 4- x 4-ft boxes. Three of the shredders were capable of shredding these containers and their contents in 1 to 15 minutes. Two were able to shred typical TWTF waste to acceptable particle size. The test waste included concrete, 1/4-in. steel plate (carbon and stainless), 1-in. rebar, rock, glass, plastic, paper, cloth, wood, steel cable, chain, etc. The two shredders were able to shred drums even with unshreddable items inside; the unshreddable items lay on top for later recovery by a manipulator while the other waste was being shredded

Development of a Radioactive Waste Assay System

Energy Technology Data Exchange (ETDEWEB)

Kang, Duck Won; Song, Myung Jae; Shin, Sang Woon; Sung, Kee Bang; Ko, Dae Hach [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Kil Jeong; Park, Jong Mook; Jee, Kwang Yoong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-12-31

Nuclear Act of Korea requires the manifest of low and intermediate level radioactive waste generated at nuclear power plants prior to disposal sites.Individual history records of the radioactive waste should be contained the information about the activity of nuclides in the drum, total activity, weight, the type of waste. A fully automated nuclide analysis assay system, non-destructive analysis and evaluation system of the radioactive waste, was developed through this research project. For the nuclides that could not be analysis directly by MCA, the activities of the representative {gamma}-emitters(Cs-137, Co-60) contained in the drum were measured by using that system. Then scaling factors were used to calculate the activities of {alpha}, {beta}-emitters. Furthermore, this system can automatically mark the analysis results onto the drum surface. An automated drum handling system developed through this research project can reduce the radiation exposure to workers. (author). 41 refs., figs.

Transuranic waste assay instrumentation: new developments and directions at the Los Alamos Scientific Laboratory

Energy Technology Data Exchange (ETDEWEB)

Close, D.A.; Umbarger, C.J.; West, L.; Smith, W.J.; Cates, M.R.; Noel, B.W.; Honey, F.J.; Franks, L.A.; Pigg, J.L.; Trundle, A.S.

1978-01-01

The Los Alamos Scientific Laboratory is developing assay instrumentation for the quantitative analysis of transuranic materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. This also includes wastes generated in the decontamination and decommissioning of facilities and wastes generated during burial ground exhumation. The assay instrumentation will have a detection capability for the transuranics of less than 10 nCi of activity per gram of waste whenever practicable.

Transuranic waste assay instrumentation: new developments and directions at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Close, D.A.; Umbarger, C.J.; West, L.; Smith, W.J.; Cates, M.R.; Noel, B.W.; Honey, F.J.; Franks, L.A.; Pigg, J.L.; Trundle, A.S.

1978-01-01

The Los Alamos Scientific Laboratory is developing assay instrumentation for the quantitative analysis of transuranic materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. This also includes wastes generated in the decontamination and decommissioning of facilities and wastes generated during burial ground exhumation. The assay instrumentation will have a detection capability for the transuranics of less than 10 nCi of activity per gram of waste whenever practicable

Considerations for an active and passive scanner to assay nuclear waste drums

International Nuclear Information System (INIS)

Martz, H.E.; Azevedo, S.G.; Roberson, G.P.; Schneberk, D.J.; Koenig, Z.M.; Camp, D.C.

1990-01-01

Radioactive wastes are generated at many DOE laboratories, military facilities, fuel fabrication and enrichment plants, reactors, hospitals, and university research facilities. At all of these sites, wastes must be separated, packaged, categorized, and packed into some sort of container--usually 208-L (55-gal) drums--for shipment to waste-storage sites. Prior to shipment, the containers must be labeled, assayed, and certified; the assay value determines the ultimate disposition of the waste containers. An accurate nondestructive assay (NDA) method would identify all the radioisotopes present and provide a quantitative measurement of their activity in the drum. In this way, waste containers could be routed in the most cost-effective manner and without having to reopen them. Currently, the most common gamma-ray method used to assay nuclear waste drums is segmented gamma-ray scanning (SGS) spectrometer that crudely measures only the amount of 235 U or 239 Pu present in the drum. This method uses a spatially-averaged, integrated, emitted gamma-ray-intensity value. The emitted intensity value is corrected by an assumed constant-attenuation value determined by a spatially-averaged, transmission (or active) measurement. Unfortunately, this typically results in an inaccurate determination of the radioactive activities within a waste drum because this measurement technique is valid only for homogeneous-attenuation or known drum matrices. However, since homogeneous-attenuation matrices are not common and may be unknown, other NDA techniques based on active and Passive CT (A ampersand PCT) are under development. The active measurement (ACT) yields a better attenuation matrix for the drum, while the passive measurement (PCT) more accurately determines the identity of the radioisotopes present and their activities. 9 refs., 2 figs

Capability and limitation study of the DDT passive-active neutron waste assay instrument

International Nuclear Information System (INIS)

Nicholas, N.J.; Coop, K.L.; Estep, R.J.

1992-05-01

The differential-dieaway-technique passive-active neutron assay system is widely used by transuranic waste generators to certify their drummed waste for eventual shipment to the Waste Isolation Pilot Plant (WIPP). Stricter criteria being established for waste emplacement at the WIPP site has led to a renewed interest in improvements to and a better understanding of current nondestructive assay (NDA) techniques. Our study includes the effects of source position, extreme matrices, high neutron backgrounds, and source self-shielding to explore the system's capabilities and limitations and to establish a basis for comparison with other NDA systems. 11 refs

A batch assay to measure microbial hydrogen sulfide production from sulfur-containing solid wastes

International Nuclear Information System (INIS)

Sun, Mei; Sun, Wenjie; Barlaz, Morton A.

2016-01-01

Large volumes of sulfur-containing wastes enter municipal solid waste landfills each year. Under the anaerobic conditions that prevail in landfills, oxidized forms of sulfur, primarily sulfate, are converted to sulfide. Hydrogen sulfide (H 2 S) is corrosive to landfill gas collection and treatment systems, and its presence in landfill gas often necessitates the installation of expensive removal systems. For landfill operators to understand the cost of managing sulfur-containing wastes, an estimate of the H 2 S production potential is needed. The objective of this study was to develop and demonstrate a biochemical sulfide potential (BSP) test to measure the amount of H 2 S produced by different types of sulfur-containing wastes in a relatively fast (30 days) and inexpensive (125 mL serum bottles) batch assay. This study confirmed the toxic effect of H 2 S on both sulfate reduction and methane production in batch systems, and demonstrated that removing accumulated H 2 S by base adsorption was effective for mitigating inhibition. H 2 S production potentials of coal combustion fly ash, flue gas desulfurization residual, municipal solid waste combustion ash, and construction and demolition waste were determined in BSP assays. After 30 days of incubation, most of the sulfate in the wastes was converted to gaseous or aqueous phase sulfide, with BSPs ranging from 0.8 to 58.8 mL H 2 S/g waste, depending on the chemical composition of the samples. Selected samples contained solid phase sulfide which contributed to the measured H 2 S yield. A 60 day incubation in selected samples resulted in 39–86% additional sulfide production. H 2 S production measured in BSP assays was compared with that measured in simulated landfill reactors and that calculated from chemical analyses. H 2 S production in BSP assays and in reactors was lower than the stoichiometric values calculated from chemical composition for all wastes tested, demonstrating the importance of assays to estimate the

SWEPP PAN assay system uncertainty analysis: Passive mode measurements of graphite waste

International Nuclear Information System (INIS)

Blackwood, L.G.; Harker, Y.D.; Meachum, T.R.; Yoon, Woo Y.

1997-07-01

The Idaho National Engineering and Environmental Laboratory is being used as a temporary storage facility for transuranic waste generated by the U.S. Nuclear Weapons program at the Rocky Flats Plant (RFP) in Golden, Colorado. Currently, there is a large effort in progress to prepare to ship this waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. In order to meet the TRU Waste Characterization Quality Assurance Program Plan nondestructive assay compliance requirements and quality assurance objectives, it is necessary to determine the total uncertainty of the radioassay results produced by the Stored Waste Examination Pilot Plant (SWEPP) Passive Active Neutron (PAN) radioassay system. To this end a modified statistical sampling and verification approach has been developed to determine the total uncertainty of a PAN measurement. In this approach the total performance of the PAN nondestructive assay system is simulated using computer models of the assay system and the resultant output is compared with the known input to assess the total uncertainty. This paper is one of a series of reports quantifying the results of the uncertainty analysis of the PAN system measurements for specific waste types and measurement modes. In particular this report covers passive mode measurements of weapons grade plutonium-contaminated graphite molds contained in 208 liter drums (waste code 300). The validity of the simulation approach is verified by comparing simulated output against results from measurements using known plutonium sources and a surrogate graphite waste form drum. For actual graphite waste form conditions, a set of 50 cases covering a statistical sampling of the conditions exhibited in graphite wastes was compiled using a Latin hypercube statistical sampling approach

Evaluation of drop versus trickle-feeding systems for crated or group-penned gestating sows.

Science.gov (United States)

Hulbert, L E; McGlone, J J

2006-04-01

A total of 160 gilts were used to evaluate the effects of pen vs. crated housing systems and drop- vs. trickle-fed feeding systems on sow productivity, occurrence of lesions during farrowing and weaning, immune measures, and behavioral responses during 2 consecutive gestation periods. Of the 160 eligible gilts, 117 farrowed in parity 1, and of those, 72 farrowed in parity 2. The gilts were randomly assigned to represent 1 of 4 factorially arranged treatment groups: pen drop-fed, crate drop-fed, pen trickle-fed, or crate trickle-fed. Replicate blocks were used for each parity with 5 sows per block initially in each treatment. At weaning, sows housed in pens had greater (P trickle-feeding system. Lesions scores and all other productivity measures did not differ among treatments. An interaction was observed for percentage of neutrophil phagocytosis (P trickle-fed sows, but in crates, drop-fed sows had a tendency for lower phagocytosis than trickle-fed sows. All other immune measures were not different among treatments. The occurrence of oral-nasal-facial (ONF) behaviors (chewing, rooting, and rubbing) and active behaviors increased, and lying behavior decreased (P trickle-feeding systems. None of the environments evaluated were associated with significant physiological stress responses among the sows. Thus, sows were able to adapt within each environment through behavioral mechanisms without the need to invoke major physiological adjustments.

Performance Demonstration Program Plan for Nondestructive Assay of Boxed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

2001-01-01

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP for boxed waste assay systems. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the boxed waste PDP, a simulated waste container consists of a modified standard waste box (SWB) emplaced with radioactive standards and fabricated matrix inserts. An SWB is a waste box with ends designed specifically to fit the TRUPACT-II shipping container. SWB's will be used to package a substantial volume of the TRU waste for disposal. These PDP sample components

A passive-active neutron device for assaying remote-handled transuranic waste

International Nuclear Information System (INIS)

Estep, R.J.; Coop, K.L.; Deane, T.M.; Lujan, J.E.

1990-01-01

A combined passive-active neutron assay device was constructed for assaying remote-handled transuranic waste. A study of matrix and source position effects in active assays showed that a knowledge of the source position alone is not sufficient to correct for position-related errors in highly moderating or absorbing matrices. An alternate function for the active assay of solid fuel pellets was derived, although the efficacy of this approach remains to be established

A batch assay to measure microbial hydrogen sulfide production from sulfur-containing solid wastes

Energy Technology Data Exchange (ETDEWEB)

Sun, Mei, E-mail: msun8@uncc.edu [Department of Civil, Construction, and Environmental Engineering, North Carolina State University, Campus Box 7908, Raleigh, NC (United States); Sun, Wenjie, E-mail: wsun@smu.edu [Department of Civil, Construction, and Environmental Engineering, North Carolina State University, Campus Box 7908, Raleigh, NC (United States); Department of Civil and Environmental Engineering, Southern Methodist University, PO Box 750340, Dallas, TX (United States); Barlaz, Morton A., E-mail: barlaz@ncsu.edu [Department of Civil, Construction, and Environmental Engineering, North Carolina State University, Campus Box 7908, Raleigh, NC (United States)

2016-05-01

Large volumes of sulfur-containing wastes enter municipal solid waste landfills each year. Under the anaerobic conditions that prevail in landfills, oxidized forms of sulfur, primarily sulfate, are converted to sulfide. Hydrogen sulfide (H{sub 2}S) is corrosive to landfill gas collection and treatment systems, and its presence in landfill gas often necessitates the installation of expensive removal systems. For landfill operators to understand the cost of managing sulfur-containing wastes, an estimate of the H{sub 2}S production potential is needed. The objective of this study was to develop and demonstrate a biochemical sulfide potential (BSP) test to measure the amount of H{sub 2}S produced by different types of sulfur-containing wastes in a relatively fast (30 days) and inexpensive (125 mL serum bottles) batch assay. This study confirmed the toxic effect of H{sub 2}S on both sulfate reduction and methane production in batch systems, and demonstrated that removing accumulated H{sub 2}S by base adsorption was effective for mitigating inhibition. H{sub 2}S production potentials of coal combustion fly ash, flue gas desulfurization residual, municipal solid waste combustion ash, and construction and demolition waste were determined in BSP assays. After 30 days of incubation, most of the sulfate in the wastes was converted to gaseous or aqueous phase sulfide, with BSPs ranging from 0.8 to 58.8 mL H{sub 2}S/g waste, depending on the chemical composition of the samples. Selected samples contained solid phase sulfide which contributed to the measured H{sub 2}S yield. A 60 day incubation in selected samples resulted in 39–86% additional sulfide production. H{sub 2}S production measured in BSP assays was compared with that measured in simulated landfill reactors and that calculated from chemical analyses. H{sub 2}S production in BSP assays and in reactors was lower than the stoichiometric values calculated from chemical composition for all wastes tested, demonstrating

Performance Values for Non-Destructive Assay (NDA) Technique Applied to Wastes: Evaluation by the ESARDA NDA Working Group

International Nuclear Information System (INIS)

Rackham, Jamie; Weber, Anne-Laure; Chard, Patrick

2012-01-01

The first evaluation of NDA performance values was undertaken by the ESARDA Working Group for Standards and Non Destructive Assay Techniques and was published in 1993. Almost ten years later in 2002 the Working Group reviewed those values and reported on improvements in performance values and new measurement techniques that had emerged since the original assessment. The 2002 evaluation of NDA performance values did not include waste measurements (although these had been incorporated into the 1993 exercise), because although the same measurement techniques are generally applied, the performance is significantly different compared to the assay of conventional Safeguarded special nuclear material. It was therefore considered more appropriate to perform a separate evaluation of performance values for waste assay. Waste assay is becoming increasingly important within the Safeguards community, particularly since the implementation of the Additional Protocol, which calls for declaration of plutonium and HEU bearing waste in addition to information on existing declared material or facilities. Improvements in the measurement performance in recent years, in particular the accuracy, mean that special nuclear materials can now be accounted for in wastes with greater certainty. This paper presents an evaluation of performance values for the NDA techniques in common usage for the assay of waste containing special nuclear material. The main topics covered by the document are: 1- Techniques for plutonium bearing solid wastes 2- Techniques for uranium bearing solid wastes 3 - Techniques for assay of fissile material in spent fuel wastes. Originally it was intended to include performance values for measurements of uranium and plutonium in liquid wastes; however, as no performance data for liquid waste measurements was obtained it was decided to exclude liquid wastes from this report. This issue of the performance values for waste assay has been evaluated and discussed by the ESARDA

Performance Values for Non-Destructive Assay (NDA) Technique Applied to Wastes: Evaluation by the ESARDA NDA Working Group

Energy Technology Data Exchange (ETDEWEB)

Rackham, Jamie [Babcock International Group, Sellafield, Seascale, Cumbria, (United Kingdom); Weber, Anne-Laure [Institut de Radioprotection et de Surete Nucleaire Fontenay-Aux-Roses (France); Chard, Patrick [Canberra, Forss Business and Technology park, Thurso, Caithness (United Kingdom)

2012-12-15

The first evaluation of NDA performance values was undertaken by the ESARDA Working Group for Standards and Non Destructive Assay Techniques and was published in 1993. Almost ten years later in 2002 the Working Group reviewed those values and reported on improvements in performance values and new measurement techniques that had emerged since the original assessment. The 2002 evaluation of NDA performance values did not include waste measurements (although these had been incorporated into the 1993 exercise), because although the same measurement techniques are generally applied, the performance is significantly different compared to the assay of conventional Safeguarded special nuclear material. It was therefore considered more appropriate to perform a separate evaluation of performance values for waste assay. Waste assay is becoming increasingly important within the Safeguards community, particularly since the implementation of the Additional Protocol, which calls for declaration of plutonium and HEU bearing waste in addition to information on existing declared material or facilities. Improvements in the measurement performance in recent years, in particular the accuracy, mean that special nuclear materials can now be accounted for in wastes with greater certainty. This paper presents an evaluation of performance values for the NDA techniques in common usage for the assay of waste containing special nuclear material. The main topics covered by the document are: 1- Techniques for plutonium bearing solid wastes 2- Techniques for uranium bearing solid wastes 3 - Techniques for assay of fissile material in spent fuel wastes. Originally it was intended to include performance values for measurements of uranium and plutonium in liquid wastes; however, as no performance data for liquid waste measurements was obtained it was decided to exclude liquid wastes from this report. This issue of the performance values for waste assay has been evaluated and discussed by the ESARDA

Computerized low-level waste assay system operation manual

International Nuclear Information System (INIS)

Jones, D.F.; Cowder, L.R.; Martin, E.R.

1976-01-01

An operation and maintenance manual for the computerized low-level waste box counter is presented, which describes routine assay techniques as well as theory of operation treated in sufficient depth so that an experienced assayist can make nonroutine assays. In addition, complete system schematics are included, along with a complete circuit description to facilitate not only maintenance and troubleshooting, but also reproduction of the instrument if desired. Complete software system descriptions are included so far as calculational algorithms are concerned, although detailed instruction listings would have to be obtained from Group R-1 at LASL in order to make machine-language code changes

On performance experience and measurements with Ningyo Waste Assay System (NWAS). 3

International Nuclear Information System (INIS)

Zaima, Naoki; Nakashima, Shin'ichi; Nakatsuka, Yoshiaki; Kado, Kazumi; Fujiki, Naoki

2014-03-01

A uranium mass assay system, NWAS (Ningyo Waste Assay System), for 200-litter wastes drums applied by NDA method was developed and accumulated the data of the actual uranium bearing wastes drums. The system consists of the 16 pieces of Helium-3 proportional counters for neutron detection generated from U-234(α,n) reaction or U-238 spontaneous fissions with polyethylene moderation and a Germanium solid state detector (Ge-SSD) for gamma ray detection as to determine uranium enrichment. In previous report, some measurement experiences had been introduced briefly. After that the measurements campaigns against the actual wastes drums stored in URCP had been carried out successfully, the uranium determination data of 850 drums had been accumulated approximately. Those characteristics were rich in variety including various kinds of matrices, uranium chemical compositions and range of uranium mass and so on. These works have contributed the decrease of the MUF in URCP, for which was the first purpose of introduction of NWAS. On the other hand several considerable problems on the system or methodology had been revealed technically or analytically through the measurements experiences. Such experiences are to be described precisely, in addition newly gained knowledge will be marshaled. Furthermore as the next improvement plans, the active neutrons assay for uranium bearing wastes drums are now progressing. The results of complications will lead us to the progressive next steps. (author)

System for automatic crate recognition

Directory of Open Access Journals (Sweden)

Radovan Kukla

2012-01-01

Full Text Available This contribution describes usage of computer vision and artificial intelligence methods for application. The method solves abuse of reverse vending machine. This topic has been solved as innovation voucher for the South Moravian Region. It was developed by Mendel university in Brno (Department of informatics – Faculty of Business and Economics and Department of Agricultural, Food and Environmental Engineering – Faculty of Agronomy together with the Czech subsidiary of Tomra. The project is focused on a possibility of integration industrial cameras and computers to process recognition of crates in the verse vending machine. The aim was the effective security system that will be able to save hundreds-thousands financial loss. As suitable development and runtime platform there was chosen product ControlWeb and VisionLab developed by Moravian Instruments Inc.

Nest building and posture changes and activity budget of gilts housed in pens and crates

DEFF Research Database (Denmark)

Andersen, Inger Lise; Vasdal, Guro; Pedersen, Lene Juul

2014-01-01

was born until 8 h after the birth of the first piglet. There was no significant effect of the sows breeding value on any of the sow behaviours. Sows housed in pens spent significantly more time nest building than crated sows from 4 to 12 h prepartum (P ...The aim of the present work was to study nest building, posture changes and the overall activity budget of gilts in pens vs. crates. Twenty-three HB gilts (high piglet survival day 5) and 21 LB gilts (low piglet survival day 5) were video recorded from day 110 in pregnancy to four days after...... farrowing in either a farrowing pen or farrowing crate. The gilts were provided with 2 kg of chopped straw daily from day 113 of pregnancy until farrowing in both environments. Nest building and other activity measures of the sows were analysed using continuous sampling the last 12 h before the first piglet...

Application of expert system technology to nondestructive waste assay - initial prototype model

Energy Technology Data Exchange (ETDEWEB)

Becker, G.K.; Determan, J.C. [Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States)

1997-11-01

Expert system technology has been identified as a technique useful for filling certain types of technology/capability gaps in existing waste nondestructive assay (NDA) applications. In particular, expert system techniques are being investigated with the intent of providing on-line evaluation of acquired data and/or directed acquisition of data in a manner that mimics the logic and decision making process a waste NDA expert would employ. The space from which information and data sources utilized in this process is much expanded with respect to the algorithmic approach typically utilized in waste NDA. Expert system technology provides a mechanism to manage and reason with this expanded information/data set. The material presented in this paper concerns initial studies and a resultant prototype expert system that incorporates pertinent information, and evaluation logic and decision processes, for the purpose of validating acquired waste NDA measurement assays. 6 refs., 6 figs.

Application of expert system technology to nondestructive waste assay - initial prototype model

International Nuclear Information System (INIS)

Becker, G.K.; Determan, J.C.

1997-01-01

Expert system technology has been identified as a technique useful for filling certain types of technology/capability gaps in existing waste nondestructive assay (NDA) applications. In particular, expert system techniques are being investigated with the intent of providing on-line evaluation of acquired data and/or directed acquisition of data in a manner that mimics the logic and decision making process a waste NDA expert would employ. The space from which information and data sources utilized in this process is much expanded with respect to the algorithmic approach typically utilized in waste NDA. Expert system technology provides a mechanism to manage and reason with this expanded information/data set. The material presented in this paper concerns initial studies and a resultant prototype expert system that incorporates pertinent information, and evaluation logic and decision processes, for the purpose of validating acquired waste NDA measurement assays. 6 refs., 6 figs

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

2009-01-01

Each testing and analytical facility performing waste characterization activities for the Waste Isolation Pilot Plant (WIPP) participates in the Performance Demonstration Program (PDP) to comply with the Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC) (DOE/WIPP-02-3122) and the Quality Assurance Program Document (QAPD) (CBFO-94-1012). The PDP serves as a quality control check for data generated in the characterization of waste destined for WIPP. Single blind audit samples are prepared and distributed to each of the facilities participating in the PDP. The PDP evaluates analyses of simulated headspace gases, constituents of the Resource Conservation and Recovery Act (RCRA), and transuranic (TRU) radionuclides using nondestructive assay (NDA) techniques.

Fully automated laboratory for the assay of plutonium in wastes and recoverable scraps

International Nuclear Information System (INIS)

Guiberteau, P.; Michaut, F.; Bergey, C.; Debruyne, T.

1990-01-01

To determine the plutonium content of wastes and recoverable scraps in intermediate size containers (ten liters) an automated laboratory has been carried out. Two passive methods of measurement are used. Gamma ray spectrometry allows plutonium isotopic analysis, americium determination and plutonium assay in wastes and poor scraps. Calorimetry is used for accurate (± 3%) plutonium determination in rich scraps. A full automation was realized with a barcode management and a supply robot to feed the eight assay set-ups. The laboratory works on a 24 hours per day and 365 days per year basis and has a capacity of 8,000 assays per year

Gregory Vlastos y los estudios sobre el Sócrates histórico

Directory of Open Access Journals (Sweden)

Carmen Trueba Atienza

2015-12-01

Full Text Available Este artigo discute a abordagem de Sócrates por Gregory Vlastos em “The historical Socrates and Athenian Democracy”, trabalho publicado na revista Political Theory (1983, e sua repercussão.

Menipo y Sócrates en Diálogos de los Muertos 6: pederastía en el Hades

OpenAIRE

Maksimczuk, José Pablo

2014-01-01

En el presente trabajo se analiza un pasaje de Diálogos de los muertos 6 de Luciano de Samósata. En el mismo Sócrates luego de una breve charla con Menipo de Gádara mantenida en el Hades invita al cínico a "echarse" (κατάκειμαι) junto a él y los apuestos Cármides, Fedro y Alcibíades. Un análisis lexical y contextual del fragmento revela que la invitación de Sócrates esconde una intención pederástica. A partir de un estudio conjunto de la obra pretendemos explicar la causa por la cual Sócrates...

Transuranic and Low-Level Boxed Waste Form Nondestructive Assay Technology Overview and Assessment

International Nuclear Information System (INIS)

Becker, G.; Connolly, M.; McIlwain, M.

1999-01-01

The Mixed Waste Focus Area (MWFA) identified the need to perform an assessment of the functionality and performance of existing nondestructive assay (NDA) techniques relative to the low-level and transuranic waste inventory packaged in large-volume box-type containers. The primary objectives of this assessment were to: (1) determine the capability of existing boxed waste form NDA technology to comply with applicable waste radiological characterization requirements, (2) determine deficiencies associated with existing boxed waste assay technology implementation strategies, and (3) recommend a path forward for future technology development activities, if required. Based on this assessment, it is recommended that a boxed waste NDA development and demonstration project that expands the existing boxed waste NDA capability to accommodate the indicated deficiency set be implemented. To ensure that technology will be commercially available in a timely fashion, it is recommended this development and demonstration project be directed to the private sector. It is further recommended that the box NDA technology be of an innovative design incorporating sufficient NDA modalities, e.g., passive neutron, gamma, etc., to address the majority of the boxed waste inventory. The overall design should be modular such that subsets of the overall NDA system can be combined in optimal configurations tailored to differing waste types

Assay of plutonium contaminated waste by gamma spectrometry

International Nuclear Information System (INIS)

Adsley, I.; Bull, R.; Davies, M.; Green, M.

2011-01-01

The extreme toxicity of plutonium necessitates the segregation of plutonium contaminated materials (PCM) with extremely small (sub-μg) levels of contamination. The driver to measure accurately these small quantities of plutonium within (relatively) large volumes of waste is (in part) financial. In particular the cost of disposal (per unit volume) rises steeply with increasing waste-category. Within the UK, there has been a historical reluctance to use low energy gamma radiation to sentence PCM because of the potential for self attenuation by dense materials. This is unfortunate because the low-energy gamma radiation from PCM offers the only practicable technique for segregating PCM within the various Low Level Waste (LLW) (>0.4Bq/g) and sub-LLW categories. Whilst passive neutron counting techniques have proved successful for assay of waste well into the Intermediate Level Waste (ILW) (>100Bq/g) category, a cursory study reveals that these techniques are barely capable of detecting mg quantities of plutonium -- let alone the sub-μg quantities present in LLW. This paper considers the use of two types of gamma detector for assay of PCM: the thin sodium iodide FIDLER (Field Instrument for the Detection of Low Energy Radiation) and the HPGe (High Purity Germanium) detector. Systems utilising these two types of detector can provide complementary information. FIDLER measurements are conducted by careful, local, systematic monitoring of surfaces. By contrast a HPGe detector can be used to monitor entire walls, or even rooms, in one measurement. Thus, a HPGe detector placed in the centre of room (from which any radioactive hot-spots have previously been removed) could be used to demonstrate that the average activity remaining close to the surface of the walls/floor/ceiling is below a given limit. The Monte Carlo Code MCNP 1 has been used to model both FIDLER probe and HPGe detector in the measurement geometries described above. The MCNP simulations have been validated

Energetics of sows and gilts in gestation crates in the cold.

NARCIS (Netherlands)

Verstegen, M.W.A.; Curtis, S.E.

1988-01-01

Seventy pregnant sows and gilts in gestation crates with unbedded concrete-slat floors and partitions in common (which permitted contact by neighbors) in a closed house with air temperature 10 to 12 degrees C during cold weather were studied for 3 wk. The animals' lower critical temperature and

To Make an Omelette You Have to Break the Egg Crate.

Science.gov (United States)

Corbett, H. Dickson

1982-01-01

A study of instructional change in three schools reveals that a change strategy should take advantage of existing communication networks. Where there is little interdependence among teachers, administrators need to encourage its growth and replace the egg crate form of organization with arrangements that increase teacher interaction. (MLF)

Social Technology Apply to National Policy on Solid Waste: Solid Waste Management Integrated in the Countryside

Directory of Open Access Journals (Sweden)

Greice Kelly Lourenco Porfirio de Oliveira

2016-06-01

Full Text Available This article aims to study the environmentally friendly social technologies through appropriate techniques to the treatment of solid waste disposed of improperly. After exposure of concepts, a reflection on the use of social technologies as a mechanism for realization of integrated management objectives of waste set by the National Solid Waste Policy will be made – 12.305/10 . Finally, data from the Social Technologies Bank of Brazil Foundation will be displayed showing the results of the use of technology to promote the integrated management of solid waste in rural communities Crateús/CE , through a provision aimed at PNRS, selective collection

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

DOE Carlsbad Field Office

2001-01-01

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the drummed waste PDP, a simulated waste container consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Drum PDP materials are stored at these sites under secure conditions to

Test procedure for boxed waste assay system

International Nuclear Information System (INIS)

Wachter, J.

1994-01-01

This document, prepared by Los Alamos National Laboratory's NMT-4 group, details the test methodology and requirements for Acceptance/Qualification testing of a Boxed Waste Assay System (BWAS) designed and constructed by Pajarito Scientific Corporation. Testing of the BWAS at the Plutonium Facility (TA55) at Los Alamos National Laboratory will be performed to ascertain system adherence to procurement specification requirements. The test program shall include demonstration of conveyor handling capabilities, gamma ray energy analysis, and imaging passive/active neutron accuracy and sensitivity. Integral to these functions is the system's embedded operating and data reduction software

Preliminary report of the comparison of multiple non-destructive assay techniques on LANL Plutonium Facility waste drums

International Nuclear Information System (INIS)

Bonner, C.; Schanfein, M.; Estep, R.

1999-01-01

Prior to disposal, nuclear waste must be accurately characterized to identify and quantify the radioactive content. The DOE Complex faces the daunting task of measuring nuclear material with both a wide range of masses and matrices. Similarly daunting can be the selection of a non-destructive assay (NDA) technique(s) to efficiently perform the quantitative assay over the entire waste population. In fulfilling its role of a DOE Defense Programs nuclear User Facility/Technology Development Center, the Los Alamos National Laboratory Plutonium Facility recently tested three commercially built and owned, mobile nondestructive assay (NDA) systems with special nuclear materials (SNM). Two independent commercial companies financed the testing of their three mobile NDA systems at the site. Contained within a single trailer is Canberra Industries segmented gamma scanner/waste assay system (SGS/WAS) and neutron waste drum assay system (WDAS). The third system is a BNFL Instruments Inc. (formerly known as Pajarito Scientific Corporation) differential die-away imaging passive/active neutron (IPAN) counter. In an effort to increase the value of this comparison, additional NDA techniques at LANL were also used to measure these same drums. These are comprised of three tomographic gamma scanners (one mobile unit and two stationary) and one developmental differential die-away system. Although not certified standards, the authors hope that such a comparison will provide valuable data for those considering these different NDA techniques to measure their waste as well as the developers of the techniques

Monte Carlo calculational design of an NDA instrument for the assay of waste products from high enriched uranium spent fuels

International Nuclear Information System (INIS)

Eccleston, G.W.; Schrandt, R.G.; MacDonald, J.L.; Cverna, F.H.

1979-01-01

The Monte Carlo design of the waste assay region of a dual assay system, to be installed at the Fluorinal and Storage Facility, is described. The instrument will be used by the facility operator to assay high-enriched spent fuel packages and waste solids produced from dissolution of the fuels. The fissile content discharged in the waste is expected to vary between 0 and 400 g of 235 U. Material accountability measurements of the waste must be obtained in the presence of large neutron (0.5 x 10 6 n/s) and gamma (50,000 R/hr) backgrounds. The assay system employs fast-neutron irradiation of the sample, using a 5 mg 252 Cf source, followed by delayed neutron counting after the source is transferred to storage. Calculations indicate a +-4-g (2 sigma) assay for a waste canister containing 300 g of 235 U is achievable with an end-of-life (1 mg) 252 Cf source and a background rate of 0.5 x 10 6 n/s

Use of Insulated Covers over Product Crates to Reduce Losses in Amaranth during Shipping Delays

Directory of Open Access Journals (Sweden)

Lizanne Wheeler

2015-12-01

Full Text Available Amaranth is a leafy vegetable with high nutrient content which is sensitive to temperature and low relative humidity. Delays in shipment to market may result in significant losses, therefore improved packaging to minimize mechanical damage and reduce moisture loss are desirable. Amaranth was stored in three types of consumer packages, bunches, clamshells and thin plastic bags, within vented plastic crates. Pallet loads were either covered with insulated material or not, while awaiting transportation. Results indicated covering pallets improved the color and overall quality while reducing weight loss and wilting. Covered crates had a “good” (7.6/9.0 overall quality while uncovered averaged 5.5/9.0 or “moderate” quality. There were significant differences in consumer package type, with the bagged amaranth having almost “excellent” quality (8.8/9.0 compared to “good-fair” quality in clamshells (6.2/9.0 and “poor-fair” quality in the control bunches (4.7/9.0. Amaranth stored in thin plastic bags was better in quality and color, with less weight loss and wilting, however, temperatures at the end of six hours of storage were higher and this may lead to microbial growth. Storage of amaranth in thin bags or clamshell packages, within plastic crates covered with insulated pallet covers while awaiting shipping resulted in improved overall quality and color.

Comparison of solid-phase and eluate assays to gauge the ecotoxicological risk of organic wastes on soil organisms

International Nuclear Information System (INIS)

Domene, Xavier; Alcaniz, Josep M.; Andres, Pilar

2008-01-01

Development of methodologies to assess the safety of reusing polluted organic wastes in soil is a priority in Europe. In this study, and coupled with chemical analysis, seven organic wastes were subjected to different aquatic and soil bioassays. Tests were carried out with solid-phase waste and three different waste eluates (water, methanol, and dichloromethane). Solid-phase assays were indicated as the most suitable for waste testing not only in terms of relevance for real situations, but also because toxicity in eluates was generally not representative of the chronic effects in solid-phase. No general correlations were found between toxicity and waste pollutant burden, neither in solid-phase nor in eluate assays, showing the inability of chemical methods to predict the ecotoxicological risks of wastes. On the contrary, several physicochemical parameters reflecting the degree of low organic matter stability in wastes were the main contributors to the acute toxicity seen in collembolans and daphnids. - Comparison of solid-phase and eluate bioassays for organic waste testing

Waste assay measurement integration system user interface

International Nuclear Information System (INIS)

Mousseau, K.C.; Hempstead, A.R.; Becker, G.K.

1995-01-01

The Waste Assay Measurement Integration System (WAMIS) is being developed to improve confidence in and lower the uncertainty of waste characterization data. There are two major components to the WAMIS: a data access and visualization component and a data interpretation component. The intent of the access and visualization software is to provide simultaneous access to all data sources that describe the contents of any particular container of waste. The visualization software also allows the user to display data at any level from raw to reduced output. Depending on user type, the software displays a menuing hierarchy, related to level of access, that allows the user to observe only those data sources s/he has been authorized to view. Access levels include system administrator, physicist, QA representative, shift operations supervisor, and data entry. Data sources are displayed in separate windows and presently include (1) real-time radiography video, (2) gamma spectra, (3) passive and active neutron, (4) radionuclide mass estimates, (5) total alpha activity (Ci), (6) container attributes, (7) thermal power (w), and (8) mass ratio estimates for americium, plutonium, and uranium isotopes. The data interpretation component is in the early phases of design, but will include artificial intelligence, expert system, and neural network techniques. The system is being developed on a Pentium PC using Microsoft Visual C++. Future generations of WAMIS will be UNIX based and will incorporate more generically radiographic/tomographic, gamma spectroscopic/tomographics, neutron, and prompt gamma measurements

Computed neutron coincidence counting applied to passive waste assay

Energy Technology Data Exchange (ETDEWEB)

Bruggeman, M.; Baeten, P.; De Boeck, W.; Carchon, R. [Nuclear Research Centre, Mol (Belgium)

1997-11-01

Neutron coincidence counting applied for the passive assay of fissile material is generally realised with dedicated electronic circuits. This paper presents a software based neutron coincidence counting method with data acquisition via a commercial PC-based Time Interval Analyser (TIA). The TIA is used to measure and record all time intervals between successive pulses in the pulse train up to count-rates of 2 Mpulses/s. Software modules are then used to compute the coincidence count-rates and multiplicity related data. This computed neutron coincidence counting (CNCC) offers full access to all the time information contained in the pulse train. This paper will mainly concentrate on the application and advantages of CNCC for the non-destructive assay of waste. An advanced multiplicity selective Rossi-alpha method is presented and its implementation via CNCC demonstrated. 13 refs., 4 figs., 2 tabs.

Computed neutron coincidence counting applied to passive waste assay

International Nuclear Information System (INIS)

Bruggeman, M.; Baeten, P.; De Boeck, W.; Carchon, R.

1997-01-01

Neutron coincidence counting applied for the passive assay of fissile material is generally realised with dedicated electronic circuits. This paper presents a software based neutron coincidence counting method with data acquisition via a commercial PC-based Time Interval Analyser (TIA). The TIA is used to measure and record all time intervals between successive pulses in the pulse train up to count-rates of 2 Mpulses/s. Software modules are then used to compute the coincidence count-rates and multiplicity related data. This computed neutron coincidence counting (CNCC) offers full access to all the time information contained in the pulse train. This paper will mainly concentrate on the application and advantages of CNCC for the non-destructive assay of waste. An advanced multiplicity selective Rossi-alpha method is presented and its implementation via CNCC demonstrated. 13 refs., 4 figs., 2 tabs

Autonomous controller (JCAM 10) for CAMAC crate with 8080 (INTEL) microprocessor

International Nuclear Information System (INIS)

Gallice, P.; Mathis, M.

1975-01-01

The CAMAC crate autonomous controller JCAM-10 is designed around an INTEL 8080 microprocessor in association with a 5K RAM and 4K REPROM memory. The concept of the module is described, in which data transfers between CAMAC modules and the memory are optimised from software point of view as well as from execution time. In fact, the JCAM-10 is a microcomputer with a set of 1000 peripheral units represented by the CAMAC modules commercially available

ASSESSMENT OF TOXICITY OF INDUSTRIAL WASTES USING CROP PLANT ASSAYS

OpenAIRE

Carmen Alice Teacă; Ruxanda Bodîrlău

2008-01-01

Environmental pollution has a harmful action on bioresources, including agricultural crops. It is generated through many industrial activities such as mining, coal burning, chemical technology, cement production, pulp and paper industry, etc. The toxicity of different industrial wastes and heavy metals excess was evaluated using crop plant assays (germination and hydroponics seedlings growth tests). Experimental data regarding the germination process of wheat (from two cultivars) and rye seed...

SVX Sequence Crate Custom J2/J3 Backplane

International Nuclear Information System (INIS)

Utes, M.

1997-01-01

The Custom J2/J3 Backplane is a full length (21 slot) user specified custom 3U backplane to be used in both the J2 and J3 positions. Slot spacing is identical to that used for VME (0.8-inch), and each backplane shall fit into a standard Eurocard VME style crate. The purpose of the Custom J2/J3 Backplane is to send and receive control and clock signals from the SVX chips via 3M pleated foil cables (Slots 2-21), and in slot 1, accept a cable connector and route its signal through to a signal distribution board.

Statistical sampling plan for the TRU waste assay facility

International Nuclear Information System (INIS)

Beauchamp, J.J.; Wright, T.; Schultz, F.J.; Haff, K.; Monroe, R.J.

1983-08-01

Due to limited space, there is a need to dispose appropriately of the Oak Ridge National Laboratory transuranic waste which is presently stored below ground in 55-gal (208-l) drums within weather-resistant structures. Waste containing less than 100 nCi/g transuranics can be removed from the present storage and be buried, while waste containing greater than 100 nCi/g transuranics must continue to be retrievably stored. To make the necessary measurements needed to determine the drums that can be buried, a transuranic Neutron Interrogation Assay System (NIAS) has been developed at Los Alamos National Laboratory and can make the needed measurements much faster than previous techniques which involved γ-ray spectroscopy. The previous techniques are reliable but time consuming. Therefore, a validation study has been planned to determine the ability of the NIAS to make adequate measurements. The validation of the NIAS will be based on a paired comparison of a sample of measurements made by the previous techniques and the NIAS. The purpose of this report is to describe the proposed sampling plan and the statistical analyses needed to validate the NIAS. 5 references, 4 figures, 5 tables

Chemical Eradication of the Ring Rot Bacterium Clavibacter michiganensis subsp. sepedonicus on Potato Storage Crates

NARCIS (Netherlands)

Stevens, L.H.; Lamers, J.G.; Zouwen, van der P.S.; Mendes, O.; Berg, van den W.; Tjou-Tam-Sin, N.N.A.; Jilesen, C.J.T.J.; Spoorenberg, P.M.; Wolf, van der J.M.

2017-01-01

Four commercially available disinfection products were tested for their efficacy against Clavibacter michiganensis subsp. sepedonicus (Cms), causative agent of bacterial ring rot, on wooden potato storage crates. Each of these products represented a different class of biocide, i.e. organic acids

Are Fish and Standardized FETAX Assays Protective Enough for Amphibians? A Case Study on Xenopus laevis Larvae Assay with Biologically Active Substances Present in Livestock Wastes

Directory of Open Access Journals (Sweden)

Federica Martini

2012-01-01

Full Text Available Biologically active substances could reach the aquatic compartment when livestock wastes are considered for recycling. Recently, the standardized FETAX assay has been questioned, and some researchers have considered that the risk assessment performed on fish could not be protective enough to cover amphibians. In the present study a Xenopus laevis acute assay was developed in order to compare the sensitivity of larvae relative to fish or FETAX assays; veterinary medicines (ivermectin, oxytetracycline, tetracycline, sulfamethoxazole, and trimethoprim and essential metals (zinc, copper, manganese, and selenium that may be found in livestock wastes were used for the larvae exposure. Lethal (LC50 and sublethal effects were estimated. Available data in both, fish and FETAX studies, were in general more protective than values found out in the current study, but not in all cases. Moreover, the presence of nonlethal effects, caused by ivermectin, zinc, and copper, suggested that several physiological mechanisms could be affected. Thus, this kind of effects should be deeply investigated. The results obtained in the present study could expand the information about micropollutants from livestock wastes on amphibians.

Radioactive waste package assay facility. Final report - V. A

International Nuclear Information System (INIS)

Molesworth, T.V.; Strachan, N.R.; Findlay, D.J.S.; Wise, M.O.; Forrest, K.R.; Rogers, J.D.

1993-01-01

This report provides a summary of research work carried out in support of the development of an integrated assay system for the quality checking of Intermediate Level Waste encapsulated in cement. Four non-destructive techniques were originally identified as being viable methods for obtaining radiometric inventory data from a cemented 500 litre ILW package. The major part of the programme was devoted to the development of two interrogation techniques; active neutron for measuring the total fissile content and active gamma for measuring the total actinide content. An electron linear accelerator was used to supply the interrogating beam for these two methods. In addition the linear accelerator beam could be used for high energy radiography. The results of this work are described and the performances and limitations of the non-destructive methods are summarised. The main engineering and operational features which influence the design of an integrated assay facility are outlined and a conceptual layout for a facility to inspect 750 ILW drums a year is described. Details of the detection methods, data processing and potential application of the assay facility are given in three associated HMIP reports. (Author)

Quality Assistance Objectives for Nondestructive Assay at the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

CANTALOUB, M.G.

2000-01-01

The Waste Receiving and Processing (WRAP) facility, located on the Word Site in southeast Washington, is a key link in the certification of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP). Waste characterization is one of the vital functions performed at WRAP, and nondestructive assay (NDA) measurements of TRU waste containers is one of two required methods used for waste characterization. The Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE/WIPP-069 (WIPP-WAC) delineates the quality assurance objectives which have been established for NDA measurement systems. Sites must demonstrate that the quality assurance objectives can be achieved for each radioassay system over the applicable ranges of measurement. This report summarizes the validation of the WRAP NDA systems against the radioassay quality assurance objectives or QAOs. A brief description of the each test and significant conclusions are included. Variables that may have affected test outcomes and system response are also addressed

Single-crate stand-alone CAMAC control system for a negative ion source test facility

International Nuclear Information System (INIS)

Juras, R.C.; Ziegler, N.F.

1979-01-01

A single-crate CAMAC system was configured to control a negative ion source development facility at ORNL and control software was written for the crate microcomputer. The software uses inputs from a touch panel and a shaft encoder to control the various operating parameters of the test facility and uses the touch panel to display the operating status. Communication to and from the equipment at ion source potential is accomplished over optical fibers from an ORNL-built CAMAC module. A receiver at ion source potential stores the transmitted data and some of these stored values are then used to control discrete parameters of the ion source (i.e., power supply on or off). Other stored values are sent to a multiplexed digital-to-analog converter to provide analog control signals. A transmitter at ion source potential transmits discrete status information and several channels of analog data from an analog-to-digital converter back to the ground-potential receiver where it is stored to be read and displayed by the software

Characterizing and improving passive-active shufflers for assays of 208-Liter waste drums

International Nuclear Information System (INIS)

Rinard, P.M.; Adams, E.L.; Menlove, H.O.; Sprinkle, J.K. Jr.

1992-01-01

A passive and active neutron shuffler for 208-L waste drums has been used to perform over 1500 active and 500 passive measurements on uranium and plutonium samples in 28 different matrices. The shuffler is now better characterized and improvements have been implemented or suggested. An improved correction for the effects of the matrix material was devised from flux-monitor responses. The most important cause of inaccuracies in assays is a localized instead of a uniform distribution of fissile material in a drum; a technique for deducing the distribution from the assay data and then applying a correction is suggested and will be developed further. A technique is given to detect excessive amounts of moderator that could make hundreds of grams of 235 U assay as zero grams. Sensitivities (minimum detectable masses) for 235 U with active assays and for 240 Pu eff with passive assays are presented and the effects of moderators and absorbers on sensitivities noted

PROMETHEE: a versatile R and D measurement device for low level waste assay

International Nuclear Information System (INIS)

Romeyer Dherby, J.; Passard, C.; Mariani, A.

1996-01-01

The accurate measurement of heavy nuclide masses and activities in radioactive wastes drums is an important part of waste management. The Active/Passive non destructive assay of radioactive waste drums using a 14 MeV neutron generator is particularly interesting for alpha low level measurements or for gamma irradiating wastes. The development, optimisation, and validation of such a device for industrial use necessitate the building of a demonstrator. In 1985, the CEA decided to build at Cadarache the PROMETHEE modular system for experimenting the pulsed generator techniques, and since then, this device has led us to define several specific systems. At the present time, in the frame of COGEMA actions to reduce the volume of the reprocessing waste, a new strategy of drumming and incineration is going to start at LA HAGUE and MARCOULE, for the low level waste planned for surface storage. This strategy depends on the performance improvement of non destructive measurements systems used for the alpha waste evaluation. In this goal, a developments and tests are carried out on the PROMETHEE research and development facility at CEA CADARACHE, in order to obtain the required performances

PROMETHEE: a versatile R and D measurement device for low level waste assay

Energy Technology Data Exchange (ETDEWEB)

Romeyer Dherby, J.; Passard, C.; Mariani, A

1996-12-31

The accurate measurement of heavy nuclide masses and activities in radioactive wastes drums is an important part of waste management. The Active/Passive non destructive assay of radioactive waste drums using a 14 MeV neutron generator is particularly interesting for alpha low level measurements or for gamma irradiating wastes. The development, optimisation, and validation of such a device for industrial use necessitate the building of a demonstrator. In 1985, the CEA decided to build at Cadarache the PROMETHEE modular system for experimenting the pulsed generator techniques, and since then, this device has led us to define several specific systems. At the present time, in the frame of COGEMA actions to reduce the volume of the reprocessing waste, a new strategy of drumming and incineration is going to start at LA HAGUE and MARCOULE, for the low level waste planned for surface storage. This strategy depends on the performance improvement of non destructive measurements systems used for the alpha waste evaluation. In this goal, a developments and tests are carried out on the PROMETHEE research and development facility at CEA CADARACHE, in order to obtain the required performances.

Recent developments at French atomic energy commission relating to non destructive nuclear waste assay by using electron accelerator

International Nuclear Information System (INIS)

Lvoussi, A.; Romeyer-Dhebey, J.; Jallu, F.; Passard, C.; Mariani, A.; Recroix, H.; Payan, E.; Denis, C.; Loridon, J.; Buisson, A.; Nurdin, G.; Allano, J.; Jaureguy, J.C.

2000-01-01

An important program is currently in progress at several laboratories over the world for the development of sensitive, practical non-destructive assay techniques for the quantification of low level transuranics (TRU) in solid wastes. The wide variety of materials and contaminants, the low concentrations and large volumes involve, all make this kind of assay a complicated affair. Over the last few years, considerable progress has been made in the field of assay techniques for low level contaminated wastes. This report describes the methods being developed at French Atomic Energy Commission (C.E.A.) in Cadarache to assay high density TRU waste packages by using photon, neutron or both photon and neutron as interrogating particles. All of these particles are produced by using a pulsed electron linear accelerator from which the photons are produced following Bremsstrahlung phenomena on a heavy metallic converter and the neutrons are generated in appropriate low level photoneutron threshold target (e.g. Beryllium). The dynamic of photonuclear interactions and photoneutron production, use of an electron linear accelerator as a particle source, experimental and electronics details, experimental results, simulation to experiment performances and future experimental and theoretical studies are discussed. (authors)

Monitoring of plutonium contaminated solid waste streams. Chapter II: principles and theory of radiometric assay

International Nuclear Information System (INIS)

Birkhoff, G.; Bondar, L.; Notea, A.; Segal, Y.

1977-01-01

The interpretation of a count rate distribution obtained from radiometric assay of a given waste items population in terms of source strength distribution is discussed. A model for the evaluation of errors, arising from non uniform source density distribution (Pu) within the item volume and heterogeneity of matrix materials, is presented. Points concerning calibration procedures and representativity of reference materials are dealt with. Qualification procedures for possible monitoring systems are outlined on the basis of comparison with reference systems. The latter are composed of reference monitors based on high resolution gamma spectrometry and passive and active neutron techniques. The importance of information upon the elemental composition and density distribution of matrix materials for the interpretation of radiometric assay of solid wastes is stressed

The development of an expert system for the characterization of waste assay data

Energy Technology Data Exchange (ETDEWEB)

Bridges, S.; Hodges, J.; Sparrow, C. [Mississippi State Univ., Mississippi State, MS (United States)] [and others

1997-11-01

Containers of transuranic and low-level alpha contaminated waste generated as a byproduct of Department of Energy defense-related programs must be characterized before their proper disposition can be determined. Nondestructive assay methods are the most desirable means for assessing the mass and activity of the entrained transuranic radionuclides. However, there are other sources of information that may be useful in the characterization of the entrained waste (e.g., container manifests, information about the generation process, and destructive assay techniques performed on representative samples). This paper describes initial work on an expert system being developed to analyze and characterize containerized radiological waste. This system is being developed by scientists at the Mississippi State University Diagnostic and Instrumentation Laboratory (DIAL) in collaboration with scientists at the Idaho National Engineering Laboratory. The DIAL scientists are responsible for (1) the development of techniques to represent and reason with evidence from a variety of sources, and (2) the development of appropriate method(s) to represent and reason with confidence levels associated with that evidence. This paper describes exploratory versions of the expert system developed to evaluate four techniques for representing and reasoning with the confidence in the evidence: MYCIN-style certainty factors, Dempster-Shafer Theory, Bayesian networks, and fuzzy logic. 16 refs., 8 figs., 4 tabs.

The development of an expert system for the characterization of waste assay data

International Nuclear Information System (INIS)

Bridges, S.; Hodges, J.; Sparrow, C.

1997-01-01

Containers of transuranic and low-level alpha contaminated waste generated as a byproduct of Department of Energy defense-related programs must be characterized before their proper disposition can be determined. Nondestructive assay methods are the most desirable means for assessing the mass and activity of the entrained transuranic radionuclides. However, there are other sources of information that may be useful in the characterization of the entrained waste (e.g., container manifests, information about the generation process, and destructive assay techniques performed on representative samples). This paper describes initial work on an expert system being developed to analyze and characterize containerized radiological waste. This system is being developed by scientists at the Mississippi State University Diagnostic and Instrumentation Laboratory (DIAL) in collaboration with scientists at the Idaho National Engineering Laboratory. The DIAL scientists are responsible for (1) the development of techniques to represent and reason with evidence from a variety of sources, and (2) the development of appropriate method(s) to represent and reason with confidence levels associated with that evidence. This paper describes exploratory versions of the expert system developed to evaluate four techniques for representing and reasoning with the confidence in the evidence: MYCIN-style certainty factors, Dempster-Shafer Theory, Bayesian networks, and fuzzy logic. 16 refs., 8 figs., 4 tabs

Proceedings for the nondestructive assay and nondestructive examination waste characterization conference. No. 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

This report contains paper presented at the 5th Nondestructive Assay and nondestructive Examination Waste Characterization conference. Topics included compliance, neutron NDA techniques, gamma NDA techniques, tomographic methods, and NDA modality and information combination techniques. Individual reports have been processed separately for the United States Department of Energy databases.

Proceedings for the nondestructive assay and nondestructive examination waste characterization conference. No. 5

International Nuclear Information System (INIS)

1997-01-01

This report contains paper presented at the 5th Nondestructive Assay and nondestructive Examination Waste Characterization conference. Topics included compliance, neutron NDA techniques, gamma NDA techniques, tomographic methods, and NDA modality and information combination techniques. Individual reports have been processed separately for the United States Department of Energy databases

Neutron interrogator assay system for the Idaho Chemical Processing Plant waste canisters and spent fuel: preliminary description and operating procedures manual

International Nuclear Information System (INIS)

Menlove, H.O.; Eccleston, G.; Close, D.A.; Speir, L.G.

1978-05-01

A neutron interrogation assay system is being designed for the measurement of waste canisters and spent fuel packages at the new Idaho Chemical Processing Plant to be operated by Allied Chemical Corp. The assay samples consist of both waste canisters from the fluorinel dissolution process and spent fuel assemblies. The assay system is a 252 Cf ''Shuffler'' that employs a cyclic sequence of fast-neutron interrogation with a 252 Cf source followed by delayed-neutron counting to determine the 235 U content

The help of simulation codes in designing waste assay systems using neutron measurement methods: Application to the alpha low level waste assay system PROMETHEE 6

Energy Technology Data Exchange (ETDEWEB)

Mariani, A.; Passard, C.; Jallu, F. E-mail: fanny.jallu@cea.fr; Toubon, H

2003-11-01

The design of a specific nuclear assay system for a dedicated application begins with a phase of development, which relies on information from the literature or on knowledge resulting from experience, and on specific experimental verifications. The latter ones may require experimental devices which can be restricting in terms of deadline, cost and safety. One way generally chosen to bypass these difficulties is to use simulation codes to study particular aspects. This paper deals with the potentialities offered by the simulation in the case of a passive-active neutron (PAN) assay system for alpha low level waste characterization; this system has been carried out at the Nuclear Measurements Development Laboratory of the French Atomic Energy Commission. Due to the high number of parameters to be taken into account for its development, this is a particularly sophisticated example. Since the PAN assay system, called PROMETHEE (prompt epithermal and thermal interrogation experiment), must have a detection efficiency of more than 20% and preserve a high level of modularity for various applications, an improved version has been studied using the MCNP4 (Monte Carlo N-Particle) transport code. Parameters such as the dimensions of the assay system, of the cavity and of the detection blocks, and the thicknesses of the nuclear materials of neutronic interest have been optimised. Therefore, the number of necessary experiments was reduced.

The help of simulation codes in designing waste assay systems using neutron measurement methods: Application to the alpha low level waste assay system PROMETHEE 6

International Nuclear Information System (INIS)

Mariani, A.; Passard, C.; Jallu, F.; Toubon, H.

2003-01-01

The design of a specific nuclear assay system for a dedicated application begins with a phase of development, which relies on information from the literature or on knowledge resulting from experience, and on specific experimental verifications. The latter ones may require experimental devices which can be restricting in terms of deadline, cost and safety. One way generally chosen to bypass these difficulties is to use simulation codes to study particular aspects. This paper deals with the potentialities offered by the simulation in the case of a passive-active neutron (PAN) assay system for alpha low level waste characterization; this system has been carried out at the Nuclear Measurements Development Laboratory of the French Atomic Energy Commission. Due to the high number of parameters to be taken into account for its development, this is a particularly sophisticated example. Since the PAN assay system, called PROMETHEE (prompt epithermal and thermal interrogation experiment), must have a detection efficiency of more than 20% and preserve a high level of modularity for various applications, an improved version has been studied using the MCNP4 (Monte Carlo N-Particle) transport code. Parameters such as the dimensions of the assay system, of the cavity and of the detection blocks, and the thicknesses of the nuclear materials of neutronic interest have been optimised. Therefore, the number of necessary experiments was reduced

Uncertainty analysis of the SWEPP PAN assay system for glass waste (content codes 440, 441 and 442)

International Nuclear Information System (INIS)

Blackwood, L.G.; Harker, Y.D.; Meachum, T.R.; Yoon, W.Y.

1996-10-01

INEL is being used as a temporary storage facility for transuranic waste generated by the Nuclear Weapons program at the Rocky Flats Plant. Currently, there is a large effort in progress to prepare to ship this waste to WIPP. In order to meet the TRU Waste Characterization Quality Assurance Program Plan nondestructive assay compliance requirements and quality assurance objectives, it is necessary to determine the total uncertainty of the radioassay results produced by the Stored Waste Examination Pilot Plant (SWEPP) Passive Action Neutron (PAN) radioassay system. This paper discusses a modified statistical sampling and verification approach used to determine the total uncertainty of SWEPP PAN measurements for glass waste (content codes 440, 441, and 442) contained in 208 liter drums. In the modified statistical sampling and verification approach, the total performance of the SWEPP PAN nondestructive assay system for specifically selected waste conditions is simulated using computer models. A set of 100 cases covering the known conditions exhibited in glass waste was compiled using a combined statistical sampling and factorial experimental design approach. Parameter values assigned in each simulation were derived from reviews of approximately 100 real-time radiography video tapes of RFP glass waste drums, results from previous SWEPP PAN measurements on glass waste drums, and shipping data from RFP where the glass waste was generated. The data in the 100 selected cases form the multi-parameter input to the simulation model. The reported plutonium masses from the simulation model are compared with corresponding input masses. From these comparisons, the bias and total uncertainty associated with SWEPP PAN measurements on glass waste drums are estimated. The validity of the simulation approach is verified by comparing simulated output against results from calibration measurements using known plutonium sources and two glass waste calibration drums

Uncertainty analysis of the SWEPP PAN assay system for glass waste (content codes 440, 441 and 442)

Energy Technology Data Exchange (ETDEWEB)

Blackwood, L.G.; Harker, Y.D.; Meachum, T.R.; Yoon, W.Y.

1996-10-01

INEL is being used as a temporary storage facility for transuranic waste generated by the Nuclear Weapons program at the Rocky Flats Plant. Currently, there is a large effort in progress to prepare to ship this waste to WIPP. In order to meet the TRU Waste Characterization Quality Assurance Program Plan nondestructive assay compliance requirements and quality assurance objectives, it is necessary to determine the total uncertainty of the radioassay results produced by the Stored Waste Examination Pilot Plant (SWEPP) Passive Action Neutron (PAN) radioassay system. This paper discusses a modified statistical sampling and verification approach used to determine the total uncertainty of SWEPP PAN measurements for glass waste (content codes 440, 441, and 442) contained in 208 liter drums. In the modified statistical sampling and verification approach, the total performance of the SWEPP PAN nondestructive assay system for specifically selected waste conditions is simulated using computer models. A set of 100 cases covering the known conditions exhibited in glass waste was compiled using a combined statistical sampling and factorial experimental design approach. Parameter values assigned in each simulation were derived from reviews of approximately 100 real-time radiography video tapes of RFP glass waste drums, results from previous SWEPP PAN measurements on glass waste drums, and shipping data from RFP where the glass waste was generated. The data in the 100 selected cases form the multi-parameter input to the simulation model. The reported plutonium masses from the simulation model are compared with corresponding input masses. From these comparisons, the bias and total uncertainty associated with SWEPP PAN measurements on glass waste drums are estimated. The validity of the simulation approach is verified by comparing simulated output against results from calibration measurements using known plutonium sources and two glass waste calibration drums.

Matrix effects of TRU [transuranic] assays using the SWEPP PAN assay system

International Nuclear Information System (INIS)

Smith, J.R.

1990-08-01

The Drum Assay System (DAS) at the Stored Waste Experimental Pilot Plant (SWEPP) is a second-generation active-passive neutron assay system. It has been used to assay over 5000 208-liter drums of transuranic waste from the Rocky Flats Plant (RFP). Data from these assays have been examined and compared with the assays performed at Rocky Flats, mainly utilize counting of 239 Pu gamma rays. For the most part the passive assays are in very good agreement with the Rocky Flats assays. The active assays are strongly correlated with the results of the other two methods, but require matrix-dependent correction factors beyond those provided by the system itself. A set of matrix-dependent correction factors has been developed from the study of the assay results. 3 refs., 4 figs., 3 tabs

Automated box/drum waste assay (252Cf shuffler) through the material access and accountability boundary

International Nuclear Information System (INIS)

Horley, E.C.; Bjork, C.W.; Bourret, S.C.; Polk, P.J.; Schneider, C.J.; Studley, R.V.

1992-01-01

For the first time, a shuffler waste-assay system has been made a part of material access and accountability boundary (MAAB). A 252 Cf Pass-Thru shuffler integrated with a conveyor handling system, will process box or drum waste across the MAAB. This automated system will significantly reduce personnel operating costs because security forces will not be required at the MAAB during waste transfer. Further, the system eliminates the chance of a mix-up between measured and nonmeasured waste. This Pass-Thru shuffler is to be installed in the Westinghouse Savannah River Company 321M facility to screen waste boxes and drums for 235 U. An automated conveyor will load waste containers into the shuffler, and upon verification, will transfer the containers across the MAAB. Verification will consist of a weight measurement followed by active neutron interrogation. Containers that pass low-level waste criteria will be conveyed to an accumulator section outside the MAAB. If a container fails to meet the waste criteria, it will be rejected and sent back to the load station for manual inspection and repackaging

Passive non destructive assay of hull waste by gross neutron counting method

International Nuclear Information System (INIS)

Andola, Sanjay; Sur, Amit; Rawool, A.M.; Sharma, B.; Kaushik, T.C.; Gupta, S.C.; Basu, Sekhar; Raman Kumar; Agarwal, K.

2014-01-01

The special nuclear material accounting (SNMA) is an important and necessary issue now in nuclear waste management. The hull waste generated from dissolution of spent fuel contains small amounts of Uranium and Plutonium and other actinides due to undissolved trapped material inside zircoalloy tubes. We report here on the development of a Passive Hull monitoring system using gross neutron counting technique and its implementation with semiautomatic instrumentation. The overall sensitivity of the 3 He detector banks placed at 75 cm from the centre of loaded hull cask comes out to 5.2 x 10 -3 counts per neutron (c/n) while with standard Pu-Be source placed in same position it comes out to be 3.1 x 10 3 c/n. The difference in the efficiency is mainly because of the differences in the geometry and size of hull cask as well as difference in the energy spectrum of hull waste and Pu-Be source. This is accounted through Monte Carlo computations. The Pu mass in solid waste comes out as expected and varies with the surface dose rate of drum in almost a proportional manner. Being simple and less time consuming, this setup has been installed for routine assay of solid Hull waste at NRB, Tarapur

O julgamento de Sócrates

Directory of Open Access Journals (Sweden)

Arnaldo Sampaio de Moraes Godoy

2003-07-01

Full Text Available Trata da historiografia jurídica e dasrelações entre direito, história e verdade.Vale-se de referências literárias ao julgamentode Sócrates, colhida em textos de contemporâneosdo filósofo, identificando tessiturade narrativas que atestam incongruência,relativismo e construído cultural clássico natradição ocidental. Indica abordagens mais recentes,como a de Isidor Stone, não aceita pelatradição acadêmica. Instiga, na medida em quepretende invocar que a história do direito émenos o que aconteceu e mais o que o narradorpretende inventariar. Denuncia aspectos damiragem helênica, contribuindo na construçãodos saberes críticos na feição contemporâneodos textos de filosofia do direito.It deals with juridical historiographyand the relations between right, history andtruth. It relies on literary references on thetrial of Socrates, collected from texts of histime, identifying the narrative webbing thatwitnesses incongruence, relativism, andclassic cultural constructs of western tradition.It also points out novel approaches,like that of Isidor Stone, which is not acceptedby the academic tradition. It instigates, onceit intends to invoke that history of law is lesswhat happened than what the narrator wantsit to be. It denounces aspects of the helenicmirage, contributing to the construction ofcritical knowledge in the making of contemporarytexts on philosophy of law.

Bremsstrahlung-Based Imaging and Assays of Radioactive, Mixed and Hazardous Waste

Science.gov (United States)

Kwofie, J.; Wells, D. P.; Selim, F. A.; Harmon, F.; Duttagupta, S. P.; Jones, J. L.; White, T.; Roney, T.

2003-08-01

A new nondestructive accelerator based x-ray fluorescence (AXRF) approach has been developed to identify heavy metals in large-volume samples. Such samples are an important part of the process and waste streams of U.S Department of Energy sites, as well as other industries such as mining and milling. Distributions of heavy metal impurities in these process and waste samples can range from homogeneous to highly inhomogeneous, and non-destructive assays and imaging that can address both are urgently needed. Our approach is based on using high-energy, pulsed bremsstrahlung beams (3-6.5 MeV) from small electron accelerators to produce K-shell atomic fluorescence x-rays. In addition we exploit pair-production, Compton scattering and x-ray transmission measurements from these beams to probe locations of high density and high atomic number. The excellent penetrability of these beams allows assays and images for soil-like samples at least 15 g/cm2 thick, with elemental impurities of atomic number greater than approximately 50. Fluorescence yield of a variety of targets was measured as a function of impurity atomic number, impurity homogeneity, and sample thickness. We report on actual and potential detection limits of heavy metal impurities in a soil matrix for a variety of samples, and on the potential for imaging, using AXRF and these related probes.

A method for assay of special nuclear material in high level liquid waste streams

International Nuclear Information System (INIS)

Venkata Subramani, C.R.; Swaminathan, K.; Asuvathraman, R.; Kutty, K.V.G.

2003-01-01

The assay of special nuclear material in the high level liquid waste streams assumes importance as this is the first stage in the extraction cycle and considerable losses of plutonium could occur here. This stream contains all the fission products as also the minor actinides and hence normal nuclear techniques cannot be used without prior separation of the special nuclear material. This paper presents the preliminary results carried out using wavelength dispersive x-ray fluorescence as part of the developmental efforts to assay SNM in these streams by instrumental techniques. (author)

Assay development status report for total cyanide

International Nuclear Information System (INIS)

Simpson, B.C.; Jones, T.E.; Pool, K.H.

1993-02-01

A validated cyanide assay that is applicable to a variety of tank waste matrices is necessary to resolve certain waste tank safety issues and for purposes of overall waste characterization. The target for this effort is an assay with an applicable range of greater than 1,000 ppM (0.10 wt%) total cyanide and a confidence level greater than 80%. Figure 1 illustrates the operating regime of the proposed cyanide assay method. The Assay Development Status Report for Total Cyanide will summarize the past experience with cyanide analyses on-tank waste matrices and will rate the status of the analytical methods used to assay total cyanide (CN - ion) in the tank waste matrices as acceptable or unacceptable. This paper will also briefly describe the current efforts for improving analytical resolution of the assays and the attempts at speciation

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

2005-01-01

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) is a test program designed to yield data on measurement system capability to characterize drummed transuranic (TRU) waste generated throughout the Department of Energy (DOE) complex. The tests are conducted periodically and provide a mechanism for the independent and objective assessment of NDA system performance and capability relative to the radiological characterization objectives and criteria of the Office of Characterization and Transportation (OCT). The primary documents requiring an NDA PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC), which requires annual characterization facility participation in the PDP, and the Quality Assurance Program Document (QAPD). This NDA PDP implements the general requirements of the QAPD and applicable requirements of the WAC. Measurement facilities must demonstrate acceptable radiological characterization performance through measurement of test samples comprised of pre-specified PDP matrix drum/radioactive source configurations. Measurement facilities are required to analyze the NDA PDP drum samples using the same procedures approved and implemented for routine operational waste characterization activities. The test samples provide an independent means to assess NDA measurement system performance and compliance per criteria delineated in the NDA PDP Plan. General inter-comparison of NDA measurement system performance among DOE measurement facilities and commercial NDA services can also be evaluated using measurement results on similar NDA PDP test samples. A PDP test sample consists of a 55-gallon matrix drum containing a waste matrix type representative of a particular category of the DOE waste inventory and nuclear material standards of known radionuclide and isotopic composition typical of DOE radioactive material. The PDP sample components are made available to participating measurement facilities as designated by the

On the influence of matrix's heterogeneity on uncertainty of gamma-spectrometry at activity assay of radioactive waste

Directory of Open Access Journals (Sweden)

V. S. Prokopenko

2009-09-01

Full Text Available The influence of the waste matrix heterogeneity on the flux density value of initial gamma quanta at the transport of quanta in the matrix was considered. It is shown that the waste heterogeneity leads to the positive shift of the average flux density value comparing with corresponding value for homogeneous waste if average value of the attenuation factor in heterogeneous matrix is equal to the attenuation factor of homogeneous matrix. Due to this the activity assay of heterogeneous waste by a technique which was calibrated by using a homogeneous standard (surrogate container the measurement results will be positively shifted, or, in other words, conservative estimation of the waste activity will be obtained.

On the efficiency calibration of a drum waste assay system

CERN Document Server

Dinescu, L; Cazan, I L; Macrin, R; Caragheorgheopol, G; Rotarescu, G

2002-01-01

The efficiency calibration of a gamma spectroscopy waste assay system, constructed by IFIN-HH, was performed. The calibration technique was based on the assumption of a uniform distribution of the source activity in the drum and also a uniform sample matrix. A collimated detector (HPGe--20% relative efficiency) placed at 30 cm from the drum was used. The detection limit for sup 1 sup 3 sup 7 Cs and sup 6 sup 0 Co is approximately 45 Bq/kg for a sample of about 400 kg and a counting time of 10 min. A total measurement uncertainty of -70% to +40% was estimated.

Gamma ray scanner systems for nondestructive assay of heterogeneous waste barrels

International Nuclear Information System (INIS)

Martz, H.E.; Decman, B.J.; Roberson, G.P.; Levai, F.

1997-01-01

Traditional gamma safeguards measurements have usually been performed using a segmented gamma scanning (SGS) system. The accuracy of this technique relies on the assumption that the sample matrix and the activity are both uniform for a segment. Waste barrels are often highly heterogeneous, span a wide range of composition and matrix type. The primary sources of error are all directly or indirectly related to a non-uniform measurement response associated with unknown radioactive source spatial distribution and heterogeneity of the matrix. These errors can be significantly reduced by some imaging techniques that measure exact spatial locations of sources and attenuation maps. In this paper we describe a joint R ampersand D effort between the Lawrence Livermore National Laboratory (LLNL) and the Institute of Nuclear Techniques (INT) of the Technical University, Budapest, to compare results obtained by two different gamma-ray nondestructive assay (NDA) systems used for imaging waste barrels. The basic principles are the same, but the approaches are different. Key factors to judge the adequacy of a method are the detection limit and the accuracy. Test drums representing waste to be measured are used to determine basic parameters of these techniques

Emulation of MS DOS Operational System on the Autonomous Crate-Controller with I8086 microprocessor

International Nuclear Information System (INIS)

Hons, Z.; Cizek, P.; Streit, V.

1988-01-01

KM-DOS operating system for CAMAC autonomous crate-controller based on Intel 8086/8087 microprocessor connected with Pravec-16 IBM PC is described. The KM-DOS system fully emulates the MS DOS environment on the CAMAC controller. Thus ASSEMBLER, FORTRAN, C and PASCAL programs compiled and linked on IBM PC and compatible can be run on the CAMAC controller and parall work of both computers is enabled

Relative performance of a TGS for the assay of drummed waste as function of collimator opening

International Nuclear Information System (INIS)

Kane, S.C.; Croft, S.; McClay, P.; Venkataraman, R.; Villani, M.F.

2007-01-01

Improving the safety, accuracy and overall cost effectiveness of the processes and methods used to characterize and handle radioactive waste is an on-going mission for the nuclear industry. An important contributor to this goal is the development of superior non-destructive assay instruments. The Tomographic Gamma Scanner (TGS) is a case in point. The TGS applies low spatial resolution experimental computed tomography (CT) linear attenuation coefficient maps with three-dimensional high-energy resolution single photon emission reconstructions. The results are presented as quantitative matrix attenuation corrected images and assay values for gamma-emitting radionuclides. Depending on a number of operational factors, this extends the diversity of waste forms that can be assayed, to a given accuracy, to items containing more heterogeneous matrix distributions and less uniform emission activity distributions. Recent advances have significantly extended the capability to a broader range of matrix density and to a wider dynamic range of surface dose rate. Automated systems sense the operational conditions, including the container type, and configure themselves accordingly. The TGS also provides a flexible data acquisition platform and can be used to perform far-field style measurements, classical segmented gamma scanner measurements, or to implement hybrid methods, such as reconstructions that use a priori knowledge to constrain the image reconstruction or the underlying energy dependence of the attenuation. A single, yet flexible, general purpose instrument of this kind adds several tiers of strategic and tactical value to facilities challenged by a diverse and difficult to assay waste streams. The TGS is still in the early phase of industrial uptake. There are only a small number of general purpose TGS systems operating worldwide, most being configured to automatically select between a few configurations appropriate for routine operations. For special investigations

Effect of radiant heat at the birth site in farrowing crates on hypothermia and behaviour in neonatal piglets

DEFF Research Database (Denmark)

Andersen, Heidi Mai-Lis; Pedersen, Lene Juul

2016-01-01

It has been documented that floor heating of the farrowing area in loose housed sows improves survival of piglets significantly. However, today, the majority of farrowing pens are designed with crating of sows and slatted floor at the birth site. The aim of this study was to investigate whether...... providing radiant heat at the birth site to new-born piglets in pens with crated sows reduced hypothermia, time to first milk intake and growth of the piglets during the 1st week. Second parity Danish Landrace×Yorkshire sows (n=36) were randomly divided into two groups: Control (CG) and heat (HG......). In the area behind the sow (zone 1), two radiant heat panels were mounted above the slatted floor in the HG. The farrowings were attended, and the heaters were turned on at birth of first piglet and turned off 12 h after. Birth time, time to leave zone 1, time to first contact with udder and time to first...

SWEPP PAN assay system uncertainty analysis: Active mode measurements of solidified aqueous sludge waste

International Nuclear Information System (INIS)

Blackwood, L.G.; Harker, Y.D.; Meachum, T.R.

1997-12-01

The Idaho National Engineering and Environmental Laboratory is being used as a temporary storage facility for transuranic waste generated by the US Nuclear Weapons program at the Rocky Flats Plant (RFP) in Golden, Colorado. Currently, there is a large effort in progress to prepare to ship this waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. In order to meet the TRU Waste Characterization Quality Assurance Program Plan nondestructive assay compliance requirements and quality assurance objectives, it is necessary to determine the total uncertainty of the radioassay results produced by the Stored Waste Examination Pilot Plant (SWEPP) Passive Active Neutron (PAN) radioassay system. This paper is one of a series of reports quantifying the results of the uncertainty analysis of the PAN system measurements for specific waste types and measurement modes. In particular this report covers active mode measurements of weapons grade plutonium-contaminated aqueous sludge waste contained in 208 liter drums (item description codes 1, 2, 7, 800, 803, and 807). Results of the uncertainty analysis for PAN active mode measurements of aqueous sludge indicate that a bias correction multiplier of 1.55 should be applied to the PAN aqueous sludge measurements. With the bias correction, the uncertainty bounds on the expected bias are 0 ± 27%. These bounds meet the Quality Assurance Program Plan requirements for radioassay systems

A l-nCi/g sensitivity transuranic waste assay system using pulsed neutron interrogation

International Nuclear Information System (INIS)

Kunz, W.E.; Atencio, J.D.; Caldwell, J.T.

1980-01-01

We have developed a pulsed thermal neutron interrogation system and have demonstrated a sub-1-nCi/g assay sensitivity for high density TRU wastes contained in 200-liter barrels. We detect prompt fission neutrons, resulting in greatly enhanced sensitivity compared to techniques in which delayed fission neutrons are detected. We observe a linear assay response over at least three orders of magnitude in 235 U (or 239 Pu) mass. We also have measured a flat (to +-10%) interrogation flux profile throughout the volume of a 200-liter barrel filled with 200 kg of sand and vermiculite, which indicates flatness of response to fissile material at different locations within the barrel

Innovations in the Assay of Un-Segregated Multi-Isotopic Grade TRU Waste Boxes with SuperHENC and FRAM Technology

International Nuclear Information System (INIS)

Simpson, A. P.; Barber, S.; Abdurrahman, N. M.

2006-01-01

The Super High Efficiency Neutron Coincidence Counter (SuperHENC) was originally developed by BIL Solutions Inc., Los Alamos National Laboratory (LANL) and Rocky Flats Environmental Technology Site (RFETS) for assay of transuranic (TRU) waste in Standard Waste Boxes (SWB) at Rocky Flats. This mobile system was a key component in the shipment of over 4,000 SWBs to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The system was WIPP certified in 2001 and operated at the site for four years. The success of this system, a passive neutron coincidence counter combined with high resolution gamma spectroscopy, led to the order of two new units, delivered to Hanford in 2004. Several new challenges were faced at Hanford: For example, the original RFETS system was calibrated for segregated waste streams such that metals, plastics, wet combustibles and dry combustibles were separated by 'Item Description Codes' prior to assay. Furthermore, the RFETS mission of handling only weapons grade plutonium, enabled the original SuperHENC to benefit from the use of known Pu isotopics. Operations at Hanford, as with most other DOE sites, generate un-segregated waste streams, with a wide diversity of Pu isotopics. Consequently, the new SuperHENCs are required to deal with new technical challenges. The neutron system's software and calibration methodology have been modified to encompass these new requirements. In addition, PC-FRAM software has been added to the gamma system, providing a robust isotopic measurement capability. Finally a new software package has been developed that integrates the neutron and gamma data to provide a final assay results and analysis report. The new system's performance has been rigorously tested and validated against WIPP quality requirements. These modifications, together with the mobile platform, make the new SuperHENC far more versatile in handling diverse waste streams and allow for rapid redeployment around the DOE complex. (authors)

9 CFR 93.805 - Ports of entry, inspection, and treatment. 1

Science.gov (United States)

2010-01-01

... in paragraph (b)(3) of this section, and any plastic sheet used to wrap any shipping crate, shall be... shipping crate or vehicle containing the animal shall be removed, sealed in plastic bags, and incinerated... crate, plastic must be fastened around the shipping crate so that all animal waste, hay, straw, feed...

Isócrates y los orígenes de la educación cívica. Actualidad de un pensador clásico

Directory of Open Access Journals (Sweden)

José Fernández-Santillán

2016-01-01

Full Text Available Isócrates ha sido descuidado como una figura señera entre los grandes pensadores políticos de la Grecia antigua. El presente ensayo rescata el legado de este filósofo, particularmente su trabajo como educador cívico, hoy tan necesario para construir ciudadanía.El método que utilizó para promover la democracia fue la deliberación pública, no solamente a través de la discusión verbal sino también de la difusión de escritos. En consecuencia, Isócrates contribuyó a crear espacios de discusión muy semejantes a lo que ahora conocemos como “esfera pública”.Lo que ponemos de relieve es que Isócrates creyó en el papel de la palabra como eje transformador tanto de los hombres como del régimen político. El ideal de democracia que tuvo en mente fue el régimen instaurado por Solón y Clístenes. Siempre tuvo en cuenta ese modelo para restaurar la vida cívica en Atenas y en las ciudades Estado de la Grecia antigua.

Validation of Non-Invasive Waste Assay System (Gamma Box Counter) Performance at AECL Whiteshell Laboratories - 13136

International Nuclear Information System (INIS)

Attas, E.M.; Bialas, E.; Rhodes, M.J.

2013-01-01

Low-level radioactive waste (LLW) in solid form, resulting from decommissioning and operations activities at AECL's Whiteshell Laboratories (WL), is packaged in B-25 and B-1000 standard waste containers and characterized before it is shipped to an on-site interim storage facility, pending AECL decisions on long term management of its LLW. Assay of the waste packages before shipment contributes to an inventory of the interim storage facility and provides data to support acceptance at a future repository. A key characterization step is a gamma spectrometric measurement carried out under standard conditions using an automated, multi-detector Waste Assay System (WAS), purchased from Antech Corporation. A combination of ORTEC gamma acquisition software and custom software is used in this system to incorporate multiple measurements from two collimated high-resolution detectors. The software corrects the intensities of the gamma spectral lines for geometry and attenuation, and generates a table of calculated activities or limits of detection for a user-defined list of radioisotopes that may potentially be present. Validation of WAS performance was a prerequisite to routine operation. Documentation of the validation process provides assurance of the quality of the results produced, which may be needed one or two decades after they were generated. Aspects of the validation included setting up a quality control routine, measurements of standard point sources in reproducible positions, study of the gamma background, optimization of user-selectable software parameters, investigation of the effect of non-uniform distribution of materials and radionuclides, and comparison of results with measurements made using other gamma detector systems designed to assay bulk materials. The following key components of the validation process have been established. A daily quality control routine has been instituted, to verify stability of the gamma detector operation and the background levels

APNEA/WIT system nondestructive assay capability evaluation plan for select accessibly stored INEL RWMC waste forms

International Nuclear Information System (INIS)

Becker, G.K.

1997-01-01

Bio-Imaging Research Inc. (BIR) and Lockheed Martin Speciality Components (LMSC) are engaged in a Program Research and Development Agreement and a Rapid Commercialization Initiative with the Department of Energy, EM-50. The agreement required BIR and LMSC to develop a data interpretation method that merges nondestructive assay and nondestructive examination (NDA/NDE) data and information sufficient to establish compliance with applicable National TRU Program (Program) waste characterization requirements and associated quality assurance performance criteria. This effort required an objective demonstration of the BIR and LMSC waste characterization systems in their standalone and integrated configurations. The goal of the test plan is to provide a mechanism from which evidence can be derived to substantiate nondestructive assay capability and utility statement for the BIT and LMSC systems. The plan must provide for the acquisition, compilation, and reporting of performance data thereby allowing external independent agencies a basis for an objective evaluation of the standalone BIR and LMSC measurement systems, WIT and APNEA respectively, as well as an expected performance resulting from appropriate integration of the two systems. The evaluation is to be structured such that a statement regarding select INEL RWMC waste forms can be made in terms of compliance with applicable Program requirements and criteria

Non-destructive assay of radioactive waste

International Nuclear Information System (INIS)

Eid, C.; Bernard, P.

1990-01-01

The nuclear fuel cycle generates a large variety of waste containing Pu. After treatment and conditioning the final destination of this waste is either to be disposed by shallow land burial or in underground geological repositories. The method of disposal is determined by the quantity of Pu contained in the waste to be disposed of. For this reason and taking into account the rigorous requirements of the safety authorities concerning the protection of people and the environment, it is most important to determine accurately the Pu contents in the waste. Separate abstracts were prepared for 28 papers in this book

PROMETHEE: An Alpha Low Level Waste Assay System Using Passive and Active Neutron Measurement Methods

International Nuclear Information System (INIS)

Passard, Christian; Mariani, Alain; Jallu, Fanny; Romeyer-Dherbey, Jacques; Recroix, Herve; Rodriguez, Michel; Loridon, Joel; Denis, Caroline; Toubon, Herve

2002-01-01

The development of a passive-active neutron assay system for alpha low level waste characterization at the French Atomic Energy Commission is discussed. Less than 50 Bq[α] (about 50 μg Pu) per gram of crude waste must be measured in 118-l 'European' drums in order to reach the requirements for incinerating wastes. Detection limits of about 0.12 mg of effective 239 Pu in total active neutron counting, and 0.08 mg of effective 239 Pu coincident active neutron counting, may currently be detected (empty cavity, measurement time of 15 min, neutron generator emission of 1.6 x 10 8 s -1 [4π]). The most limiting parameters in terms of performances are the matrix of the drum - its composition (H, Cl...), its density, and its heterogeneity degree - and the localization and self-shielding properties of the contaminant

Survey of EEC solid waste arisings and performance of non-destructive assay systems

International Nuclear Information System (INIS)

Bremner, W.B.; Adaway, D.W.; Yates, A.

1992-01-01

This report covers the work carried out during an one-year contract which surveyed the radioactive solid waste arisings in EEC Member States and also tabulated information on the performance of the non-destructive assay (NDA) system used. The work was jointly carried out with CEA partners at Cadarache and Paris. The tabulated data give information on types, packaging, associated activity, and NDA capability of the utilities or research organisations. Some short comings in NDA capabilities are identified and possible solutions are given

Safeguards and Non-destructive Assay

International Nuclear Information System (INIS)

Carchon, R.; Bruggeman, M.

2001-01-01

SCK-CEN's programme on safeguards and non-destructive assay includes: (1) various activities to assure nuclear materials accountancy; (2) contributes to the implementation of Integrated Safeguards measures in Belgium and to assist the IAEA through the Belgian Support Programme; (3) renders services to internal and external customers in the field of safeguards; (4) improves passive neutron coincidence counting techniques for waste assay and safeguards verification measurements by R and D on correlation algorithms implemented via software or dedicated hardware; (5) improves gamma assay techniques for waste assay by implementing advanced scanning techniques and different correlation algorithms; and (6) develops numerical calibration techniques. Major achievements in these areas in 2000 are reported

The nondestructive assay of 55-gallon drums containing uranium and transuranic waste using passive-active shufflers

International Nuclear Information System (INIS)

Rinard, P.M.; Adams, E.L.; Menlove, H.O.; Sprinkle, J.K. Jr.

1992-11-01

This study has been completed to characterize and improve the performance of passive-active neutron (PAN) shufflers in assaying 55gal. drums of nuclear facility waste for uranium and transuranic elements. Over 1700 active measurements and 800 passive measurements were made using 28 different matrices. Some of the matrices had homogeneous distributions of known amounts of moderating and absorbing materials, whereas others were less well characterized. Some of the well-characterized matrices simulate facility waste better than the others,especially matrices of paper, iron, polyethylene in nine different densities (with and without neutron poisons), alumina trap material, and concrete blocks

SVX Sequence Crate Custom J1 Backplane

International Nuclear Information System (INIS)

Utes, M.

1997-01-01

The Custom J1 Backplane is a full length (21 slot) user specified custom 3U backplane to be used in the J1 position. Slot spacing is identical to that used for VME (0.8-inch), and each backplane shall fit into a standard Eurocard VME style crate. The purpose of the Custom J1 Backplane is to: (1) Provide +5 volt power to slots 1 through 21; (2) Provide -5.2 volt power to slots 1 through 21; (3) Provide five bits of geographic addressing to slots 2 through 21. Slot 2 will have all five bits pulled low; slot 21 will have the value 10100. See Appendix A; (4) Route a differential 1553 signal from a triaxial bulkhead connector to slots 2 through 11. This differential signal is bussed as a daisy chain. A 75 ohm resistor to ground shall be located near the last destination slot for each of these two signals; (5) Route a second differential 1553 signal from a triaxial bulkhead connector to slots 12 through 21. This differential signal is bussed as a daisy chain. A 75 ohm resistor to ground shall be located near the last destination slot for each of these two signals; (6) Route two NRZ signals and two Clock signals from slot 1 to each of slots 2 through 21. These are individual signals, not bussed.

ASSESSMENT OF TOXICITY OF INDUSTRIAL WASTES USING CROP PLANT ASSAYS

Directory of Open Access Journals (Sweden)

Carmen Alice Teacă

2008-11-01

Full Text Available Environmental pollution has a harmful action on bioresources, including agricultural crops. It is generated through many industrial activities such as mining, coal burning, chemical technology, cement production, pulp and paper industry, etc. The toxicity of different industrial wastes and heavy metals excess was evaluated using crop plant assays (germination and hydroponics seedlings growth tests. Experimental data regarding the germination process of wheat (from two cultivars and rye seeds in the presence of industrial wastes (thermal power station ash, effluents from a pre-bleaching stage performed on a Kraft cellulose – chlorinated lignin products or chlorolignin, along with use of an excess of some heavy metals (Zn and Cu are presented here. Relative seed germination, relative root elongation, and germination index (a factor of relative seed germination and relative root elongation were determined. Relative root elongation and germination index were more sensitive indicators of toxicity than seed germination. The toxic effects were also evaluated in hydroponics experiments, the sensitivity of three crop plant species, namely Triticum aestivum L. (wheat, Secale cereale (rye, and Zea mays (corn being compared. Physiological aspects, evidenced both by visual observation and biometric measurements (mean root, aerial part and plant length, as well as the cellulose and lignin content were examined.

Sobre a presença de Sócrates na psicanálise

Directory of Open Access Journals (Sweden)

Anna Carolina Lo Bianco

2001-01-01

Full Text Available Não tendo deixado uma obra escrita, podemos dizer que o pensamento de Sócrates que chega até nós é fundado sobre um ponto básico, central e caro também à experiência psicanalítica: o da presença diante do outro. O artigo examina as características que cercam o exercício do procedimento socrático, ressaltando o impacto que ele tem sobre o interlocutor. Procura, em seguida, tomar a sua riqueza de princípios para ver, com as lentes da própria psicanálise, em que estes oferecem algumas condições de possibilidade para o melhor desenvolvimento de suas formulações.

Packaging waste prevention in the distribution of fruit and vegetables: An assessment based on the life cycle perspective.

Science.gov (United States)

Tua, Camilla; Nessi, Simone; Rigamonti, Lucia; Dolci, Giovanni; Grosso, Mario

2017-04-01

In recent years, alternative food supply chains based on short distance production and delivery have been promoted as being more environmentally friendly than those applied by the traditional retailing system. An example is the supply of seasonal and possibly locally grown fruit and vegetables directly to customers inside a returnable crate (the so-called 'box scheme'). In addition to other claimed environmental and economic advantages, the box scheme is often listed among the packaging waste prevention measures. To check whether such a claim is soundly based, a life cycle assessment was carried out to verify the real environmental effectiveness of the box scheme in comparison to the Italian traditional distribution. The study focused on two reference products, carrots and apples, which are available in the crate all year round. An experience of a box scheme carried out in Italy was compared with some traditional scenarios where the product is distributed loose or packaged at the large-scale retail trade. The packaging waste generation, 13 impact indicators on environment and human health and energy consumptions were calculated. Results show that the analysed experience of the box scheme, as currently managed, cannot be considered a packaging waste prevention measure when compared with the traditional distribution of fruit and vegetables. The weaknesses of the alternative system were identified and some recommendations were given to improve its environmental performance.

Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program. Revision 1

International Nuclear Information System (INIS)

1997-01-01

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) consists of a series of tests conducted on a regular frequency to evaluate the capability for nondestructive assay of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed with TRU waste characterization systems. Measurement facility performance will be demonstrated by the successful analysis of blind audit samples according to the criteria set by this Program Plan. Intercomparison between measurement groups of the DOE complex will be achieved by comparing the results of measurements on similar or identical blind samples reported by the different measurement facilities. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess the performance of measurement groups regarding compliance with established Quality Assurance Objectives (QAOs). As defined for this program, a PDP sample consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components, once manufactured, will be secured and stored at each participating measurement facility designated and authorized by Carlsbad Area Office (CAO) under secure conditions to protect them from loss, tampering, or accidental damage

Enhancing anaerobic digestion of food waste through biochemical methane potential assays at different substrate: inoculum ratios.

Science.gov (United States)

Hobbs, Shakira R; Landis, Amy E; Rittmann, Bruce E; Young, Michelle N; Parameswaran, Prathap

2018-01-01

Food waste has a high energy potential that can be converted into useful energy in the form of methane via anaerobic digestion. Biochemical Methane Potential assays (BMPs) were conducted to quantify the impacts on methane production of different ratios of food waste. Anaerobic digester sludge (ADS) was used as the inoculum, and BMPs were performed at food waste:inoculum ratios of 0.42, 1.42, and 3.0g chemical oxygen demand/g volatile solids (VS). The 1.42 ratio had the highest CH 4 -COD recovery: 90% of the initial total chemical oxygen demand (TCOD) was from food waste, followed by ratios 0.42 and 3.0 at 69% and 57%, respectively. Addition of food waste above 0.42 caused a lag time for CH 4 production that increased with higher ratios, which highlighted the negative impacts of overloading with food waste. The Gompertz equation was able to represent the results well, and it gave lag times of 0, 3.6 and 30days and maximum methane productions of 370, 910, and 1950mL for ratios 0.42, 1.42 and 3.0, respectively. While ratio 3.0 endured a long lag phase and low VSS destruction, ratio 1.42 achieved satisfactory results for all performance criteria. These results provide practical guidance on food-waste-to-inoculum ratios that can lead to optimizing methanogenic yield. Copyright © 2017 Elsevier Ltd. All rights reserved.

INEL test plan for evaluating waste assay systems

International Nuclear Information System (INIS)

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP

INEL test plan for evaluating waste assay systems

Energy Technology Data Exchange (ETDEWEB)

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP.

Operability test procedure for TRUSAF assayer software upgrade

International Nuclear Information System (INIS)

Cejka, C.C.

1995-01-01

This OTP is to be used to ensure the operability of the Transuranic Waste Assay System (TRUWAS). The system was upgraded and requires a retest to assure satisfactory operation. The upgrade consists of an AST 486 computer to replace the IBM-PC/XT, and a software upgrade (CNEUT). The software calculations are performed in the same manner as in the previous system (NEUT), however, the new software is written in C Assembly Language. CNEUT is easier to use and far more powerful than the previous program. The TRUWAS is used to verify the TRU content of waste packages sent for storage in the Transuranic Storage and Assay Facility (TRUSAF). The TRUSAF is part of Westinghouse Hanford's certification program for waste to be shipped to the Waste Isolation Pilot Plant (WIPP) in New Mexico. The Transuranic Waste Assayer uses a combination passive-active neutron interrogation system to determine the TRU content of 55-gallon waste drums. The system consists of a shielded assay chamber; Deuterium-Tritium neutron generator; Helium-3 proportional counters; drum handling system; electronics including preamplifier, amplifier, and discriminator for each of the counter packages; and an AST 486 computer/printer system for data acquisition and analysis. The system can detect down to TRU levels of 10 nCi/g in the waste matrix. The equipment to be tested is: Assay Chamber Door Drum Turntable and Automatic Loading Platform Interlocks Assayer Software; and IBM computer/printer software. The objective of the test is to verify that the system is operational with the AST 486 computer, the software used in the new computer system correctly calculates TRU levels, and the new computer system is capable of storing and retrieving data

Management of solid wastes during decommissioning of research reactors. Evaluation of gross clearance levels and mathematical simulation of solid waste assay techniques

International Nuclear Information System (INIS)

Gopalakrishnan, R.K.; Sobhan Babu, K.; Sharma, D.N.

2008-01-01

Full text: Decommissioning of nuclear facilities constitute a challenge mainly due to the huge and complex nature of radioactive waste generated during this process. In the context of management and disposal of waste and reuse/recycle of usable materials during decommissioning of reactors, clearance levels for relevant radio nuclides are of vital importance. Radionuclide specific clearance levels are developed by IAEA and such levels allow the facility for free release of materials to the environment without further regulatory consideration. An effort has been made in this paper to establish clearance levels for radionuclides associated with various system and structural components of a research reactor and rather than radionuclide specific clearance levels, these values are derived for gross activity concentration, which is more practical for radioactive waste categorization, disposal and reuse or recycle of usable materials. The first step towards the derivation of clearance levels is the calculation of annual doses relating to unit activity concentration for each nuclide using various enveloping scenarios. After the estimation of doses, the limiting enveloping scenario (the one that gives the highest dose) is identified. The clearance levels are then derived by dividing the reference dose level (10 μSv/y) by the annual dose calculated per unit activity concentration for the limiting enveloping scenario The clearance level for gross beta-gamma activity concentration is then evaluated as the product of the limiting clearance level and the number of radionuclides characterized for the structural components. Simulation studies were also carried out for the design of a monitoring system for estimation of activity concentration of the decommissioned materials, especially rubbles/ concrete, using mathematical models. Conventional solid waste assay techniques would not suffice to the requirement of decommissioning waste categorization since very low level activity

SRTC Spreadsheet to Determine Relative Percent Difference (RPD) for Duplicate Waste Assay Results and to Perform the RPD Acceptance Test

International Nuclear Information System (INIS)

Casella, V.R.

2002-01-01

This report documents the calculations and logic used for the Microsoft(R) Excel spreadsheet that is used at the 773-A Solid Waste Assay Facility for evaluating duplicate analyses, and validates that the spreadsheet is performing these functions correctly

An expert system framework for nondestructive waste assay

International Nuclear Information System (INIS)

Becker, G.K.

1996-01-01

Management and disposition of transuranic (RU) waste forms necessitates determining entrained RU and associated radioactive material quantities as per National RU Waste Characterization Program requirements. Technical justification and demonstration of a given NDA method used to determine RU mass and uncertainty in accordance with program quality assurance is difficult for many waste forms. Difficulties are typically founded in waste NDA methods that employ standards compensation and/or employment of simplifying assumptions on waste form configurations. Capability to determine and justify RU mass and mass uncertainty can be enhanced through integration of waste container data/information using expert system and empirical data-driven techniques with conventional data acquisition and analysis. Presented is a preliminary expert system framework that integrates the waste form data base, alogrithmic techniques, statistical analyses, expert domain knowledge bases, and empirical artificial intelligence modules into a cohesive system. The framework design and bases in addition to module development activities are discussed

Innovative Applications of In Situ Gamma Spectroscopy for Non-destructive Assay of Transuranic Wastes

International Nuclear Information System (INIS)

Watters, D.J.; Weismann, J.J.; Duke, S.J.; Nicosia, W.C.

2009-01-01

Cabrera Services (CABRERA), under contract to National Security Technologies, LLC (NSTec), supported the transuranic (TRU) waste reduction initiative at the Radioactive Waste Management Complex of the Nevada Test Site (NTS). CABRERA developed advanced NDA techniques for oversized boxes (OSB) and drums using in situ gamma spectroscopy during several phases of the project. A more thorough characterization method was employed during the planning phase of the project to better understand the TRU content and distribution within each container, while a comprehensive NDA program was designed and implemented during the intrusive phase that guided waste segregation and re-packaging of both TRU and low-level wastes (LLW). NSTec took receipt of 58 oversized boxes of suspect TRU waste from Lawrence Livermore National Lab (LLNL). TRU waste is defined as greater than 3.7 kilobecquerels per gram [kBq/g] (100 nanocuries (nCi)/g) activity from alpha-emitting radionuclides with atomic number greater than 92 having a half-life greater than 20 years. Each box was custom-made to house a variety of suspect TRU wastes resulting from years of weapons program research, development, and testing. Since their arrival at NTS, the boxes have undergone several iterations of non-destructive assay (NDA) in preparation for the comprehensive repackaging effort. NDA has included two rounds of in situ gamma spectroscopy and real-time radiography (RTR) scans that were videotaped. Contents have been confirmed to include glove boxes, HEPA filters and their housings, and assorted process equipment and piping. TRU content was determined via directly measuring plutonium-239 (Pu-239), americium-241 (Am-241), and other radionuclides, while adding calculated results for non-measurable nuclides using reliable scaling factors developed from acceptable knowledge (AK). Advantages of CABRERA's NDA methods included: - More NDA information is available in the same amount of counting time, allowing NSTec to make more

Electronics system for transuranic waste assays using a photon interrogation technique

International Nuclear Information System (INIS)

Johnson, L.O.; Lawrence, R.S.

1979-12-01

This report documents the development of electronics for a neutron detection system used in experiments to demonstrate the feasibility of a photon interrogation technique for transuranic (TRU) waste assays. The system consists of the neutron detection and signal conditioning circuits, variable time-gate generators, and a data acquisition system. The data acquisition system is configured using commercially available scalers, timers, teletype, and control components. The remainder of the system, with the exception of the neutron detectors, uses components designed in-house. The neutron detection system consists of 3 He proportional counters installed in a polyethylene moderator assembly. The counters are direct-coupled to a high-count-rate, current-sensitive preamplifier. The preamplifier and an additional two-stage amplifier are also installed in the moderator assembly. Signal conditioning includes baseline restoration and fast discrimination. A variable time-gate generator with logic gates allows for separation of prompt and delayed neutron counts, and generation of prompt and delayed deadtimes. The 3 He proportional counters will detect not only the neutrons from the TRU waste sample, but also the high-energy photons used to induce fission in the sample. The burst of photons (gamma flash) tends to overload and paralyze the electronics. This system has been designed to recover from a worst-case gamma flash overload within 10 microseconds. The system has met all the requirements generated for the photon interrogation experiments

Sócrates, la "Piedad" y los márgenes de la convivencia cívica

OpenAIRE

Beneitez, José Manuel

2006-01-01

La polis clásica fue producto del pluralismo cívico y no conoció ningún dogmatismo de carácter político o religioso; sin embargo, la "piedad" (hósios, eusébeia) sirvió de piedra de toque para consolidar la convivencia cívica. Atenas, la primera democracia que hubo en el mundo, afamada por reinar en ella la libertad de palabra, fue la misma que silenció a Sócrates. Al célebre filósofo se le condenó a morir por no creer en los dioses de su ciudad, por haber introducido otros nuev...

Selection of non-destructive assay methods: Neutron counting or calorimetric assay?

International Nuclear Information System (INIS)

Cremers, T.L.; Wachter, J.R.

1994-01-01

The transition of DOE facilities from production to D ampersand D has lead to more measurements of product, waste, scrap, and other less attractive materials. Some of these materials are difficult to analyze by either neutron counting or calorimetric assay. To determine the most efficacious analysis method, variety of materials, impure salts and hydrofluorination residues have been assayed by both calorimetric assay and neutron counting. New data will be presented together with a review of published data. The precision and accuracy of these measurements are compared to chemistry values and are reported. The contribution of the gamma ray isotopic determination measurement to the overall error of the calorimetric assay or neutron assay is examined and discussed. Other factors affecting selection of the most appropriate non-destructive assay method are listed and considered

Recommendations for CAMAC Serial Highway drivers and LAM Graders for the SCC-L2 Serial Crate Controller

International Nuclear Information System (INIS)

1978-01-01

The functional requirements of Drivers for the CAMAC Serial Highway defined in IEEE Standard 595-1976 are described. The description is independent of the implementation, and in particular no assumption is made about the boundary between hardware and software within the Driver. Topics covered are the user interface, the supporting system services required, demand handling, and a detailed discussion of the message analysis for various levels of error recovery. An appendix describes the recommended features of LAM Graders for use with the Serial Crate Controller Type L2 of IEEE Std 595-1976

Calibration method for a radwaste assay system

International Nuclear Information System (INIS)

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

2004-01-01

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

Opto-box: Optical modules and mini-crate for ATLAS pixel and IBL detectors

Directory of Open Access Journals (Sweden)

Bertsche David

2016-01-01

Full Text Available The opto-box is a custom mini-crate for housing optical modules which process and transfer optoelectronic data. Many novel solutions were developed for the custom design and manufacturing. The system tightly integrates electrical, mechanical, and thermal functionality into a small package of size 35×10x8 cm3. Special attention was given to ensure proper shielding, grounding, cooling, high reliability, and environmental tolerance. The custom modules, which incorporate Application Specific Integrated Circuits, were developed through a cycle of rigorous testing and redesign. In total, fourteen opto-boxes have been installed and loaded with modules on the ATLAS detector. They are currently in operation as part of the LHC run 2 data read-out chain. This conference proceeding is in support of the poster presented at the International Conference on New Frontiers in Physics (ICNFP 2015 [1].

Pu-238 assay performance with the Canberra IQ3 system

Energy Technology Data Exchange (ETDEWEB)

Booth, L.; Gillespie, B.; Seaman, G.

1997-11-01

Canberra Industries has recently completed a demonstration project at the Westinghouse Savannah River Site (WSRC) to characterize 55-gallon drums containing Pu-238 contaminated waste. The goal of this project was to detect and quantify Pu-238 contaminated waste. The goal of this project was to detect and quantify Pu-238 waste to detection limits of less than 50 nCi/g using gamma assay techniques. This would permit reclassification of these drums from transuranic (TRU) waste to low-level waste (LLW). The instrument used for this assay was a Canberra IQ3 high sensitivity gamma assay system, mounted in a trailer. The results of the measurements demonstrate achievement of detection levels as low as 1 nCi/g for low density waste drums, and good correlation with known concentrations in several test drums. In addition, the data demonstrates significant advantages for using large area low-energy germanium detectors for achieving the lowest possible MDAs for gamma rays in the 80-250 keV range. 1 fig., 2 tabs.

Waste assaying and radiation monitoring equipment at the waste management centre of NPP Leningrad

Directory of Open Access Journals (Sweden)

Šokčić-Kostić Marina

2006-01-01

Full Text Available The waste accumulated in the past at the Nuclear Power Plant Leningrad has to be sorted and packed in an optimal way. In the area of waste treatment and management, the completeness and quality of direct monitoring are of the outmost importance for the validity of, and confidence in, both practicable waste management options and calculations of radiological impacts. Special monitoring systems are needed for this purpose. Consistent with the scale of work during the waste treatment procedures and the complexity of the plant data have to be collected from characteristic parts in various treatment stages. To combine all the information, a tracking procedure is needed during the waste treatment process to characterize the waste for interim and/or final disposal. RWE NUKEM GmbH has developed special customer-tailored systems which fulfill the specifications required by plant operation and by the authorities.

Metrological tests of a 200 L calibration source for HPGE detector systems for assay of radioactive waste drums

International Nuclear Information System (INIS)

Boshkova, T.; Mitev, K.

2016-01-01

In this work we present test procedures, approval criteria and results from two metrological inspections of a certified large volume "1"5"2Eu source (drum about 200 L) intended for calibration of HPGe gamma assay systems used for activity measurement of radioactive waste drums. The aim of the inspections was to prove the stability of the calibration source during its working life. The large volume source was designed and produced in 2007. It consists of 448 identical sealed radioactive sources (modules) apportioned in 32 transparent plastic tubes which were placed in a wooden matrix which filled the drum. During the inspections the modules were subjected to tests for verification of their certified characteristics. The results show a perfect compliance with the NIST basic guidelines for the properties of a radioactive certified reference material (CRM) and demonstrate the stability of the large volume CRM-drum after 7 years of operation. - Highlights: • Large (200 L) volume drum source designed, produced and certified as CRM in 2007. • Source contains 448 identical sealed radioactive "1"5"2Eu sources (modules). • Two metrological inspections in 2011 and 2014. • No statistically significant changes of the certified characteristics over time. • Stable calibration source for HPGe-gamma radioactive waste assay systems.

In-situ measurement of texture and elastic strains with HIPPO-CRATES

International Nuclear Information System (INIS)

Hartig, Ch.; Vogel, S.C.; Mecking, H.

2006-01-01

In this paper, the micromechanical interaction between constituents of a metallic material during elastic and plastic deformation are analyzed by comparing experimental results with modeling predictions. This comparison aims at determining the locally acting internal stresses, the spatial distribution of strains and the rules allowing deriving the macroscopic behavior of the material from the behavior of its microscopic constituents. We report the application of a new deformation apparatus CRATES, which allows measuring texture and crystal lattice spacings, and from these crystal lattice strains, using neutron diffraction. From the in-situ measured elastic lattice strains ε hkl the corresponding local stresses can be derived. The deformation apparatus allows uni-axial tensile or compressive deformation up to 100 kN and is specifically designed for use in the HIPPO neutron time-of-flight diffractometer. In this paper, we report initial results on an iron-copper model system (Fe100, Fe33Cu67, Fe67Cu33, vol.%) and commercial magnesium alloys (Mg-AZ31 and Mg-AZ80). Finite element calculations using a crystal-plastic constitutive law, allowing for shear and hardening of crystallographic slip-systems, were used for the interpretation of the measurements

Standard test method for non-destructive assay of nuclear material in waste by passive and active neutron counting using a differential Die-away system

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This test method covers a system that performs nondestructive assay (NDA) of uranium or plutonium, or both, using the active, differential die-away technique (DDT), and passive neutron coincidence counting. Results from the active and passive measurements are combined to determine the total amount of fissile and spontaneously-fissioning material in drums of scrap or waste. Corrections are made to the measurements for the effects of neutron moderation and absorption, assuming that the effects are averaged over the volume of the drum and that no significant lumps of nuclear material are present. These systems are most widely used to assay low-level and transuranic waste, but may also be used for the measurement of scrap materials. The examples given within this test method are specific to the second-generation Los Alamos National Laboratory (LANL) passive-active neutron assay system. 1.1.1 In the active mode, the system measures fissile isotopes such as 235U and 239Pu. The neutrons from a pulsed, 14-MeV ne...

Waste management bibliography 1979-1981

International Nuclear Information System (INIS)

Oakley, D.T.

1981-10-01

The Los Alamos National Laboratory is conducting a variety of research and development to ensure the safety of storing and treating all types of radioactive wastes. These activities include the assay and sorting of waste, the interaction of waste with the earth, and the treatment of waste to reduce the volume and mobility of radionuclides in waste. The practical lessons learned from safely storing waste at Los Alamos since the mid-1940s are an ingredient in determining the direction of our research. National waste management programs are structured according to categories of waste, for example, high level, low level, mill tailings, and transuranic. In this bibliography publications are listed since 1979 according to the following disciplines to show the relevance of work to more than one category of waste: summary and overview; material science; environmental studies; geochemistry and geology; waste assay; soil/waste interactions shallow land burial; volume reduction and technology development; and nonradioactive wastes

Clinical records anonymisation and text extraction (CRATE): an open-source software system.

Science.gov (United States)

Cardinal, Rudolf N

2017-04-26

Electronic medical records contain information of value for research, but contain identifiable and often highly sensitive confidential information. Patient-identifiable information cannot in general be shared outside clinical care teams without explicit consent, but anonymisation/de-identification allows research uses of clinical data without explicit consent. This article presents CRATE (Clinical Records Anonymisation and Text Extraction), an open-source software system with separable functions: (1) it anonymises or de-identifies arbitrary relational databases, with sensitivity and precision similar to previous comparable systems; (2) it uses public secure cryptographic methods to map patient identifiers to research identifiers (pseudonyms); (3) it connects relational databases to external tools for natural language processing; (4) it provides a web front end for research and administrative functions; and (5) it supports a specific model through which patients may consent to be contacted about research. Creation and management of a research database from sensitive clinical records with secure pseudonym generation, full-text indexing, and a consent-to-contact process is possible and practical using entirely free and open-source software.

Neonatal piglet traits of importance for survival in crates and indoor pens

DEFF Research Database (Denmark)

Pedersen, Lene Juul; Berg, Peer; Jørgensen, Grete

2011-01-01

The primary aim of the present study was to investigate whether the same piglet traits contributed to the same causes of neonatal piglet mortality in crates (CT) and pens (PN). Gilts originating from 2 distinct genetic groups that differed in breeding value for piglet survival rate at d 5 (SR5......) were used. These were distributed to farrow in either PN or CT as follows: high-SR5 and CT (n = 30); low-SR5 and CT (n = 27); high-SR5 and PN (n = 22); and low-SR5 and PN (n = 24). Data on individual piglets were collected at birth, including interbirth interval; birth order; birth weight; rectal...... with a logit link function. No significant effect (NS) of housing was observed on the odds of a piglet being stillborn (F1,73 = 0.1, NS), being crushed (F1,53 = 1.4, NS), or dying of starvation (F1,53 = 0.3, NS). No significant differences were observed between the 2 genetic groups for any category...

Firmware development and testing of the ATLAS IBL Back-Of-Crate card

CERN Document Server

Stramaglia, ME; The ATLAS collaboration

2014-01-01

ATLAS is one of the four big LHC experiments and currently its Pixel-Detector is being upgraded with a new innermost 4th layer, the Insertable B-Layer (IBL). The upgrade will result in better tracking efficiency and compensate radiation damages of the Pixel-Detector. Newly developed front-end electronics and the higher than originally planned LHC luminosity will require a complete re-design of the Off-Detector-Electronics consisting of the Back-Of-Crate card (BOC) and the Read-Out-Driver (ROD). The main purpose of the BOC card is the distribution of the LHC clock to all Pixel-Detector components as well as interfacing the detector and the higher-level-readout optically. It is equipped with three Xilinx Spartan-6 FPGAs, one BOC Control FPGA (BCF) and two BOC Main FPGAs (BMF). The BMF are responsible for the signal processing of all incoming and outgoing data. The data-path to the detector is running a 40 MHz bi-phase-mark encoded stream. This stream is delayed by a fine delay block using Spartan-6 IODELAY prim...

Firmware development and testing of the ATLAS IBL Back Of Crate card

CERN Document Server

Stramaglia, Maria Elena; The ATLAS collaboration

2015-01-01

ATLAS is one of the four big LHC experiments and currently its Pixel Detector was upgraded with a new innermost 4th layer: the Insertable B-Layer (IBL). The upgrade will result in better tracking efficiency and compensate radiation damages of the Pixel-Detector. Newly developed front-end electronics and the higher than originally planned LHC luminosity required a complete re-design of the Off Detector Electronics consisting of the Back Of Crate card (BOC) and the Read Out Driver (ROD). The main purpose of the BOC card is the distribution of the LHC clock to all Pixel Detector components as well as interfacing the detector and the higher level readout optically. The data-path to the detector is running a 40 MHz bi phase mark (BPM) encoded stream. The 160 MHz 8b10b encoded data path from the detector is phase and word aligned in the firmware and then forwarded to the ROD after decoding. The ROD will send out the processed data which is then forwarded to the higher level readout by the BOC card. An overview of t...

A PC-based discrete tomography imaging software system for assaying radioactive waste containers

International Nuclear Information System (INIS)

Palacios, J.C.; Longoria, L.C.; Santos, J.; Perry, R.T.

2003-01-01

A PC-based discrete tomography imaging software system for assaying radioactive waste containers for use in facilities in Mexico has been developed. The software system consists of three modules: (i) for reconstruction transmission tomography, (ii) for reconstruction emission tomography, and (iii) for simulation tomography. The Simulation Module is an interactive computer program that is used to create simulated databases for input to the Reconstruction Modules. These databases may be used in the absence of physical measurements to insure that the tomographic theoretical models are valid and that the coding accurately describes these models. Simulation may also be used to determine the detection limits of the reconstruction methodology. A description of the system, the theory, and a demonstration of the systems capabilities is provided in the paper. The hardware for this system is currently under development

Development of an integrated assay facility

International Nuclear Information System (INIS)

Molesworth, T.V.; Bailey, M.; Findlay, D.J.S.; Parsons, T.V.; Sene, M.R.; Swinhoe, M.T.

1990-01-01

The I.R.I.S. concept proposed the use of passive examination and active interrogation techniques in an integrated assay facility. A linac would generate the interrogating gamma and neutron beams. Insufficiently detailed knowledge about active neutron and gamma interrogation of 500 litre drums of cement immobilised intermediate level waste led to a research programme which is now in its main experimental stage. Measurements of interrogation responses are being made using simulated waste drums containing actinide samples and calibration sources, in an experimental assay assembly. Results show that responses are generally consistent with theory, but that improvements are needed in some areas. A preliminary appraisal of the engineering and economic aspects of integrated assay shows that correct operational sequencing is required to achieve the short cycle time needed for high throughput. The main engineering features of a facility have been identified

Viabilidade técnica e econômica da caixa Embrapa para comercialização de tomate para consumo in natura Technical and economic viability of the Embrapa crate for marketing of fresh tomatoes

Directory of Open Access Journals (Sweden)

Nirlene J. Vilela

2002-06-01

Full Text Available Foram avaliadas as vantagens econômicas da nova embalagem desenvolvida pela Embrapa Hortaliças para comercialização de tomate para consumo in natura. A caixa tipo "K", embalagem mais usada no Brasil, tem grande número de características indesejáveis. Considerando os problemas da caixa tipo "K" e o alto índice de perdas pós-colheita na cadeia produtiva de hortaliças, a Embrapa Hortaliças iniciou um programa de pesquisa para o desenvolvimento de uma nova embalagem para tomate. O trabalho culminou com a definição da nova embalagem de plástico nomeada caixa Embrapa. Além de outras vantagens técnicas a nova embalagem, comparada com a caixa tipo "K", apresentou redução de perdas pós colheita (17%, considerando a conservação e integridade dos frutos. Para um horizonte de 5 anos, os indicadores econômicos para ambas embalagens, mostraram viabilidade econômica superior para a caixa Embrapa, sendo o valor presente líquido de, aproximadamente, R$ 60,7 mil e R$ 90,0 mil para a caixa tipo "K" e Caixa Embrapa, respectivamente. A taxa de benefício/custo foi de 4,80 e 7,80 para a caixa tipo "K" e caixa Embrapa, respectivamente. Considerando preços correntes e custos totais, a caixa Embrapa apresentou-se técnica e economicamente viável.The economic advantages of a new crate developed for commercialization of fresh tomatoes was evaluated. The Box type "K", name of the package for fresh vegetables crops mostly employed in Brazil, has many undesirables features. Considering the problems of box type "K" and the high index of post harvest losses in the production chain of vegetables, Embrapa Hortaliças started a research program focusing on the development of a new container for fresh tomatoes. This work ended with the adaptation of a new crate model made of plastic. This Embrapa crate showed comparative physical advantages of approximately 17% reduction in postharvest losses when compared to the box type K, considering conservation and

Los Alamos waste drum shufflers users manual

International Nuclear Information System (INIS)

Rinard, P.M.; Adams, E.L.; Painter, J.

1993-01-01

This user manual describes the Los Alamos waste drum shufflers. The primary purpose of the instruments is to assay the mass of 235 U (or other fissile materials) in drums of assorted waste. It can perform passive assays for isotopes that spontaneously emit neutrons or active assays using the shuffler technique as described on this manual

Computer-determined assay time based on preset precision

International Nuclear Information System (INIS)

Foster, L.A.; Hagan, R.; Martin, E.R.; Wachter, J.R.; Bonner, C.A.; Malcom, J.E.

1994-01-01

Most current assay systems for special nuclear materials (SNM) operate on the principle of a fixed assay time which provides acceptable measurement precision without sacrificing the required throughput of the instrument. Waste items to be assayed for SNM content can contain a wide range of nuclear material. Counting all items for the same preset assay time results in a wide range of measurement precision and wastes time at the upper end of the calibration range. A short time sample taken at the beginning of the assay could optimize the analysis time on the basis of the required measurement precision. To illustrate the technique of automatically determining the assay time, measurements were made with a segmented gamma scanner at the Plutonium Facility of Los Alamos National Laboratory with the assay time for each segment determined by counting statistics in that segment. Segments with very little SNM were quickly determined to be below the lower limit of the measurement range and the measurement was stopped. Segments with significant SNM were optimally assays to the preset precision. With this method the total assay time for each item is determined by the desired preset precision. This report describes the precision-based algorithm and presents the results of measurements made to test its validity

Making transuranic assay measurements using modern controllers

International Nuclear Information System (INIS)

Kuckertz, T.H.; Caldwell, J.T.; Medvick, P.A.; Kunz, W.E.; Hastings, R.D.

1987-01-01

This paper describes methodology and computer-controlled instrumentation developed at the Los Alamos National Laboratory that accurately performs nondestructive assays of large containers bearing transuranic wastes and nonradioactive matrix materials. These assay systems can measure fissile isotopes with 1-mg sensitivity and spontaneous neutron-emitting isotopes at a 10-mg sensitivity. The assays are performed by neutron interrogation, detection, and counting in a custom assay chamber. An International Business Machines Personal Computer (IBM-PC) is used to control the CAMAC-based instrumentation system that acquires the assay data. 6 refs., 7 figs

Solid waste handling

International Nuclear Information System (INIS)

Parazin, R.J.

1995-01-01

This study presents estimates of the solid radioactive waste quantities that will be generated in the Separations, Low-Level Waste Vitrification and High-Level Waste Vitrification facilities, collectively called the Tank Waste Remediation System Treatment Complex, over the life of these facilities. This study then considers previous estimates from other 200 Area generators and compares alternative methods of handling (segregation, packaging, assaying, shipping, etc.)

Evaluation of anaerobic co-digestion of dairy manure with food wastes via bio-methane potential assay and CSTR reactor.

Science.gov (United States)

Ye, Yulin; Zamalloa, Carlos; Lin, Hongjian; Yan, Mi; Schmidt, David; Hu, Bo

2015-01-01

The introduction of food wastes into anaerobic digestion (AD) brings a promising scenario of increasing feedstock availability and overall energy production from AD. This study evaluated the biodegradability and methane potential from co-digestion of two typical food wastes, kitchen waste and chicken fat, with dairy manure. For single substrate, the bio-methane potential assays showed that kitchen waste had the highest methane yield of 352 L-CH4 kg(-1)-VS added, 92% more than dairy manure alone. Chicken fat at the same Volatile Solid (VS) level (2 g L(-1)) inhibited bio-methane production. Addition of kitchen waste and chicken fat to a VS percentage of up to 40% improved overall methane yield by 44% and 34%, respectively. Synergistic effect was observed when either combining two or three substrates as AD feedstock, possibly as a result of increased biodegradability of organic materials in chicken fat and kitchen waste compared with dairy manure. Addition of chicken fat improved methane yield more than kitchen waste. However, addition of chicken fat VS over 0.8 g L(-1) should be cautiously done because it may cause reactor failure due to decrease in pH. The maximum methane yield was 425 L-CH4 kg(-1)-VS, achieved at a VS ratio of 2:2:1 for kitchen waste, chicken fat, and dairy manure. Results from batch AD experiment demonstrated that supplementing dairy manure to chicken fat and/or kitchen waste improved alkalinity of substrate due to the inclusion of more titratable bases in dairy manure, and therefore stabilized the methanogenesis and substantially improved biogas yield. A mixture of substrates of kitchen waste, chicken fat, and dairy manure at a ratio of 1:1:3 was fed to a continuously stirred tank reactor operated at organic loading rates of 3.28, 6.55, and 2.18 g-COD L(-1)-day (hydraulic retention time of 20, 10, and 30 days, respectively) under mesophilic condition, and methane production rate reached 0.65, 0.95, and 0.34 L-CH4 L(-1)-reactor-day.

Status of the WAND (Waste Assay for Nonradioactive Disposal) project as of July 1997

International Nuclear Information System (INIS)

Arnone, G.J.; Foster, L.A.; Foxx, C.L.; Hagan, R.C.; Martin, E.R.; Myers, S.C.; Parker, J.L.

1998-03-01

The WAND (Waste Assay for Nonradioactive Disposal) system can scan thought-to-be-clean, low-density waste (mostly paper and plastics) to determine whether the levels of any contaminant radioactivity are low enough to justify their disposal in normal public landfills or similar facilities. Such a screening would allow probably at least half of the large volume of low-density waste now buried at high cost in LANL's Rad Waste Landfill (Area G at Technical Area 54) to be disposed of elsewhere at a much lower cost. The WAND System consists of a well-shielded bank of six 5-in.-diam. phoswich scintillation detectors; a mechanical conveyor system that carries a 12-in.-wide layer of either shredded material or packets of paper sheets beneath the bank of detectors; the electronics needed to process the outputs of the detectors; and a small computer to control the whole system and to perform the data analysis. WAND system minimum detectable activities (MDAs) for point sources range from ∼20 dps for 241 Am to approximately 10 times that value for 239 Pu, with most other nuclides of interest being between those values, depending upon the emission probabilities of the radiations emitted (usually gamma rays and/or x-rays). The system can also detect beta particles that have energies ≥100 keV, but it is not easy to define an MDA based on beta radiation detection because of the greater absorption of beta particles relative to photons in low Z-materials. The only radioactive nuclides not detectable by the WAND system are pure alpha emitters and very-low-energy beta emitters. At this time, operating procedures and quality assurance procedures are in place and training materials are available to operators. The system is ready to perform useful work; however, it would be both possible and desirable to upgrade the electronic components and the analysis algorithms

Characterization of alpha low level waste in 118 litre drums by passive and active neutron measurements in the promethee assay system

International Nuclear Information System (INIS)

Jallu, F.; Passard, C.; Mariani, A.; Ma, J.L.; Baudry, G.; Romeyer-Dherbey, J.; Recroix, H.; Rodriguez, M.; Loridon, J.; Denis, C.; Toubon, H.

2003-01-01

This paper deals with the PROMETHEE (PROMpt, epithermal and THErmal interrogation experiment) waste assay system for alpha low level waste (LLW) characterization. This device, including both passive and active neutron measurement methods, is developed at the French Atomic Energy Commission (C.E.A.), Cadarache Centre, in cooperation with COGEMA. Its purpose is to reach the requirements for incinerating alpha waste (less than 50 Bq[α], i.e. about 50 μg of Pu per gram of raw waste) in 118 litre- > drums. The PROMETHEE development and progress are performed with the help of simulation based on the Monte Carlo code MCNP4 [1]. These calculations are coupled with specific experiments in order to confirm calculated results and to obtain characteristics that can not be approached by the simulation (background for example). This paper presents the PROMETHEE measurement cell, its current performances, and studies performed at the laboratory about the most limiting parameters such as the matrix of the drum - its composition (H, Cl..), its density and its heterogeneity degree -the localization and the self-shielding properties of the contaminant. (orig.)

Characterization of alpha low level waste in 118 litre drums by passive and active neutron measurements in the promethee assay system

Energy Technology Data Exchange (ETDEWEB)

Jallu, F.; Passard, C.; Mariani, A.; Ma, J.L.; Baudry, G.; Romeyer-Dherbey, J.; Recroix, H.; Rodriguez, M.; Loridon, J.; Denis, C. [French Atomic Energy Commission (C.E.A./Cadarache), DED/SCCD/LDMN, Durance (France); Toubon, H. [COGEMA, VELIZY-VILLACOUBLAY (France)

2003-07-01

This paper deals with the PROMETHEE (PROMpt, epithermal and THErmal interrogation experiment) waste assay system for alpha low level waste (LLW) characterization. This device, including both passive and active neutron measurement methods, is developed at the French Atomic Energy Commission (C.E.A.), Cadarache Centre, in cooperation with COGEMA. Its purpose is to reach the requirements for incinerating alpha waste (less than 50 Bq[{alpha}], i.e. about 50 {mu}g of Pu per gram of raw waste) in 118 litre-<> drums. The PROMETHEE development and progress are performed with the help of simulation based on the Monte Carlo code MCNP4 [1]. These calculations are coupled with specific experiments in order to confirm calculated results and to obtain characteristics that can not be approached by the simulation (background for example). This paper presents the PROMETHEE measurement cell, its current performances, and studies performed at the laboratory about the most limiting parameters such as the matrix of the drum - its composition (H, Cl..), its density and its heterogeneity degree -the localization and the self-shielding properties of the contaminant. (orig.)

Standard test method for nondestructive assay of nuclear material in scrap and waste by passive-Active neutron counting using 252Cf shuffler

CERN Document Server

American Society for Testing and Materials. Philadelphia

2008-01-01

1.1 This test method covers the nondestructive assay of scrap and waste items for U, Pu, or both, using a 252Cf shuffler. Shuffler measurements have been applied to a variety of matrix materials in containers of up to several 100 L. Corrections are made for the effects of matrix material. Applications of this test method include measurements for safeguards, accountability, TRU, and U waste segregation, disposal, and process control purposes (1, 2, 3). 1.1.1 This test method uses passive neutron coincidence counting (4) to measure the 240Pu-effective mass. It has been used to assay items with total Pu contents between 0.03 g and 1000 g. It could be used to measure other spontaneously fissioning isotopes such as Cm and Cf. It specifically describes the approach used with shift register electronics; however, it can be adapted to other electronics. 1.1.2 This test method uses neutron irradiation with a moveable Cf source and counting of the delayed neutrons from the induced fissions to measure the 235U equiva...

Neutron coincidence counting based on time interval analysis with dead time corrected one and two dimensional Rossi-alpha distributions: an application for passive neutron waste assay

International Nuclear Information System (INIS)

Bruggeman, M.; Baeten, P.; De Boeck, W.; Carchon, R.

1996-03-01

The report describes a new neutron multiplicity counting method based on Rossi-alpha distributions. The report also gives the necessary dead time correction formulas for the multiplicity counting method. The method was tested numerically using a Monte Carlo simulation of pulse trains. The use of this multiplicity method in the field of waste assay is explained: it can be used to determine the amount of fissile material in a waste drum without prior knowledge of the actual detection efficiency

Analytical protocol to study the food safety of (multiple-)recycled high-density polyethylene (HDPE) and polypropylene (PP) crates: Influence of recycling on the migration and formation of degradation products

NARCIS (Netherlands)

Coulier, L.; Orbons, H.G.M.; Rijk, R.

2007-01-01

An analytical protocol was set up and successfully applied to study the food safety of recycled HDPE and PP crates. A worst-case scenario was applied that focused not only on overall migration and specific migration of accepted starting materials but also on migratable degradation products of

Radioactive waste package assay facility. Volume 2. Investigation of active neutron and active gamma interrogation

International Nuclear Information System (INIS)

Bailey, M.; Bunce, L.J.; Findlay, D.J.S.; Jolly, J.E.; Parsons, T.V.; Sene, M.R.; Swinhoe, M.T.

1992-01-01

Volume 2 of this report describes the theoretical and experimental work carried out at Harwell on active neutron and active gamma interrogation of 500 litre cemented intermediate level waste drums. The design of a suitable neutron generating target in conjunction with a LINAC was established. Following theoretical predictions of likely neutron responses, an experimental assay assembly was built. Responses were measured for simulated drums of ILW, based on CAGR, Magnox and PCM wastes. Good correlations were established between quantities of 235 -U, nat -U and D 2 O contained in the drums, and the neutron signals. Expected sensitivities are -1g of fissile actinide and -100g of total actinide. A measure of spatial distribution is obtainable. The neutron time spectra obtained during neutron interrogation were more complex than expected, and more analysis is needed. Another area of discrepancy is the difference between predicted and measured thermal neutron flux in the drum. Clusters of small 3 He proportional counters were found to be much superior for fast neutron detection than larger diameter counters. It is necessary to ensure constancy of electron beam position relative to target(s) and drum, and prudent to measure the target neutron or gamma output as appropriate. 59 refs., 77 figs., 11 tabs

Advantages of the segregation step for the radioactive waste management

International Nuclear Information System (INIS)

Medeiros, Regina Bitelli; Mattos, Maria Fernanda S.S.

2002-01-01

Due to the increasing use of radioactive materials in the research activities, the waste management is essential to guarantee personnel safety and the preservation of the environmental quality. It is possible to determine the date of discharge in the public sewage treatment system based on the estimated activity of the radioactive waste and on the solid waste discharge limit of 74 Bq/g as recommended by the radiation protection rules. The goal of this work is to demonstrate the advantages of the waste segregation by specific activity as a means of minimization of the stored waste. The residual specific activity and volume were estimated in the several steps of assays using 32 P and 3 H. The storage times were calculated and compared with the estimated time considering the residual activity as 2 % of the total activity used in the experiment. The segregation by steps of the assay allowed for the reduction of the waste volume and stored time. In the assays with 3 H only 20 % of the total waste generated was stored and in the assays with 32 P it was possible to discharge 90 % of the radioactive waste after 38 days. (author)

IGA resistance of TT Alloy 690 and concentration behavior of Broached Egg Crate tube support configuration

International Nuclear Information System (INIS)

Suzuki, S.; Kusakabe, T.; Yamamoto, H.; Arioka, K.; Ochi, T.

1992-01-01

In order to improve the reliability of the Steam Generator (SG), TT Alloy 690 and BEC (Broached Egg Crate) type tube support plate has been developed. Some tests are carried out to heighten the reliability for these improvements all the more and the following results are obtained. (1) SERT test (Slow Extension Rate Test) made clear that TT690 has less IGA susceptibility in comparison with MA600. (2) The alkaline susceptibility on the occurrence of IGA/SCC on TT690 and MA600 obtained by SERT corresponds to that obtained by Model Boiler test. (3) By model boiler test, superior concentration behaviors for BEC type tube support plate configuration have been recognized in comparison with Drill type. This result is obtained by the joint research of the five utilities (Kansai Epco, Hokkaido Epco, Shikoku Epco, Kyushu Epco, JAPCO) and MHI

Transuranic contaminated waste form characterization and data base

International Nuclear Information System (INIS)

Kniazewycz, B.G.; McArthur, W.C.

1980-07-01

This volume contains 5 appendices. Title listing are: technologies for recovery of transuranics; nondestructive assay of TRU contaminated wastes; miscellaneous waste characteristics; acceptance criteria for TRU waste; and TRU waste treatment technologies

Quantitative CrAssphage PCR Assays for Human Fecal ...

Science.gov (United States)

Environmental waters are monitored for fecal pollution to protect public health and water resources. Traditionally, general fecal indicator bacteria are used; however, they cannot distinguish human fecal waste from pollution from other animals. Recently, a novel bacteriophage, crAssphage, was discovered by metagenomic data mining and reported to be abundant in and closely associated with human fecal waste. To confirm bioinformatic predictions, 384 primer sets were designed along the length of the crAssphage genome. Based upon initial screening, two novel crAssphage qPCR assays (CPQ_056 and CPQ_064) were designed and evaluated in reference fecal samples and water matrices. The assays exhibited high specificities (98.6%) when tested against a large animal fecal reference library and were highly abundant in raw sewage and sewage impacted water samples. In addition, CPQ_056 and CPQ_064 assay performance was compared to HF183/BacR287 and HumM2 methods in paired experiments. Findings confirm viral crAssphage qPCR assays perform at a similar level to well established bacterial human-associated fecal source identification technologies. These new viral based assays could become important water quality management and research tools. To inform the public.

O cidadão Sócrates e o filosofar numa democracia Socrates as a citizen and the act of philosophizing in a democracy

Directory of Open Access Journals (Sweden)

Roberto Goto

2010-04-01

Full Text Available Examinando o julgamento de Sócrates (470-399 a.C. por Atenas, no contexto da Guerra do Peloponeso (431-404 a.C., este texto busca as raízes, as razões e os significados de sua condenação nas críticas relações entre o filósofo e seus concidadãos. Neste caso - justamente no que podemos chamar de ''o caso Sócrates'' - o filósofo aparece (de conformidade com a Apologia escrita por Platão como um cidadão-filósofo que desafia o Estado ateniense e incomoda seus concidadãos na medida em que exerce a cidadania como uma forma de filosofar e pratica a filosofia como um direito e um dever de cidadania.This article examines the trial of Socrates (470-399 B.C. by Athens, in the context of the Peloponnesian War (431-404 B.C., searching for the roots, reasons and meanings of his condemnation in the critical relations between the philosopher and his fellow citizens. In this case - exactly in what we can call ''the Socrates case'' - the philosopher appears (according to Plato's Apology as a citizen-philosopher who challenges the Athenian State and disturbs his fellow citizens while he exercises citizenship as a form of philosophizing and practices philosophy as a right and a duty of citizenship.

Improvement of non-destructive fissile mass assays in α low-level waste drums: A matrix correction method based on neutron capture gamma-rays and a neutron generator

Science.gov (United States)

Jallu, F.; Loche, F.

2008-08-01

Within the framework of radioactive waste control, non-destructive assay (NDA) methods may be employed. The active neutron interrogation (ANI) method is now well-known and effective in quantifying low α-activity fissile masses (mainly 235U, 239Pu, 241Pu) with low densities, i.e. less than about 0.4, in radioactive waste drums of volumes up to 200 l. The PROMpt Epithermal and THErmal interrogation Experiment (PROMETHEE [F. Jallu, A. Mariani, C. Passard, A.-C. Raoux, H. Toubon, Alpha low level waste control: improvement of the PROMETHEE 6 assay system performances. Nucl. Technol. 153 (January) (2006); C. Passard, A. Mariani, F. Jallu, J. Romeyer-Dherber, H. Recroix, M. Rodriguez, J. Loridon, C. Denis, PROMETHEE: an alpha low level waste assay system using passive and active neutron measurement methods. Nucl. Technol. 140 (December) (2002) 303-314]) based on ANI has been under development since 1996 to reach the incinerating α low level waste (LLW) criterion of about 50 Bq[α] per gram of crude waste (≈50 μg Pu) in 118 l drums on the date the drums are conditioned. Difficulties arise when dealing with matrices containing neutron energy moderators such as H and neutron absorbents such as Cl. These components may have a great influence on the fissile mass deduced from the neutron signal measured by ANI. For example, the calibration coefficient measured in a 118 l drum containing a cellulose matrix (density d = 0.144 g cm -3) may be 50 times higher than that obtained in a poly-vinyl-chloride matrix ( d = 0.253 g cm -3). Without any information on the matrix, the fissile mass is often overestimated due to safety procedures and by considering the most disadvantageous calibration coefficient corresponding to the most absorbing and moderating calibration matrix. The work discussed in this paper was performed at the CEA Nuclear Measurement Laboratory in France. It concerns the development of a matrix effect correction method, which consists in identifying and quantifying

Improvement of non-destructive fissile mass assays in α low-level waste drums: A matrix correction method based on neutron capture gamma-rays and a neutron generator

International Nuclear Information System (INIS)

Jallu, F.; Loche, F.

2008-01-01

Within the framework of radioactive waste control, non-destructive assay (NDA) methods may be employed. The active neutron interrogation (ANI) method is now well-known and effective in quantifying low α-activity fissile masses (mainly 235 U, 239 Pu, 241 Pu) with low densities, i.e. less than about 0.4, in radioactive waste drums of volumes up to 200 l. The PROMpt Epithermal and THErmal interrogation Experiment (PROMETHEE [F. Jallu, A. Mariani, C. Passard, A.-C. Raoux, H. Toubon, Alpha low level waste control: improvement of the PROMETHEE 6 assay system performances. Nucl. Technol. 153 (January) (2006); C. Passard, A. Mariani, F. Jallu, J. Romeyer-Dherber, H. Recroix, M. Rodriguez, J. Loridon, C. Denis, PROMETHEE: an alpha low level waste assay system using passive and active neutron measurement methods. Nucl. Technol. 140 (December) (2002) 303-314]) based on ANI has been under development since 1996 to reach the incinerating α low level waste (LLW) criterion of about 50 Bq[α] per gram of crude waste (∼50 μg Pu) in 118 l drums on the date the drums are conditioned. Difficulties arise when dealing with matrices containing neutron energy moderators such as H and neutron absorbents such as Cl. These components may have a great influence on the fissile mass deduced from the neutron signal measured by ANI. For example, the calibration coefficient measured in a 118 l drum containing a cellulose matrix (density d = 0.144 g cm -3 ) may be 50 times higher than that obtained in a poly-vinyl-chloride matrix (d = 0.253 g cm -3 ). Without any information on the matrix, the fissile mass is often overestimated due to safety procedures and by considering the most disadvantageous calibration coefficient corresponding to the most absorbing and moderating calibration matrix. The work discussed in this paper was performed at the CEA Nuclear Measurement Laboratory in France. It concerns the development of a matrix effect correction method, which consists in identifying and

Improvement of non-destructive fissile mass assays in {alpha} low-level waste drums: A matrix correction method based on neutron capture gamma-rays and a neutron generator

Energy Technology Data Exchange (ETDEWEB)

Jallu, F. [Commissariat a l' Energie Atomique, CEA, DEN, Nuclear Measurement Laboratory, Bat. 224, 13108 Saint Paul lez Durance (France)], E-mail: fanny.jallu@cea.fr; Loche, F. [Commissariat a l' Energie Atomique, CEA, DEN, Nuclear Measurement Laboratory, Bat. 224, 13108 Saint Paul lez Durance (France)

2008-08-15

Within the framework of radioactive waste control, non-destructive assay (NDA) methods may be employed. The active neutron interrogation (ANI) method is now well-known and effective in quantifying low {alpha}-activity fissile masses (mainly {sup 235}U, {sup 239}Pu, {sup 241}Pu) with low densities, i.e. less than about 0.4, in radioactive waste drums of volumes up to 200 l. The PROMpt Epithermal and THErmal interrogation Experiment (PROMETHEE [F. Jallu, A. Mariani, C. Passard, A.-C. Raoux, H. Toubon, Alpha low level waste control: improvement of the PROMETHEE 6 assay system performances. Nucl. Technol. 153 (January) (2006); C. Passard, A. Mariani, F. Jallu, J. Romeyer-Dherber, H. Recroix, M. Rodriguez, J. Loridon, C. Denis, PROMETHEE: an alpha low level waste assay system using passive and active neutron measurement methods. Nucl. Technol. 140 (December) (2002) 303-314]) based on ANI has been under development since 1996 to reach the incinerating {alpha} low level waste (LLW) criterion of about 50 Bq[{alpha}] per gram of crude waste ({approx}50 {mu}g Pu) in 118 l drums on the date the drums are conditioned. Difficulties arise when dealing with matrices containing neutron energy moderators such as H and neutron absorbents such as Cl. These components may have a great influence on the fissile mass deduced from the neutron signal measured by ANI. For example, the calibration coefficient measured in a 118 l drum containing a cellulose matrix (density d = 0.144 g cm{sup -3}) may be 50 times higher than that obtained in a poly-vinyl-chloride matrix (d = 0.253 g cm{sup -3}). Without any information on the matrix, the fissile mass is often overestimated due to safety procedures and by considering the most disadvantageous calibration coefficient corresponding to the most absorbing and moderating calibration matrix. The work discussed in this paper was performed at the CEA Nuclear Measurement Laboratory in France. It concerns the development of a matrix effect correction

Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

TRINER, G.C.

1999-01-01

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

Multimodality characterization of nuclear waste drums using emerging techniques for nondestructive examination and assay

International Nuclear Information System (INIS)

Bernardi, R.T.

1993-01-01

We are developing an x-ray imaging system that incorporates several inspection technologies for complete, nondestructive evaluation of containers of nuclear waste. In Phase I and Phase II SBIR programs for the DOE, we proved the feasibility of using x-ray computed tomography (CT) and digital radiography (DR)-imaging techniques using x-rays transmitted through the object-for container inspection. Now, with further funding from DOE and working with scientists at Lawrence Livermore National Lab., we are designing a mobile inspection system that will use CT and DR as well as two x-ray emission imaging techniques-single photon emission computed tomography and nondestructive assay. This system will provide much more information about the contents of containers than currently used inspection methods, and will provide archiving of digital data. In this paper, we describe inspection system and present recent results from the CT and DR evaluations

Expected precision of neutron multiplicity measurements of waste drums

International Nuclear Information System (INIS)

Ensslin, N.; Krick, M.S.; Menlove, H.O.

1995-01-01

DOE facilities are beginning to apply passive neutron multiplicity counting techniques to the assay of plutonium scrap and residues. There is also considerable interest in applying this new measurement technique to 208-liter waste drums. The additional information available from multiplicity counting could flag the presence of shielding materials or improve assay accuracy by correcting for matrix effects such as (α,n) induced fission or detector efficiency variations. The potential for multiplicity analysis of waste drums, and the importance of better detector design, can be estimated by calculating the expected assay precision using a Figure of Merit code for assay variance. This paper reports results obtained as a function of waste drum content and detector characteristics. We find that multiplicity analysis of waste drums is feasible if a high-efficiency neutron counter is used. However, results are significantly poorer if the multiplicity analysis must be used to solve for detection efficiency

Amor celeste e amor terrestre: o encontro de Alcibíades e Sócrates em O banquete, de Platão

OpenAIRE

Gutman, Guilherme

2009-01-01

Neste texto realiza-se uma introdução à leitura de O banquete, de Platão, em especial de seu último trecho, ao qual corresponde o encontro de Alcibíades e Sócrates. Procurou-se ainda, indicar algumas discussões despertadas por esse diálogo platônico; principalmente aquelas que fazem referência às relações entre a filosofia, a literatura e a psicanálise. En este texto se realiza una introducción a la lectura de El Banquete, de Platón; especialmente del último trecho, que corresponde al encu...

Nondestructive assay measurements applied to reprocessing plants

International Nuclear Information System (INIS)

Ruhter, Wayne D.; Lee, R. Stephen; Ottmar, Herbert; Guardini, Sergio

1999-01-01

Nondestructive assay for reprocessing plants relies on passive gamma-ray spectrometry for plutonium isotopic and plutonium mass values of medium-to-low-density samples and holdup deposits; on active x-ray fluorescence and densitometry techniques for uranium and plutonium concentrations in solutions; on calorimetry for plutonium mass in product; and passive neutron techniques for plutonium mass in spent fuel, product, and waste. This paper will describe the radiation-based nondestructive assay techniques used to perform materials accounting measurements. The paper will also discuss nondestructive assay measurements used in inspections of reprocessing plants [ru

Composite waste analysis system

International Nuclear Information System (INIS)

Wachter, J.R.; Hagan, R.C.; Bonner, C.A.; Malcom, J.E.; Camp, K.L.

1993-01-01

Nondestructive analysis (NDA) of radioactive waste forms an integral component of nuclear materials accountability programs and waste characterization acceptance criterion. However, waste measurements are often complicated by unknown isotopic compositions and the potential for concealment of special nuclear materials in a manner that is transparent to gamma-ray measurement instruments. To overcome these complications, a new NDA measurement system has been developed to assay special nuclear material in both transuranic and low level waste from the same measurement platform. The system incorporates a NaI detector and customized commercial software routines to measure small quantities of radioactive material in low level waste. Transuranic waste analysis is performed with a coaxial HPGE detector and uses upgraded PC-based segmented gamma scanner software to assay containers up to 55 gal. in volume. Gamma-Ray isotopics analysis of both waste forms is also performed with this detector. Finally, a small neutron counter using specialized software is attached to the measurement platform to satisfy safeguards concerns related to nuclear materials that are not sensed by the gamma-ray instruments. This report describes important features and capabilities of the system and presents a series of test measurements that are to be performed to define system parameters

Design and operation of a passive neutron monitor for assaying the TRU content of solid wastes

International Nuclear Information System (INIS)

Brodzinski, R.L.; Brown, D.P.; Rieck, H.G. Jr.; Rogers, L.A.

1984-02-01

A passive neutron monitor has been designed and built for determining the residual transuranic (TRU) and plutonium content of chopped leached fuel hulls and other solid wastes from spent Fast Flux Test Facility (FFTF) fuel. The system was designed to measure as little as 8 g of plutonium or 88 mg of TRU in a waste package as large as a 208-l drum which could be emitting up to 220,000 R/hr of gamma radiation. For practical purposes, maximum assay times were chosen to be 10,000 sec. The monitor consists of 96 10 BF 3 neutron sensitive proportional counting tubes each 5.08 cm in diameter and 183 cm in active length. Tables of neutron emission rates from both spontaneous fission and (α,n) reactions on oxygen are given for all contributing isotopes expected to be present in spent FFTF fuel. Tables of neutron yeilds from isotopic compositions predicted for various exposures and cooling times are also given. Methods of data reduction and sources, magnitude, and control of errors are discussed. Backgrounds and efficiencies have been measured and are reported. A section describing step-by-step operational procedures is included. Guidelines and procedures for quality control and troubleshooting are also given. 13 references, 15 figures, 4 tables

An Electronic Model of the ATLAS Phase-1 Upgrade Hadronic Endcap Calorimeter Front End Crate Baseplane

CERN Document Server

Porter, Ryan

This thesis presents an electrical model of two pairs of interconnects of the ATLAS Phase-1 Upgrade Hadronic Endcap Front End Crate prototype baseplane. Stripline transmission lines of the baseplane are modeled using Keysight Technologies' Electromagnetic Professional's (EMPro) 3D electromagnetic simulation (Finite Element Method) and the connectors are modeled using built-in models in Keysight Technologies' Advanced Design System (ADS). The model is compared in both the time and frequency domain to measured Time Domain Reflectometer (TDR) traces and S-parameters. The S-parameters of the model are found to be within $5\\%$ of the measured S-parameters for transmission and reflection, and range from $25\\%$ below to $100\\%$ above for forward and backward crosstalk. To make comparisons with measurements, the cables used to connect the prototype HEC baseplane to the measurement system had to be included in the model. Plots of the S-parameters of a model without these cables are presented for one pair of interconne...

Identification of the fast and thermal neutron characteristics of transuranic waste drums

Energy Technology Data Exchange (ETDEWEB)

Storm, B.H. Jr.; Bramblett, R.L. [Lockheed Martin Specialty Components, Largo, FL (United States); Hensley, C. [Oak Ridge National Lab., TN (United States)

1997-11-01

Fissile and spontaneously fissioning material in transuranic waste drums can be most sensitively assayed using an active and passive neutron assay system such as the Active Passive Neutron Examination and Assay. Both the active and the passive assays are distorted by the presence of the waste matrix and containerization. For accurate assaying, this distortion must be characterized and accounted for. An External Matrix Probe technique has been developed that accomplishes this task. Correlations between in-drum neutron flux measurements and monitors in the Active Passive Neutron Examination and Assay chamber with various matrix materials provide a non-invasive means of predicting the thermal neutron flux in waste drums. Similarly, measures of the transmission of fast neutrons emitted from sources in the drum. Results obtained using the Lockheed Martin Specialty Components Active Passive Neutron Examination and Assay system are discussed. 12 figs., 1 tab.

Improving shuffler assay accuracy

International Nuclear Information System (INIS)

Rinard, P.M.

1995-01-01

Drums of uranium waste should be disposed of in an economical and environmentally sound manner. The most accurate possible assays of the uranium masses in the drums are required for proper disposal. The accuracies of assays from a shuffler are affected by the type of matrix material in the drums. Non-hydrogenous matrices have little effect on neutron transport and accuracies are very good. If self-shielding is known to be a minor problem, good accuracies are also obtained with hydrogenous matrices when a polyethylene sleeve is placed around the drums. But for those cases where self-shielding may be a problem, matrices are hydrogenous, and uranium distributions are non-uniform throughout the drums, the accuracies are degraded. They can be greatly improved by determining the distributions of the uranium and then applying correction factors based on the distributions. This paper describes a technique for determining uranium distributions by using the neutron count rates in detector banks around the waste drum and solving a set of overdetermined linear equations. Other approaches were studied to determine the distributions and are described briefly. Implementation of this correction is anticipated on an existing shuffler next year

Some target assay uncertainties for passive neutron coincidence counting

International Nuclear Information System (INIS)

Ensslin, N.; Langner, D.G.; Menlove, H.O.; Miller, M.C.; Russo, P.A.

1990-01-01

This paper provides some target assay uncertainties for passive neutron coincidence counting of plutonium metal, oxide, mixed oxide, and scrap and waste. The target values are based in part on past user experience and in part on the estimated results from new coincidence counting techniques that are under development. The paper summarizes assay error sources and the new coincidence techniques, and recommends the technique that is likely to yield the lowest assay uncertainty for a given material type. These target assay uncertainties are intended to be useful for NDA instrument selection and assay variance propagation studies for both new and existing facilities. 14 refs., 3 tabs

Field experience with a mobile tomographic nondestructive assay system

International Nuclear Information System (INIS)

Prettyman, T.H.; Betts, S.E.; Taggart, D.P.; Estep, R.J.; Nicholas, N.J.; Lucas, M.C.; Harlan, R.A.

1995-01-01

A mobile tomographic gamma-ray scanner (TGS) developed by Los Alamos National Laboratory was recently demonstrated at the Rocky Flats Environmental Technology Site and is currently in use at Los Alamos waste storage areas. The scanner was developed to assay radionuclides in low-level, transuranic, and mixed waste in containers ranging in size from 2 ft 3 boxes to 83-gallon overpacks. The tomographic imaging capability provides a complete correction for source distribution and matrix attenuation effects, enabling accurate assays of Pu-239 and other gamma-ray emitting isotopes. In addition, the system can reliably detect self-absorbing material such as plutonium metal shot, and can correct for bias caused by self-absorption. The system can be quickly configured to execute far-field scans, segmented gamma-ray scans, and a host of intermediate scanning protocols, enabling higher throughput (up to 20 drums per 8-hour shift). In this paper, we will report on the results of field trials of the mobile system at Rocky Flats and Los Alamos. Assay accuracy is confirmed for cases in which TGS assays can be compared with assays (e.g. with calorimetry) of individual packages within the drums. The mobile tomographic technology is expected to considerably reduce characterization costs at DOE production and environmental technology sites

Evaluation of the MADAM waste measurement system

Energy Technology Data Exchange (ETDEWEB)

Foster, L.A.; Wachter, J.R.; Hagan, R.C.

1995-03-01

The Multiple Assay Dual Analysis Measurement (MADAM) system is a combined low-level and transuranic waste assay system. The system integrates commercially available Segmented Gamma Scanner (SGS) capability with a multienergy x-ray and gamma-ray analysis to measure these two waste forms. In addition, the system incorporates a small neutron slab detector to satisfy safeguards concerns and the capability for automated high-resolution gamma-ray analysis for isotope identification. Since delivery of the system to this facility, an evaluation of the waste measurement characteristics of the system has been conducted. A set of specially constructed NIST-traceable standards was fabricated for calibration and evaluation of the low-level waste (LLW) measurement system. The measurement characteristics of the LLW assay system were determined during the evaluation, including detection limits for all isotopes of interest, matrix attenuation effects, and detector response as a function of source position. Based on these studies, several modifications to the existing analysis algorithms have been performed, new correction factors for matrix attenuation have been devised, and measurement error estimates have been calculated and incorporated into the software.

Evaluation of the MADAM waste measurement system

International Nuclear Information System (INIS)

Foster, L.A.; Wachter, J.R.; Hagan, R.C.

1995-01-01

The Multiple Assay Dual Analysis Measurement (MADAM) system is a combined low-level and transuranic waste assay system. The system integrates commercially available Segmented Gamma Scanner (SGS) capability with a multienergy x-ray and gamma-ray analysis to measure these two waste forms. In addition, the system incorporates a small neutron slab detector to satisfy safeguards concerns and the capability for automated high-resolution gamma-ray analysis for isotope identification. Since delivery of the system to this facility, an evaluation of the waste measurement characteristics of the system has been conducted. A set of specially constructed NIST-traceable standards was fabricated for calibration and evaluation of the low-level waste (LLW) measurement system. The measurement characteristics of the LLW assay system were determined during the evaluation, including detection limits for all isotopes of interest, matrix attenuation effects, and detector response as a function of source position. Based on these studies, several modifications to the existing analysis algorithms have been performed, new correction factors for matrix attenuation have been devised, and measurement error estimates have been calculated and incorporated into the software

Production and assay of cellulolytic enzyme activity of Enterobacter cloacae WPL 214 isolated from bovine rumen fluid waste of Surabaya abbatoir, Indonesia

Directory of Open Access Journals (Sweden)

W. P. Lokapirnasari

2015-03-01

Full Text Available Aim: This study aims to produce and assay cellulolytic enzyme activity (endo-(1,4-β-D-glucanase, exo-(1,4-β-Dglucanase, and β-glucosidase, at optimum temperature and optimum pH of Enterobacter cloacae WPL 214 isolated from bovine rumen fluid waste of Surabaya Abbatoir, Indonesia. Materials and Methods: To produce enzyme from a single colony of E. cloacae WPL 214, 98 × 1010 CFU/ml of isolates was put into 20 ml of liquid medium and incubated in a shaker incubator for 16 h at 35°C in accordance with growth time and optimum temperature of E. cloacae WPL 214. Further on, culture was centrifuged at 6000 rpm at 4°C for 15 min. Pellet was discarded while supernatant containing cellulose enzyme activity was withdrawn to assay endo-(1,4-β-D-glucanase, exo-(1,4-β-D-glucanase, and β-glucosidase. Results: Cellulase enzyme of E. cloacae WPL 214 isolates had endoglucanase activity of 0.09 U/ml, exoglucanase of 0.13 U/ml, and cellobiase of 0.10 U/ml at optimum temperature 35°C and optimum pH 5. Conclusion: E. cloacae WPL 214 isolated from bovine rumen fluid waste produced cellulose enzyme with activity as cellulolytic enzyme of endo-(1,4-β-D-glucanase, exo-(1,4-β-D-glucanase and β-glucosidase.

Verification of Representative Sampling in RI waste

International Nuclear Information System (INIS)

Ahn, Hong Joo; Song, Byung Cheul; Sohn, Se Cheul; Song, Kyu Seok; Jee, Kwang Yong; Choi, Kwang Seop

2009-01-01

For evaluating the radionuclide inventories for RI wastes, representative sampling is one of the most important parts in the process of radiochemical assay. Sampling to characterized RI waste conditions typically has been based on judgment or convenience sampling of individual or groups. However, it is difficult to get a sample representatively among the numerous drums. In addition, RI waste drums might be classified into heterogeneous wastes because they have a content of cotton, glass, vinyl, gloves, etc. In order to get the representative samples, the sample to be analyzed must be collected from selected every drum. Considering the expense and time of analysis, however, the number of sample has to be minimized. In this study, RI waste drums were classified by the various conditions of the half-life, surface dose, acceptance date, waste form, generator, etc. A sample for radiochemical assay was obtained through mixing samples of each drum. The sample has to be prepared for radiochemical assay and although the sample should be reasonably uniform, it is rare that a completely homogeneous material is received. Every sample is shredded by a 1 ∼ 2 cm 2 diameter and a representative aliquot taken for the required analysis. For verification of representative sampling, classified every group is tested for evaluation of 'selection of representative drum in a group' and 'representative sampling in a drum'

Survey of DOE NDA practices for CH-Tru waste certification--illustrated with a greater than 10,000 drum NDA data base

International Nuclear Information System (INIS)

Schultz, F.J.; Caldwell, J.T.; Smith, J.R.

1988-01-01

We have compiled a greater than 10,000 CH-TRU waste drum data base from seven DOE sites which have utilized such multiple NDA measurements within the past few years. Most of these nondestructive assay (NDA) technique assay result comparisons have been performed on well-characterized, segregated waste categories such as cemented sludges, combustibles, metals, graphite residues, glasses, etc., with well-known plutonium isotopic compositions. Waste segregation and categorization practices vary from one DOE site to another. Perhaps the most systematic approach has been in use for several years at the Rocky Flats Plant (RFP), operated by Rockwell International, and located near Golden, Colorado. Most of the drum assays in our data base result from assays of RFP wastes, with comparisons available between the original RFP assays and PAN assays performed independently at the Idaho National Engineering Laboratory (INEL) Solid Waste Examination Pilot Plant (SWEPP) facility. Most of the RFP assays were performed with hyperpure germanium (HPGe)-based SGS assay units. However, at least one very important waste category, processed first-stage sludges, is assayed at RFP using a sludge batch-sampling procedure, prior to filling of the waste drums. 5 refs., 5 figs

Transuranic waste examination quality assurance at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Bower, J.M.

1987-01-01

Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). A major objective of the Department of Energy (DOE) Nuclear Waste Management Programs is the proper management of the defense-generated TRU waste. The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored contact handled TRU waste in order to certify it to the Waste Isolation Pilot Plant Waste Acceptance Crtieria (WIPP-WAC). SWEPP's capabilities for certifying contact handled waste containers include weighing, real-time radiographic examination, fissile material assay examination, container integrity examination, radiological surveys and labeling of waste containers. These processes involve not only instrument accuracy but also a wide range of technician interpretation from moderate on the assay to 100% on the radiograph. This, therefore, requires a variety of quality assurance techniques to ensure that the examinations and certifications are being performed correctly. The purpose of this paper is to discuss the methods utilized by SWEPP for checking on the examination process and to ensure that waste certifications are being properly performed. Included is the application of the quality assurance techniques to each examination system, the management of the data generated by the examination, and the verifications to ensure accurate certification. 1 ref

Modified impedance control for robotic saw cutting: Simulation and implementation in three degrees of freedom

International Nuclear Information System (INIS)

Kriikku, E.M.; Reynolds, D.L.; Carroll, J.J.; Dawson, D.M.

1993-01-01

The Savannah River Site (SRS) production and decommissioning operations produce solid radioactive transuranic (TRU) waste. This waste must be repackaged and sent to the Waste Isolation Pilot Plant (WIPP) for permanent disposal. The Savannah River Technology Center (SRTC) built a test facility to demonstrate simulated waste processing. The test facility use's a CIMCORP multi-axis robot system, a CIMROC trademark II robot controller, and an electric circular saw to remotely open and size reduce plywood crates. The robot can either be teleoperated using joysticks or autonomously controlled via the, CIMROC trademark II. Both methods are inadequate for circular saw cutting of plywood crates due to frequent saw blade binding. Blade binding results from the current commercial robot controller limitations. The limitations are overcome by incorporating additional sensor information into the existing controller structure. In this paper we utilize a force sensor and a frequency counter to implement a modified impedance controller which prevents saw blade binding

Preparations for Retrieval of Buried Waste at Material Disposal Area B

International Nuclear Information System (INIS)

Chaloupka, A.B.; Criswell, C.W.; Goldberg, M.S.; Gregory, D.R.; Worth, E.P.

2009-01-01

Material Disposal Area B, a hazard category 3 nuclear facility, is scheduled for excavation and the removal of its contents. Wastes and excavated soils will be characterized for disposal at approved off-site waste disposal facilities. Since there were no waste disposal records, understanding the context of the historic operations at MDA B was essential to understanding what wastes were disposed of and what hazards these would pose during retrieval. The operational history of MDA B is tied to the earliest history of the Laboratory, the scope and urgency of World War II, the transition to the Atomic Energy Commission in January 1947, and the start of the cold war. A report was compiled that summarized the development of the process chemistry, metallurgy, and other research and production activities at the Laboratory during the 1944 to 1948 time frame that provided a perspective of the work conducted; the scale of those processes; and the handling of spent chemicals and contaminated items in lieu of waste disposal records. By 1947, all laboratories had established waste disposal procedures that required laboratory and salvage wastes to be boxed and sealed. Large items or equipment were to be wrapped with paper or placed in wooden crates. Most wastes were placed in cardboard boxes and were simply piled into the active trench. Bulldozers were used to cover the material with fill dirt on a weekly basis. No effort was made to separate waste types or loads, or to compact the wastes under the soil cover. Using the historical information and a statistical analysis of the plutonium inventory, LANL prepared a documented safety analysis for the waste retrieval activities at MDA B, in accordance with DOE Standard 1120-2005, Integration of Environment, Safety, and Health into Facility Disposition Activities, and the provisions of 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response. The selected hazard controls for the MDA B project consist of passive design

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

Effect of variability in lighting and temperature environments for mature gilts housed in gestation crates on measures of reproduction and animal well-being.

Science.gov (United States)

Canaday, D C; Salak-Johnson, J L; Visconti, A M; Wang, X; Bhalerao, K; Knox, R V

2013-03-01

The effects of room temperature and light intensity before breeding and into early gestation were evaluated on the reproductive performance and well-being of gilts housed individually in crates. In eight replicates, estrus was synchronized in mature gilts (n = 198) and after last feeding of Matrix were randomly assigned to a room temperature of 15°C (COLD), 21°C (NEUTRAL), or 30°C (HOT) and a light intensity of 11 (DIM) or 433 (BRIGHT) lx. Estrous detection was performed daily and gilts inseminated twice. Blood samples were collected before and after breeding for determination of immune measures and cortisol concentrations. Gilt ADFI, BW, and body temperature were measured. On d 30 postbreeding, gilts were slaughtered to recover reproductive tracts to evaluate pregnancy and litter characteristics. There were no temperature × light intensity interactions for any response variable. Reproductive measures of follicle development, expression of estrus, ovulation rate, pregnancy rate (83.2%), litter size (14.3 ± 0.5), and fetal measures were not affected by temperature or lighting (P > 0.10). Gilts in COLD (37.6°C) had a lower (P postural changes (P 0.10) of light or interaction with temperature on other immune cells or measures. These results indicate that temperatures in the range of 15 to 30°C or light intensity at 11 to 433 lx do not impact reproduction during the follicular phase and into early gestation for mature gilts housed in gestation crates. However, room temperature does impact physiological, behavioral, and immune responses of mature gilts and should be considered as a potential factor that may influence gilt well-being during the first 30 d postbreeding.

Waste inspection tomography (WIT)

Energy Technology Data Exchange (ETDEWEB)

Bernardi, R.T. [Bio-Imaging Research, Inc., Lincolnshire, IL (United States)

1995-10-01

Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting, isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU.

Waste inspection tomography (WIT)

International Nuclear Information System (INIS)

Bernardi, R.T.

1995-01-01

Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting, isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU

Radioactive waste reality as revealed by neutron measurements

International Nuclear Information System (INIS)

Schultz, F.J.

1995-01-01

To comprehend certain aspects of the contents of a radioactive waste container is not a trivial matter, especially if one is not allowed to open the container and peer inside. One of the suite of tools available to a practioner in the art of nondestructive assay is based upon neutron measurements. Neutrons, both naturally occuring and induced, are penertrating radiations that can be detected external to the waste container. The practioner should be skilled in applying the proper technique(s) to selected waste types. Available techniques include active and passive neutron measurements, each with their own strengths and weaknesses. The waste material itself can compromise the assay results by occluding a portion of the mass of fissile material present, or by multiplying the number of neutrons produced by a spontaneously fissioning mass. This paper will discuss the difficult, but albeit necessary marriage, between radiioactive waste types and alternative neutron measurement techniques

A waste characterization monitor for low-level radioactive waste management

International Nuclear Information System (INIS)

Davey, E.C.; Csullog, G.W.; Kupca, S.; Hippola, K.B.

1985-06-01

The exploitation of nuclear processes and technology for the benefit of Canadians results in the routine generation of approximately 12 000 m 3 of solid low-level radioactive waste annually. To protect the public and the environment, this waste must be isolated for the duration of its potential hazard. In Canada, current planning foresees the development and use of a range of storage and disposal facilities exhibiting differing containment capabilities. To demonstrate adequate isolation safety and to minimize overall costs, the radionuclide content of waste items must be quantified so that the radiological hazards of each waste item can be matched to the isolation capabilities of specific containment facilities. This paper describes a non-invasive, waste characterization monitor that is capable of quantifying the radionuclide content of low-level waste packages to the 9 Bq/g (250 pCi/g) level. The assay technique is based on passive gamma-ray spectroscopy where the concentration of gamma-ray emitting radionuclides in a waste item can be estimated from the analysis of the gamma-ray spectra of the item and calibrated standards

Total Measurement Uncertainty for the Plutonium Finishing Plant (PFP) Segmented Gamma Scan Assay System

CERN Document Server

Fazzari, D M

2001-01-01

This report presents the results of an evaluation of the Total Measurement Uncertainty (TMU) for the Canberra manufactured Segmented Gamma Scanner Assay System (SGSAS) as employed at the Hanford Plutonium Finishing Plant (PFP). In this document, TMU embodies the combined uncertainties due to all of the individual random and systematic sources of measurement uncertainty. It includes uncertainties arising from corrections and factors applied to the analysis of transuranic waste to compensate for inhomogeneities and interferences from the waste matrix and radioactive components. These include uncertainty components for any assumptions contained in the calibration of the system or computation of the data. Uncertainties are propagated at 1 sigma. The final total measurement uncertainty value is reported at the 95% confidence level. The SGSAS is a gamma assay system that is used to assay plutonium and uranium waste. The SGSAS system can be used in a stand-alone mode to perform the NDA characterization of a containe...

Micronucleus Assay and Heavy Metals Characterization of E-waste ...

African Journals Online (AJOL)

ADOWIE PERE

2018-03-28

Mar 28, 2018 ... Ba) in the sediments, water, leachate and aquatic fauna (Tilapia guineensis, Callinectes amnicola and Cardiosoma ..... (2003) limit standard (0.01mg/L) for treated waste water .... the erythrocyte of grey mullet (Mugil cephalus).

Active and passive computed tomography mixed waste focus area final report

International Nuclear Information System (INIS)

Becker, G K; Camp, D C; Decman, D J; Jackson, J A; Martz, H E; Roberson, G P.

1998-01-01

The Mixed Waste Focus Area (MWFA) Characterization Development Strategy delineates an approach to resolve technology deficiencies associated with the characterization of mixed wastes. The intent of this strategy is to ensure the availability of technologies to support the Department of Energy s (DOE) mixed-waste, low-level or transuranic (TRU) contaminated waste characterization management needs. To this end the MWFA has defined and coordinated characterization development programs to ensure that data and test results necessary to evaluate the utility of non-destructive assay technologies are available to meet site contact handled waste management schedules. Requirements used as technology development project benchmarks are based in the National TRU Program Quality Assurance Program Plan. These requirements include the ability to determine total bias and total measurement uncertainty. These parameters must be completely evaluated for waste types to be processed through a given nondestructive waste assay system constituting the foundation of activities undertaken in technology development projects. Once development and testing activities have been completed, Innovative Technology Summary Reports are generated to provide results and conclusions to support EM-30, -40, or -60 end user or customer technology selection. The active and passive computed tomography non-destructive assay system is one of the technologies selected for development by the MWFA. Lawrence Livermore National Laboratory (LLNL) has developed the active and passive computed tomography (A ampersand XT) nondestructive assay (NDA) technology to identify and accurately quantify all detectable radioisotopes in closed containers of waste. This technology will be applicable to all types of waste regardless of their classification-low level, transuranic or mixed. Mixed waste contains radioactivity and hazardous organic species. The scope of our technology is to develop a non-invasive waste-drum scanner that

Reuse of waste of glass wool in the production of mortar

International Nuclear Information System (INIS)

Vieira, P.L.C.; Santos, N.A.; Louzada, D.M.; Araujo, G.S.; Della, V.P.

2014-01-01

In recent years, the incorporation of alternative materials, especially waste, in mortars and concretes has become a common practice in the building industry. Against this background, this paper seeks to examine the possibility of using waste glass wool resulting from the steel industry in mortars in partial replacement the thin fraction of sand. To the knowledge of their chemical and mineralogical composition, the waste was subjected to x-ray fluorescence and diffraction assays. Mortars with different percentages of incorporation of waste were produced and performed flow test assays, Water Absorption by capillarity, compressive strength and compressive flexural strength. The results were compared with a reference mortar without residue. (author)

Neutronic measurements of radioactive waste; Les mesures neutroniques des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

Perot, B

1997-12-31

This document presents the general matters involved in the radioactive waste management and the different non destructive assays of radioactivity. The neutronic measurements used in the characterization of waste drums containing emitters are described with more details, especially the active neutronic interrogation assays with prompt or delayed neutron detection: physical principle, signal processing and evaluation of the detection limit. (author).

Bioremediation of cooking oil waste using lipases from wastes.

Directory of Open Access Journals (Sweden)

Clarissa Hamaio Okino-Delgado

Full Text Available Cooking oil waste leads to well-known environmental impacts and its bioremediation by lipase-based enzymatic activity can minimize the high cytotoxic potential. In addition, they are among the biocatalysts most commercialized worldwide due to the versatility of reactions and substrates. However, although lipases are able to process cooking oil wastes, the products generated from this process do not necessarily become less toxic. Thus, the aim of the current study is to analyze the bioremediation of lipase-catalyzed cooking oil wastes, as well as their effect on the cytotoxicity of both the oil and its waste before and after enzymatic treatment. Thus, assessed the post-frying modification in soybean oil and in its waste, which was caused by hydrolysis reaction catalyzed by commercial and home-made lipases. The presence of lipases in the extracts obtained from orange wastes was identified by zymography. The profile of the fatty acid esters formed after these reactions was detected and quantified through gas chromatography and fatty acids profile compared through multivariate statistical analyses. Finally, the soybean oil and its waste, with and without enzymatic treatment, were assessed for toxicity in cytotoxicity assays conducted in vitro using fibroblast cell culture. The soybean oil wastes treated with core and frit lipases through transesterification reaction were less toxic than the untreated oils, thus confirming that cooking oil wastes can be bioremediated using orange lipases.

Polyhydroxybutyrate (PHB) Synthesis by Spirulina sp. LEB 18 Using Biopolymer Extraction Waste.

Science.gov (United States)

da Silva, Cleber Klasener; Costa, Jorge Alberto Vieira; de Morais, Michele Greque

2018-01-20

The reuse of waste as well as the production of biodegradable compounds has for years been the object of studies and of global interest as a way to reduce the environmental impact generated by unsustainable exploratory processes. The conversion of linear processes into cyclical processes has environmental and economic advantages, reducing waste deposition and reducing costs. The objective of this work was to use biopolymer extraction waste in the cultivation of Spirulina sp. LEB 18, for the cyclic process of polyhydroxybutyrate (PHB) synthesis. Concentrations of 10, 15, 20, 25, and 30% (v/v) of biopolymer extraction waste were tested. For comparison, two assays were used without addition of waste, Zarrouk (SZ) and modified Zarrouk (ZM), with reduction of nitrogen. The assays were carried out in triplicate and evaluated for the production of microalgal biomass and PHB. The tests with addition of waste presented a biomass production statistically equal to ZM (0.79 g L -1 ) (p PHB in the assay containing 25% of waste was higher when compared to the other cultivations, obtaining 10.6% (w/w) of biopolymer. From the results obtained, it is affirmed that the use of PHB extraction waste in the microalgal cultivation, aiming at the synthesis of biopolymers, can occur in a cyclic process, reducing process costs and the deposition of waste, thus favoring the preservation of the environment.

TRU-ART: A cost-effective prototypical neutron imaging technique for transuranic waste certification systems

International Nuclear Information System (INIS)

Horton, W.S.

1989-01-01

The certification of defense radioactive waste as either transuranic or low-level waste requires very sensitive and accurate assay instrumentation to determine the specific radioactivity within an individual waste package. An assay instrument that employs a new technique (TRU-ART), which can identify the location of the radioactive material within a waste package, was designed, fabricated, and tested to potentially enhance the certification of problem defense waste drums. In addition, the assay instrumentation has potential application in radioactive waste reprocessing and neutron tomography. The assay instrumentation uses optimized electronic signal responses from an array of boral- and cadmium-shielded polyethylene-moderated 3 H detector packages. Normally, thermal neutrons that are detected by 3 H detectors have very poor spatial dependency that may be used to determine the location of the radioactive material. However, these shielded-detector packages of the TRU-ART system maintain the spatial dependency of the radioactive material in that the point of fast neutron thermalization is immediately adjacent to the 3 H detector. The TRU-ART was used to determine the location of radioactive material within three mock-up drums (empty, peat moss, and concrete) and four actual waste drums. The TRU-ART technique is very analogous to emission tomography. The mock-up drum and actual waste drum data, which were collected by the TRU-ART, were directly input into a algebraic reconstruction code to produce three-dimensional isoplots. Finally, a comprehensive fabrication cost estimate of the fielded drum assay system and the TRU-ART system was determined, and, subsequently, these estimates were used in a cost-benefit analysis to compare the economic advantage of the respective systems

A passive gamma scanner for estimation of plutonium in fabrication waste

International Nuclear Information System (INIS)

Venkatesan, P.P.; Burte, P.P.; Manohar, S.B.; Satya Prakash; Ramaniah, M.V.

1978-01-01

The solid plutonium wastes arising from plutonium handling laboratories and fuel fabrication facilities by their very nature (heterogeneous) are not amenable to proper sampling and hence to the standard techniques of estimation. For the proper accounting of nuclear materials a non-destructive method of waste assay is essential. A passive gamma-ray scanner developed in the Radiochemistry Division is described in the present report. The scanner detects the 384 KeV gamma complex of plutonium in a (3'' x 3'') NaI(Tl) detector. The rotation-collimation technique is used to achieve the flat response with respect to the plutonium distribution inside the waste can. The sensitivity of the scanner is 200 mg of Pu per can at 2 sigma level and 20% accuracy for a total scan time of 2000 sec. The assay results of typical waste cans and comparison of a few of these with chemical assay results are presented. This non-destructive method is fast, simple and has satisfactory accuracy. (author)

Measurement of radionuclides in waste packages

Science.gov (United States)

Brodzinski, R.L.; Perkins, R.W.; Rieck, H.G.; Wogman, N.A.

1984-09-12

A method is described for non-destructively assaying the radionuclide content of solid waste in a sealed container by analysis of the waste's gamma-ray spectrum and neutron emissions. Some radionuclides are measured by characteristic photopeaks in the gamma-ray spectrum; transuranic nuclides are measured by neutron emission rate; other radionuclides are measured by correlation with those already measured.

Inactive trials of transport systems

International Nuclear Information System (INIS)

Haberlin, M.M.; Hardy, A.R.

1985-06-01

The design and manufacture of a mock-up of a crate handling and size reduction (CHSR) facility, an experimental programme on the evaluation of a commercial air-transporter, and the selection, manufacture and commissioning trials of an integrated conveyor system for transporting crated waste into and within the mock-up facility, are considered. The mock-up facility was used for the test programme on the air-transporter and conveyor system. The air-transporter was considered suitable for transporting waste on the metal floor in the main dismantling area of the CHSR facility because it can tolerate asymmetric loading, the exhaust air flow liberated from the air-pads is low and it has excellent manoeuvrability. Commissioning trials were carried out on a commercial conveyor system consisting of unpowered rollers in the reception area, a powered slatted conveyor in the air-lock and an unpowered roller table placed on the air-transporter in the working area. It was demonstrated that a large asymmetrically loaded wooden crate can be transported into and within the facility by this method. Further design and experimental work necessary before the system can be used for remote operation is discussed. (author)

Conceptual design of the special nuclear material nondestructive assay and accountability system for the HTGR fuel refabrication pilot plant

International Nuclear Information System (INIS)

Jenkins, J.D.; McNeany, S.R.; Rushton, J.E.

1975-07-01

The conceptual design of the fissile material assay and accountability system for the HTGR refabrication pilot plant has been established. The primary feature affecting the design is the high, time varying, gamma activity of the process material due to the unavoidable presence of uranium-232. This imposes stringent requirements for remote operation and remote maintainability of system components. At the same time, the remote operation lends itself to implementation of an automated data collection and processing system for real-time accountability. The high time-varying gamma activity of the material also precludes application of a number of techniques presently employed for light-water reactor fuel assay. The techniques selected for application in the refabrication facility are (1) active thermal neutron interrogation with fast-fission or delayed-neutron counting for fuel-rod and small-sample assay, (2) calorimetry for high-level waste assay, and (3) passive gamma scanning for low-level waste assay, and rapid on-line relative rod-loading measurements. The principal nondestructive assay subsystems are identified as (1) on-line devices for 100 percent product fuel rod assay and quality control, (2) a multipurpose device in the sample inspection laboratory for small- sample assay and secondary standards calibration, and (3) equipment for assay of high- and low-uranium content scrap and waste materials. A data processing system, which coordinates data from these subsystems with information from other process control sensors, is included to provide real-time material balance information. (U.S.)

Status of operation of radionuclides assay system in Korean nuclear power plant

International Nuclear Information System (INIS)

Hwang, K.H.; Lee, K.J.; Jeong, C.W.; Ahn, S.M.

2003-01-01

In Korea, 17 nuclear power plants composed of 13 pressurized water reactors and 4 CANDU reactors are currently in operation. The cumulative amounts of low and intermediate level radioactive waste in nuclear power plant reached 58,718 drums (unit: 200 liter) in 2001. Efforts to construct LILW disposal facility are continued and its first operation is planned in the year 2008. Its first stage capacity is assumed to be 100,000 drums and total capacity will reach to 800,000 drums. Radwaste disposal site selection is an urgent national project at present time. Regulations and guidelines require detailed information about the radioactive waste package and its contents prior to the transport to the disposal sites. The Enforcement Decree of the Korean Atomic Energy Act (articles 234-17) requires the Minister of Science and Technology (MOST) of Korea to establish regulation for the waste acceptance (MOST notice. 1196-10). It requires detailed information about the radioactive waste package and its contents such as activity of radionuclides, total activities, types and characteristics of waste. For the measurement of the concentrations and activities of radionuclides in radwaste drum, a radionuclides assay system is installed at Korean nuclear power plant (KORI site) in 1996. The waste drum can be measured in the vertical direction with eight vertical segments while in the radial direction also with eight segments. Using this measurement method, homogeneous and non-homogeneous waste drum can be measured. Scaling factor methods have been played a dominant role in the determination of the radionuclides concentration in this system. For corrosion product, generic scaling factors were used due to the similarity and better-characterized properties of Korean analyzed data as compared with the worldwide data base of PWR industry. For fission product and TRU nuclides, it is not easy to determine the generic scaling factors. Thus simple model reflecting the operation history of power

An investigation of the neutron die-away time in passive neutron waste assay systems

International Nuclear Information System (INIS)

Baeten, P.; Bruggeman, M.; Carchon, R.

1997-02-01

Neutron coincidence counting applied to the assay of Pu-bearing waste is commonly based on the assumption that the time intervals between detected fission neutrons are distributed according to a mono-exponential function, often called Rossi-alpha distribution. The time constant of this characteristic exponential function is generally referred to as the die-away time of the detector assembly. In fact, the distribution of time intervals is derived from the more fundamental arrival time distribution, which is also assumed to obey a mono-exponential law. In view of the design studies for a neutron counter, the validity of this basic assumption was investigated. Different parameters such as neutron moderation and absorption in the sample and the presence of cadmium-lining were investigated by means of Monte Carlo simulations using the NCNP-code. The simulation results lead to the conclusion that the description of the arrival time function with a mono-exponential function with a sample-independent die-away time is only a first approximations. The mono-exponential decay is perturbed by a second time component related to the detection of neutrons already thermalized in the sample. This thermal component cannot be described by a mono-exponential function, but has a characteristic shape with a fast build-up reaching a maximum followed by a slow decay as a function of the arrival time. The relative contribution of this component strongly depends on the absorption and moderation of the sample matrix. This component cannot be described by a simple analytical expression involving sample related parameters. Hence, no direct useful information can be withdrawn from the arrival time probability function to characterize the waste matrix. The thermal component can be strongly suppressed by the use of cadmium-lining in front of the detector blocks simplifying the mathematical description of the arrival time probability function. Indications of the bias introduced by an inaccurate

SCO shipments from Rocky Flats - Experience and current practice [Surface Contaminated Object

International Nuclear Information System (INIS)

Bracken, Gary; Morris, Robert L.

2001-01-01

Decommissioning activities at Rocky Flats Environmental Technology Site (RFETS) are expected to generate approximately 251,000 cubic meters of low-level radioactive waste. Almost half of this will be characterized and shipped as the Department of Transportation ''Surface Contaminated Object'' (SCO) shipping class. In the 2 years since an SCO characterization method was implemented, almost 11,000 of the 18,000 cubic meters of low-level waste were SCO. RFETS experience to-date using an SCO waste characterization method has shown significant time and cost savings, reduced errors, and enhanced employee safety. SCO waste is characterized prior to packaging, near the point of generation, by any of the site's 300 Radiological Control Technicians using inexpensive radiological control survey instruments. This reduces on-site waste container moves and eliminates radiometric analysis at centrally located drum or crate counters. Containers too large for crate counters can also be characterized. Current instrumentation is not adequate to take full advantage of the SCO regulations. Future improvements in the SCO characterization and shipping process are focused on use of larger and/or reusable containers, extended-range instruments, and additional statistical methods, so that the full extent of the SCO regulations can be used

Toxicological evaluation of complex industrial wastes: Implications for exposure assessment

Energy Technology Data Exchange (ETDEWEB)

DeMarini, D.M.; Gallagher, J.E.; Houk, V.S.; Simmons, J.E.

1989-01-01

A variety of short-term bioassays to construct a battery of tests that could be used for assessing the biological effects of potentially hazardous complex industrial wastes were evaluated. Ten samples were studied for hepatotoxicity: These samples and an additional five were studied for mutagenicity. Although the data are limited to these samples, the results suggest that the Salmonella assay (either TA98 or TA100) or a prophage-induction assay (both in the presence of S9) in combination with determination of relative liver weight and levels of a set of serum enzymes in rats would provide a battery of tests suitable to characterize complex industrial wastes for mutagenic and hepatotoxic potential. The biological activities exhibited by the wastes were not readily predicted by the chemical profiles of the wastes, emphasizing the importance of characterizing potentially hazardous complex industrial wastes by both chemical and biological means.

MS transport assays for γ-aminobutyric acid transporters--an efficient alternative for radiometric assays.

Science.gov (United States)

Schmitt, Sebastian; Höfner, Georg; Wanner, Klaus T

2014-08-05

Transport assays for neurotransmitters based on radiolabeled substrates are widely spread and often indispensable in basic research and the drug development process, although the use of radioisotopes is inherently coupled to issues concerning radioactive waste and safety precautions. To overcome these disadvantages, we developed mass spectrometry (MS)-based transport assays for γ-aminobutyric acid (GABA), which is the major inhibitory neurotransmitter in the central nervous system (CNS). These "MS Transport Assays" provide all capabilities of [(3)H]GABA transport assays and therefore represent the first substitute for the latter. The performance of our approach is demonstrated for GAT1, the most important GABA transporter (GAT) subtype. As GABA is endogenously present in COS-7 cells employed as hGAT1 expression system, ((2)H6)GABA was used as a substrate to differentiate transported from endogenous GABA. To record transported ((2)H6)GABA, a highly sensitive, short, robust, and reliable HILIC-ESI-MS/MS quantification method using ((2)H2)GABA as an internal standard was developed and validated according to the Center for Drug Evaluation and Research (CDER) guidelines. Based on this LC-MS quantification, a setup to characterize hGAT1 mediated ((2)H6)GABA transport in a 96-well format was established, that enables automated processing and avoids any sample preparation. The K(m) value for ((2)H6)GABA determined for hGAT1 is in excellent agreement with results obtained from [(3)H]GABA uptake assays. In addition, the established assay format enables efficient determination of the inhibitory potency of GAT1 inhibitors, is capable of identifying those inhibitors transported as substrates, and furthermore allows characterization of efflux. The approach described here combines the strengths of LC-MS/MS with the high efficiency of transport assays based on radiolabeled substrates and is applicable to all GABA transporter subtypes.

Kalman filter analysis of delayed neutron nondestructive assay measurements

International Nuclear Information System (INIS)

Aumeier, S. E.

1998-01-01

The ability to nondestructively determine the presence and quantity of fissile and fertile nuclei in various matrices is important in several nuclear applications including international and domestics safeguards, radioactive waste characterization and nuclear facility operations. Material irradiation followed by delayed neutron counting is a well known and useful nondestructive assay technique used to determine the fissile-effective content of assay samples. Previous studies have demonstrated the feasibility of using Kalman filters to unfold individual isotopic contributions to delayed neutron measurements resulting from the assay of mixes of uranium and plutonium isotopes. However, the studies in question used simulated measurement data and idealized parameters. We present the results of the Kalman filter analysis of several measurements of U/Pu mixes taken using Argonne National Laboratory's delayed neutron nondestructive assay device. The results demonstrate the use of Kalman filters as a signal processing tool to determine the fissile and fertile isotopic content of an assay sample from the aggregate delayed neutron response following neutron irradiation

Toxicity assessment of carbon black waste: A by-product from oil refineries

Energy Technology Data Exchange (ETDEWEB)

Zhen, Xu; Ng, Wei Cheng [NUS Environmental Research Institute, National University of Singapore, 1 Create Way, Create Tower #15-02, 138602 (Singapore); Fendy; Tong, Yen Wah [Department of Chemical and Biomolecular Engineering, National University of Singapore, 4 Engineering Drive 4, 117585 (Singapore); Dai, Yanjun [School of Mechanical Engineering, Shanghai Jiaotong University, Shanghai, 200240 (China); Neoh, Koon Gee, E-mail: chenkg@nus.edu.sg [Department of Chemical and Biomolecular Engineering, National University of Singapore, 4 Engineering Drive 4, 117585 (Singapore); Wang, Chi-Hwa, E-mail: chewch@nus.edu.sg [Department of Chemical and Biomolecular Engineering, National University of Singapore, 4 Engineering Drive 4, 117585 (Singapore)

2017-01-05

Highlights: • Carbon black waste extract decreased cell viability in a dose and time-dependent manner. • Apoptosis of human cell lines was induced by carbon black waste extract. • Carbon black waste extract elicited oxidative stress by increasing intracellular ROS generation. • Carbon black waste extract impaired antioxidant enzymatic activities of human cell lines. • The high toxicity of carbon black waste extract could be attributed mainly to the effect of vanadium. - Abstract: In Singapore, approximately 30 t/day of carbon-based solid waste are produced from petrochemical processes. This carbon black waste has been shown to possess physical properties that are characteristic of a good adsorbent such as high external surface area. Therefore, there is a growing interest to reutilize and process this carbon black waste into secondary materials such as adsorbents. However, the carbon black waste obtained from petrochemical industries may contain heavy metals that are hazardous to human health and the environment, hence restricting its full potential for re-utilization. Therefore, it is important to examine the possible toxicity effects and toxicity mechanism of carbon black waste on human health. In this study, inductively coupled plasma optical emission spectroscopy (ICP-OES) analysis showed that the heavy metals, vanadium (V), molybdenum (Mo) and nickel (Ni), were present in the carbon black waste in high concentrations. Three human cell lines (HepG2 cells, MRC-5 cells and MDA-MB-231 cells) were used to investigate the toxicity of carbon black waste extract in a variety of in vitro assays. Results from MTS assays indicated that carbon black waste extract decreased the viability of all three cell lines in a dose and time-dependent manner. Observations from confocal microscopy further confirmed this phenomenon. Flow cytometry assay also showed that carbon black waste extract induced apoptosis of human cell lines, and the level of apoptosis increased with

Toxicity assessment of carbon black waste: A by-product from oil refineries

International Nuclear Information System (INIS)

Zhen, Xu; Ng, Wei Cheng; Fendy; Tong, Yen Wah; Dai, Yanjun; Neoh, Koon Gee; Wang, Chi-Hwa

2017-01-01

Highlights: • Carbon black waste extract decreased cell viability in a dose and time-dependent manner. • Apoptosis of human cell lines was induced by carbon black waste extract. • Carbon black waste extract elicited oxidative stress by increasing intracellular ROS generation. • Carbon black waste extract impaired antioxidant enzymatic activities of human cell lines. • The high toxicity of carbon black waste extract could be attributed mainly to the effect of vanadium. - Abstract: In Singapore, approximately 30 t/day of carbon-based solid waste are produced from petrochemical processes. This carbon black waste has been shown to possess physical properties that are characteristic of a good adsorbent such as high external surface area. Therefore, there is a growing interest to reutilize and process this carbon black waste into secondary materials such as adsorbents. However, the carbon black waste obtained from petrochemical industries may contain heavy metals that are hazardous to human health and the environment, hence restricting its full potential for re-utilization. Therefore, it is important to examine the possible toxicity effects and toxicity mechanism of carbon black waste on human health. In this study, inductively coupled plasma optical emission spectroscopy (ICP-OES) analysis showed that the heavy metals, vanadium (V), molybdenum (Mo) and nickel (Ni), were present in the carbon black waste in high concentrations. Three human cell lines (HepG2 cells, MRC-5 cells and MDA-MB-231 cells) were used to investigate the toxicity of carbon black waste extract in a variety of in vitro assays. Results from MTS assays indicated that carbon black waste extract decreased the viability of all three cell lines in a dose and time-dependent manner. Observations from confocal microscopy further confirmed this phenomenon. Flow cytometry assay also showed that carbon black waste extract induced apoptosis of human cell lines, and the level of apoptosis increased with

Nondestructive assay of sale materials

International Nuclear Information System (INIS)

Rodenburg, W.W.; Fleissner, J.G.

1981-01-01

This paper covers three primary areas: (1) reasons for performing nondestructive assay on SALE materials; (2) techniques used; and (3) discussion of investigators' revised results. The study shows that nondestructive calorimetric assay of plutonium offers a viable alternative to traditional wet chemical techniques. For these samples, the precision ranged from 0.4 to 0.6% with biases less than 0.2%. Thus, for those materials where sampling errors are the predominant source of uncertainty, this technique can provide improved accuracy and precision while saving time and money as well as reducing the amount of liquid wastes to be handled. In addition, high resolution gamma-ray spectroscopy measurements of solids can provide isotopic analysis data in a cost effective and timely manner. The timeliness of the method can be especially useful to the plant operator for production control and quality control measurements

The design of a high-efficiency neutron counter for waste drums to provide optimized sensitivity for plutonium assay

Energy Technology Data Exchange (ETDEWEB)

Menlove, H.O.; Beddingfield, D.H.; Pickrell, M.M. [Los Alamos National Lab., NM (United States)] [and others

1997-11-01

An advanced passive neutron counter has been designed to improve the accuracy and sensitivity for the nondestructive assay of plutonium in scrap and waste containers. The High-Efficiency Neutron Counter (HENC) was developed under a Cooperative Research Development Agreement between the Los Alamos National Laboratory and Canberra Industries. The primary goal of the development was to produce a passive assay system for 200-L drums that has detectability limits and multiplicity counting features that are superior to previous systems. A detectability limit figure of merit (FOM) was defined that included the detector efficiency, the neutron die-away time, and the detector`s active volume and density that determine the cosmic-ray background. Monte Carlo neutron calculations were performed to determine the parameters to provide an optimum FOM. The system includes the {sup 252}Cf {open_quotes}add-a-source{close_quotes} feature to improve the accuracy as well as statistical filters to reduce the cosmic-ray spallation neutron background. The final decision gave an efficiency of 32% for plutonium with a detector {sup 3}He tube volume that is significantly smaller than for previous high-efficiency systems for 200-L drums. Because of the high efficiency of the HENC, we have incorporated neutron multiplicity counting for matrix corrections for those cases where the plutonium is localized in nonuniform hydrogenous materials. The paper describes the design and performance testing of the advanced system. 5 refs., 8 figs., 3 tabs.

The design of a high-efficiency neutron counter for waste drums to provide optimized sensitivity for plutonium assay

International Nuclear Information System (INIS)

Menlove, H.O.; Beddingfield, D.H.; Pickrell, M.M.

1997-01-01

An advanced passive neutron counter has been designed to improve the accuracy and sensitivity for the nondestructive assay of plutonium in scrap and waste containers. The High-Efficiency Neutron Counter (HENC) was developed under a Cooperative Research Development Agreement between the Los Alamos National Laboratory and Canberra Industries. The primary goal of the development was to produce a passive assay system for 200-L drums that has detectability limits and multiplicity counting features that are superior to previous systems. A detectability limit figure of merit (FOM) was defined that included the detector efficiency, the neutron die-away time, and the detector's active volume and density that determine the cosmic-ray background. Monte Carlo neutron calculations were performed to determine the parameters to provide an optimum FOM. The system includes the 252 Cf open-quotes add-a-sourceclose quotes feature to improve the accuracy as well as statistical filters to reduce the cosmic-ray spallation neutron background. The final decision gave an efficiency of 32% for plutonium with a detector 3 He tube volume that is significantly smaller than for previous high-efficiency systems for 200-L drums. Because of the high efficiency of the HENC, we have incorporated neutron multiplicity counting for matrix corrections for those cases where the plutonium is localized in nonuniform hydrogenous materials. The paper describes the design and performance testing of the advanced system. 5 refs., 8 figs., 3 tabs

New chemical approach to obtain dense layer phosphate-based ionic conductor coating on negative electrode material surface: Synthesis way, outgassing and improvement of C-rate capability

Energy Technology Data Exchange (ETDEWEB)

Fleutot, Benoit, E-mail: benoit.fleutot@u-picardie.fr [Laboratoire de Réactivité et Chimie des Solides, Université de Picardie Jules Verne, CNRS UMR 7314, 33 rue Saint Leu, 80039 Amiens (France); Réseau sur le Stockage Electrochimique de l’Energie (RS2E), CNRS FR3459 (France); Davoisne, Carine; Gachot, Grégory; Cavalaglio, Sébastien; Grugeon, Sylvie; Viallet, Virginie [Laboratoire de Réactivité et Chimie des Solides, Université de Picardie Jules Verne, CNRS UMR 7314, 33 rue Saint Leu, 80039 Amiens (France); Réseau sur le Stockage Electrochimique de l’Energie (RS2E), CNRS FR3459 (France)

2017-04-01

Highlights: • Dense layer coating of based-phosphate ionic conductor obtained by spray-drying. • Influence of dense ionic conductor at the negative surface material on performances. • Impact of dense ionic conductor coating on outgassing phenomena. - Abstract: Li{sub 4}Ti{sub 5}O{sub 12} (LTO) based batteries have severe gassing behavior during charge/discharge and storage process, due to interfacial reactions between active material and electrolyte solution. In the same time, the electronic and ionic conductivity of pristine LTO is very poor and induces the use of nanoparticles which increase the outgassing phenomena. The coating of LTO particles could be a solution. For this the LTO spinel particles are modified with ionic conductor Li{sub 3}PO{sub 4} coating using a spray-drying method. For the first time a homogeneous thin dense layer phosphate based conductor is obtained without nanoparticles, as a thin film material. It is so possible to study the influence of ionic conductor deposited on the negative electrode material on performances by the controlled layer thickness. This coating was characterized by XRD, SEM, XPS and TEM. The electrochemical performance of Li{sub 3}PO{sub 4} coated Li{sub 4}Ti{sub 5}O{sub 12} is improved at high C-rate by the surface modification (improvement of 30 mAh g{sup −1} at 5 C-rate compared to pristine LTO for 5 nm of coating), inducing by a modification of surface energy. An optimum coating thickness was studied. This type of coating allows a significant decrease of outgassing phenomena due the conformal coating and opens the way to a great number of studies and new technologies.

New chemical approach to obtain dense layer phosphate-based ionic conductor coating on negative electrode material surface: Synthesis way, outgassing and improvement of C-rate capability

International Nuclear Information System (INIS)

Fleutot, Benoit; Davoisne, Carine; Gachot, Grégory; Cavalaglio, Sébastien; Grugeon, Sylvie; Viallet, Virginie

2017-01-01

Highlights: • Dense layer coating of based-phosphate ionic conductor obtained by spray-drying. • Influence of dense ionic conductor at the negative surface material on performances. • Impact of dense ionic conductor coating on outgassing phenomena. - Abstract: Li_4Ti_5O_1_2 (LTO) based batteries have severe gassing behavior during charge/discharge and storage process, due to interfacial reactions between active material and electrolyte solution. In the same time, the electronic and ionic conductivity of pristine LTO is very poor and induces the use of nanoparticles which increase the outgassing phenomena. The coating of LTO particles could be a solution. For this the LTO spinel particles are modified with ionic conductor Li_3PO_4 coating using a spray-drying method. For the first time a homogeneous thin dense layer phosphate based conductor is obtained without nanoparticles, as a thin film material. It is so possible to study the influence of ionic conductor deposited on the negative electrode material on performances by the controlled layer thickness. This coating was characterized by XRD, SEM, XPS and TEM. The electrochemical performance of Li_3PO_4 coated Li_4Ti_5O_1_2 is improved at high C-rate by the surface modification (improvement of 30 mAh g"−"1 at 5 C-rate compared to pristine LTO for 5 nm of coating), inducing by a modification of surface energy. An optimum coating thickness was studied. This type of coating allows a significant decrease of outgassing phenomena due the conformal coating and opens the way to a great number of studies and new technologies.

Monitoring of plutonium contaminated solid waste streams. Chapter IV: Passive neutron assay

International Nuclear Information System (INIS)

Birkhoff, G.; Bondar, L.

1978-01-01

The fundamentals of the passive neutron technique for the non destructive assay of plutonium bearing materials are summarized. A reference monitor for the passive neutron assay of Pu contaminated solids is described in terms of instrumental design principles and performances. The theoretical model of this reference monitor with pertinent nuclear data and functions for the interpretation of experimental data is given

TRU assay system and measurements

International Nuclear Information System (INIS)

Brodzinski, R.L.

1984-02-01

The measurement of the transuranic content of nuclear products or process residues has become increasingly important for the recovery of fissionable material from spent fuel elements, the identification of commercial fuel elements which have not yet reached full burnup, the measurement and recovery of transuranics from discarded or stored waste materials, the determination of the transuranic content in high gamma activity waste material scheduled for disposal, compliance with 10CFR61 by land burial operators/shippers, and the satisfaction of accountability requirements. Active neutron interrogation techniques measure either the prompt neutrons or the beta delayed neutrons from fission products following induced fission. These techniques normally only measure fissile transuranics ( 235 U, 239 Pu, and 241 Pu) and are commonly applied only to contact handleable waste. Passive neutron interrogation techniques, on the other hand, are capable of measuring all transuranics except 235 U with adequate sensitivity and will work on both contact handleable and high gamma activity wastes. Since the passive techniques are senstitive to a wider spectrum of transuranic isotopes than the active techniques, substantially less complex and less expensive than the active systems, and they have proven techniques for measuring small quantities of TRU in high gamma activity packages, the passive neutron TRU assay technology was chosen for development into the instruments discussed in this paper

Nondestructive characterization of low-level transuranic waste

International Nuclear Information System (INIS)

Barna, B.A.; Reinhardt, W.W.

1981-10-01

The use of nondestructive evaluation (NDE) methods is proposed for characterization of transuranic (TRU) waste stored at the Radioactive Waste Management Complex. These NDE methods include real-time x-ray radiography, real-time neutron radiography, x-ray and neutron computed tomography, thermal imaging, container weighing, visual examination, and acoustic measurements. An integrated NDE system is proposed for characterization and certification of TRU waste destined for eventual shipment to the Waste Isolation Pilot Plant in New Mexico. Methods for automating both the classification waste and control of a complete nondestructive evaluation/nondestructive assay system are presented. Feasibility testing of the different NDE methods, including real-time x-ray radiography, and development of automated waste classification techniques are covered as part of a five year effort designed to yield a production waste characterization system

Toxicological evaluation of complex industrial wastes: Implications for exposure assessment

Energy Technology Data Exchange (ETDEWEB)

DeMarini, D.M.; Gallagher, J.E.; Houk, V.S.; Simmons, J.E.

1990-07-01

We evaluated a variety of short-term bioassays to construct a battery of tests that could be used for assessing the biological effects of potentially hazardous complex industrial wastes. Ten samples were studied for hepatotoxicity; these samples and an additional five were studied for mutagenicity. Although the data are limited to these samples, the results suggest that the Salmonella assay (strain TA98) or a prophage-induction assay (both in the presence of S9) in combination with determination of relative liver weight and levels of a set of serum enzymes in rats may provide a battery of tests suitable to characterize complex industrial wastes for mutagenic and hepatotoxic potential. The biological activities exhibited by the wastes were not readily predicted by the chemical profiles of the wastes, emphasizing the importance of characterizing potentially hazardous complex industrial wastes by both chemical and biological means. DNA from liver, lung, and bladder of rats exposed to some of the wastes was analyzed by the 32P-postlabeling technique for the presence of DNA adducts. A waste that produced mutagenic urine produced a DNA adduct in bladder DNA. The implications of this approach for assessment of exposure to complex hazardous waste mixtures are discussed.

Metrological tests of a 200 L calibration source for HPGE detector systems for assay of radioactive waste drums.

Science.gov (United States)

Boshkova, T; Mitev, K

2016-03-01

In this work we present test procedures, approval criteria and results from two metrological inspections of a certified large volume (152)Eu source (drum about 200L) intended for calibration of HPGe gamma assay systems used for activity measurement of radioactive waste drums. The aim of the inspections was to prove the stability of the calibration source during its working life. The large volume source was designed and produced in 2007. It consists of 448 identical sealed radioactive sources (modules) apportioned in 32 transparent plastic tubes which were placed in a wooden matrix which filled the drum. During the inspections the modules were subjected to tests for verification of their certified characteristics. The results show a perfect compliance with the NIST basic guidelines for the properties of a radioactive certified reference material (CRM) and demonstrate the stability of the large volume CRM-drum after 7 years of operation. Copyright © 2015 Elsevier Ltd. All rights reserved.

Inactive trials of transport systems: phase II

International Nuclear Information System (INIS)

Haberlin, M.M.; Hardy, A.R.; Kennedy, S.T.

1986-11-01

Progress made during 1984-85 is reviewed in four sections: the design and installation of a stainless steel working floor in the mock-up of a crate handling and size reduction facility; the detailed evaluation of a single air pad of the type used on commercial air-transporter; an experimental programme designed to examine the problems associated with the operation of a commercial air-transporter; the design, manufacture and commissioning trials of two powered conveyor units which when combined complete a remotely operated transfer system for transporting crated waste into and within the mock-up facility. (author)

The behaviour and welfare of sows and piglets in farrowing crates or lactation pens.

Science.gov (United States)

Singh, C; Verdon, M; Cronin, G M; Hemsworth, P H

2017-07-01

Temporary confinement during parturition and early postpartum may provide an intermediary step preceding loose housing that offers improvement in sow and piglet welfare. Three experiments were conducted to investigate the implications of replacing farrowing crates (FCs) with an alternative housing system from 3 days postpartum until weaning. In each experiment sows farrowed in FCs and were randomly allocated at day 3 of lactation to either a FC or a pen with increased floor space (lactation pen (LP)) until weaning. In experiment 1, piglet growth and sow and piglet skin injuries were recorded for 32 sows and 128 focal piglets in these litters. Behaviour around nursing and piglet behavioural time budgets were also recorded for 24 of these litters (96 focal piglets for time budgets). In experiment 2, measures of skin injury and behavioural time budgets were conducted on 28 sows and 112 focal piglets. The behavioural response of sows to piglet vocalisation (maternal responsiveness test (MRT)) was also assessed. In experiment 3, piglet mortality from day 3 of lactation until weaning was recorded in 672 litters over 12 months. While housing did not affect piglet weight gain in experiment 1, or piglet skin injuries in experiments 1 or 2, sows in both experiments sustained more injuries in LP than FC (experiment 1, 2.9 v. 1.4; experiment 2, 2.5 v. 0.8 lesions/sow; P0.05). Thus, housing sows and litters in LP from day 3 of lactation minimises piglet mortality while improving maternal behaviour in sows and social behaviour in piglets.

Passive nondestructive assay of nuclear materials

International Nuclear Information System (INIS)

Reilly, D.; Ensslin, N.; Smith, H. Jr.; Kreiner, S.

1991-03-01

The term nondestructive assay (NDA) is applied to a series of measurement techniques for nuclear fuel materials. The techniques measure radiation induced or emitted spontaneously from the nuclear material; the measurements are nondestructive in that they do not alter the physical or chemical state of the nuclear material. NDA techniques are characterized as passive or active depending on whether they measure radiation from the spontaneous decay of the nuclear material or radiation induced by an external source. This book emphasizes passive NDA techniques, although certain active techniques like gamma-ray absorption densitometry and x-ray fluorescence are discussed here because of their intimate relation to passive assay techniques. The principal NDA techniques are classified as gamma-ray assay, neutron assay, and calorimetry. Gamma-ray assay techniques are treated in Chapters 1--10. Neutron assay techniques are the subject of Chapters 11--17. Chapters 11--13 cover the origin of neutrons, neutron interactions, and neutron detectors. Chapters 14--17 cover the theory and applications of total and coincidence neutron counting. Chapter 18 deals with the assay of irradiated nuclear fuel, which uses both gamma-ray and neutron assay techniques. Chapter 19 covers perimeter monitoring, which uses gamma-ray and neutron detectors of high sensitivity to check that no unauthorized nuclear material crosses a facility boundary. The subject of Chapter 20 is attribute and semiquantitative measurements. The goal of these measurements is a rapid verification of the contents of nuclear material containers to assist physical inventory verifications. Waste and holdup measurements are also treated in this chapter. Chapters 21 and 22 cover calorimetry theory and application, and Chapter 23 is a brief application guide to illustrate which techniques can be used to solve certain measurement problems

Material control and accountability procedures for a waste isolation repository

International Nuclear Information System (INIS)

Jenkins, J.D.; Allen, E.J.; Blakeman, E.D.

1978-05-01

The material control and accountability needs of a waste isolation repository are examined. Three levels of control are discussed: (1) item identification and control, (2) tamper indication, and (3) quantitative material assay. A summary of waste characteristics is presented and, based on these, plus a consideration of the accessibility of the various types of waste, material control by item identification and accountability (where the individual waste container is the basic unit) is recommended. Tamper indicating procedures are also recommended for the intermediate and low level waste categories

Transuranic waste management program and facilities

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

1986-01-01

Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PRFPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

Transuranic Waste Management Program and Facilities

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

1986-02-01

Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PREPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

Waste Inspection Tomography (WIT)

International Nuclear Information System (INIS)

Bernardi, R.T.

1995-01-01

Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU. The mobile feature of WIT allows inspection technologies to be brought to the nuclear waste drum storage site without the need to relocate drums for safe, rapid, and cost-effective characterization of regulated nuclear waste. The combination of these WIT characterization modalities provides the inspector with an unprecedented ability to non-invasively characterize the regulated contents of waste drums as large as 110 gallons, weighing up to 1,600 pounds. Any objects that fit within these size and weight restrictions can also be inspected on WIT, such as smaller waste bags and drums that are five and thirty-five gallons

SEPARATION AND EXTRACTION OF PLUTONIUM IN MIXED WASTE

International Nuclear Information System (INIS)

Desrosiers, Arthur E.; Kaiser, Robert; Antkowiak, Jason; Desrosiers, Justin; Jondro, Josh; Kulczyk, Adam

2002-01-01

The Sonatol process uses ultrasonic agitation in fluorinated surfactant solutions to remove radioactive particles from surfaces. Filtering the suspended particles allows the solutions to be reused indefinitely. The current work applies the Sonatol process to the decontamination of heterogeneous legacy Pu-238 waste that exhibits excessive hydrogen gas generation, which prevents transportation of the waste to the Waste Isolation Pilot Plant. Bartlett Services, Inc. (BSI) designed and fabricated a prototype decontamination system within a replica of a Savannah River Site glovebox. In Phase I, BSI conducted cold testing with surrogate waste material to verify that the equipment, operating procedures, and test protocols would support testing with Pu-238 in Phase II. The surrogate waste material is representative of known constituents of legacy job control waste. Two sub-micron sized Pu-238 simulants were added to the surrogate waste so that decontamination could be tested. The first simulant was an Osram Sylvania Phosphor 2284C powder that fluoresces under ultraviolet light. The use of the fluorescent simulant allows rapid, inexpensive system startup testing because residuals can be assayed using a digital camera. The results of digital pixel analysis (DPA) are available immediately and do not require use of licensed material. The second simulant, which was used for integrated cold testing, was a cerium oxide powder that was activated in a research reactor neutron flux and assayed by photon spectroscopy. The surrogate transuranic (TRU) waste material was contaminated with Pu-238 simulants and loaded into the cleaning chamber, where the surrogates were ultrasonically agitated and rinsed. The decontaminated materials were then assayed for surface contamination by DPA to establish optimum operating parameters and provide process quality control. Selected samples were sent to the Massachusetts Institute of Technology for neutron activation analysis (NAA). NAA testing

SEPARATION AND EXTRACTION OF PLUTONIUM IN MIXED WASTE

Energy Technology Data Exchange (ETDEWEB)

Arthur E. Desrosiers, ScD, CHP; Robert Kaiser, ScD; Jason Antkowiak; Justin Desrosiers; Josh Jondro; Adam Kulczyk

2002-12-13

The Sonatol process uses ultrasonic agitation in fluorinated surfactant solutions to remove radioactive particles from surfaces. Filtering the suspended particles allows the solutions to be reused indefinitely. The current work applies the Sonatol process to the decontamination of heterogeneous legacy Pu-238 waste that exhibits excessive hydrogen gas generation, which prevents transportation of the waste to the Waste Isolation Pilot Plant. Bartlett Services, Inc. (BSI) designed and fabricated a prototype decontamination system within a replica of a Savannah River Site glovebox. In Phase I, BSI conducted cold testing with surrogate waste material to verify that the equipment, operating procedures, and test protocols would support testing with Pu-238 in Phase II. The surrogate waste material is representative of known constituents of legacy job control waste. Two sub-micron sized Pu-238 simulants were added to the surrogate waste so that decontamination could be tested. The first simulant was an Osram Sylvania Phosphor 2284C powder that fluoresces under ultraviolet light. The use of the fluorescent simulant allows rapid, inexpensive system startup testing because residuals can be assayed using a digital camera. The results of digital pixel analysis (DPA) are available immediately and do not require use of licensed material. The second simulant, which was used for integrated cold testing, was a cerium oxide powder that was activated in a research reactor neutron flux and assayed by photon spectroscopy. The surrogate transuranic (TRU) waste material was contaminated with Pu-238 simulants and loaded into the cleaning chamber, where the surrogates were ultrasonically agitated and rinsed. The decontaminated materials were then assayed for surface contamination by DPA to establish optimum operating parameters and provide process quality control. Selected samples were sent to the Massachusetts Institute of Technology for neutron activation analysis (NAA). NAA testing

Waste characterization: What's on second?

International Nuclear Information System (INIS)

Schultz, F.J.; Smith, M.A.

1989-07-01

Waste characterization is the process whereby the physical properties and chemical composition of waste are determined. Waste characterization is an important element which is necessary to certify that waste meets the acceptance criteria for storage, treatment, or disposal. Department of Energy (DOE) Orders list and describe the germane waste form, package, and container criteria for the storage of both solid low-level waste package, and container criteria for the storage of both solid low-level waste (SLLW) and transuranic (TRU) waste, including chemical composition and compatibility, hazardous material content (e.g., lead), fissile material content, radioisotopic inventory, particulate content, equivalent alpha activity, thermal heat output, and absence of free liquids, explosives, and compressed gases. At the Oak Ridge National Laboratory (ORNL), the responsibility for waste characterization begins with the individual or individuals who generate the waste. The generator must be able to document the type and estimate the quantity of various materials (e.g., waste forms -- physical characteristics, chemical composition, hazardous materials, major radioisotopes) which have been placed into the waste container. Analyses of process flow sheets and a statistically valid sampling program can provide much of the required information as well as a documented level of confidence in the acquired data. A program is being instituted in which major generator facilities perform radionuclide assay of small packets of waste prior to being placed into a waste drum. 17 refs., 1 fig., 4 tabs

An improved segmented gamma scanning for radioactive waste drums

International Nuclear Information System (INIS)

Liu Cheng; Wang Dezhong; Bai Yunfei; Qian Nan

2010-01-01

In this paper, the equivalent radius of radioactive sources in each segment is determined by analyzing the different responses of the two identical detectors, and an improved segmented gamma scanning is used to assay waste drums containing mainly organic materials, and proved by an established simulation model. The simulated radioactivity distributions in homogenous waste drum and an experimental heterogeneous waste drum were compared with those of traditional segmented gamma scanning. The results show that our method is good in performance and can be used for analyzing the waste drums. (authors)

TRU waste-sampling program

International Nuclear Information System (INIS)

Warren, J.L.; Zerwekh, A.

1985-08-01

As part of a TRU waste-sampling program, Los Alamos National Laboratory retrieved and examined 44 drums of 238 Pu- and 239 Pu-contaminated waste. The drums ranged in age from 8 months to 9 years. The majority of drums were tested for pressure, and gas samples withdrawn from the drums were analyzed by a mass spectrometer. Real-time radiography and visual examination were used to determine both void volumes and waste content. Drum walls were measured for deterioration, and selected drum contents were reassayed for comparison with original assays and WIPP criteria. Each drum tested at atmospheric pressure. Mass spectrometry revealed no problem with 239 Pu-contaminated waste, but three 8-month-old drums of 238 Pu-contaminated waste contained a potentially hazardous gas mixture. Void volumes fell within the 81 to 97% range. Measurements of drum walls showed no significant corrosion or deterioration. All reassayed contents were within WIPP waste acceptance criteria. Five of the drums opened and examined (15%) could not be certified as packaged. Three contained free liquids, one had corrosive materials, and one had too much unstabilized particulate. Eleven drums had the wrong (or not the most appropriate) waste code. In many cases, disposal volumes had been inefficiently used. 2 refs., 23 figs., 7 tabs

Field test results for radioactive waste drum characterization with Waste Inspection Tomography (WIT)

Energy Technology Data Exchange (ETDEWEB)

Bernardi, R.T. [Bio-Imaging Research, Inc., Lincolnshire, IL (United States)

1997-11-01

This paper summarizes the design, fabrication, factory testing, evaluation and demonstration of waste inspection tomography (WIT). WIT consists of a self-sufficient, mobile semi-trailer for Non-Destructive Evaluation and Non-Destructive Assay (NDE/NDA) characterization of nuclear waste drums using X-ray and gamma-ray tomographic techniques. The 23-month WIT Phase I initial test results include 2 MeV Digital Radiography (DR), Computed Tomography (CT), Anger camera imaging, Single Photon Emission Computed Tomography (SPECT), Gamma-Ray Spectroscopy, Collimated Gamma Scanning (CGS), and Active and Passive Computed Tomography (A&PCT) using a 1.4 mCi source of {sup 166}Ho. These techniques were initially demonstrated on a 55-gallon phantom drum with three simulated waste matrices of combustibles, heterogeneous metals, and cement using check sources of gamma active isotopes. Waste matrix identification, isotopic identification, and attenuation-corrected gamma activity determination were all demonstrated nondestructively and noninvasively. Preliminary field tests results with nuclear waste drums are summarized. WIT has inspected drums with 0 to 20 grams plutonium 239. The minimum measured was 0.131 gram plutonium 239 in cement. 8 figs.

Epithermal interrogation of fissile waste

International Nuclear Information System (INIS)

Coop, K.L.; Hollas, C.L.

1996-01-01

Self-shielding of interrogating thermal neutrons in lumps of fissile material can be a major source of error in transuranic waste assay using the widely employed differential dieaway technique. We are developing a new instrument, the combined thermal/epithermal neutron (CTEN) interrogation instrument to detect the occurrence of self- shielding and mitigate its effects. Neutrons are moderated in the graphite walls of the CTEN instrument to provide an interrogating flux of epithermal and thermal neutrons. The induced prompt fission neutrons are detected in proportional counters. We report the results of measurements made with the CTEN instrument, using minimal and highly self-shielding plutonium and uranium sources in 55 gallon drums containing a variety of mock waste matrices. Fissile isotopes and waste forms for which the method is most applicable, and limitations associated with the hydrogen content of the waste package/matrix are described

Los Alamos Scientific Laboratory waste management technology development activities. Summary progress report, 1979

International Nuclear Information System (INIS)

Johnson, L.J.

1980-10-01

Summary reports on the Department of Energy's Nuclear Energy-sponsored waste management technology development projects at the Los Alamos Scientific Laboratory describe progress for calendar year 1979. Activities in airborne, low-level, and transuranic waste management areas are discussed. Work progress on waste assay, treatment, disposal, and environmental monitoring is reviewed

Nonradioactive air emissions notice of construction for the Waste Receiving And Processing facility

International Nuclear Information System (INIS)

1993-02-01

The mission of the Waste Receiving And Processing (WRAP) Module 1 facility (also referred to as WRAP 1) is to examine assay, characterize, treat, and repackage solid radioactive and mixed waste to enable permanent disposal of the wastes in accordance with all applicable regulations. WRAP 1 will contain equipment and facilities necessary for non-destructive examination (NDE) of wastes and to perform a non-destructive examination assay (NDA) of the total radionuclide content of the wastes, without opening the outer container (e.g., 55-gal drum). WRAP 1 will also be equipped to open drums which do not meet waste acceptance and shipping criteria, and to perform limited physical treatment of the wastes to ensure that storage, shipping, and disposal criteria are met. The solid wastes to be handled in the WRAP 1 facility include low level waste (LLW), transuranic (TRU) waste, and transuranic and low level mixed wastes (LLMW). The WRAP 1 facility will only accept contact handler (CH) waste containers. A Best Available Control Technology for Toxics (TBACT) assessment has been completed for the WRAP 1 facility (WHC 1993). Because toxic emissions from the WRAP 1 facility are sufficiently low and do not pose any health or safety concerns to the public, no controls for volatile organic compounds (VOCs), and installation of HEPA filters for particulates satisfy TBACT for the facility

Los Alamos Scientific Laboratory waste management technology development activities. Summary progress report, 1979

Energy Technology Data Exchange (ETDEWEB)

Johnson, L.J. (comp.)

1980-10-01

Summary reports on the Department of Energy's Nuclear Energy-sponsored waste management technology development projects at the Los Alamos Scientific Laboratory describe progress for calendar year 1979. Activities in airborne, low-level, and transuranic waste management areas are discussed. Work progress on waste assay, treatment, disposal, and environmental monitoring is reviewed.

Activity monitoring of alpha-bearing wastes

International Nuclear Information System (INIS)

Birkhoff, G.; Bondar, L.

1980-01-01

The paper aims at the survey on the actual situation in activity monitoring of alpha-bearing wastes. Homogeneous materials such as liquid-, gaseous- and homogeneous solid wastes are amenable to destructive analyses of representative samples. Available destructive analyses methods are sensitive and precise enough to cope with all requirements in alpha-waste monitoring. The more difficult problems are encountered with alpha-contaminated solids, when representative sampling is not practicable. Non-destructive analysis techniques are applied for monitoring this category of solid wastes. The techniques for nondestructive analysis of alpha-bearing wastes are based on the detection of gamma and/or neutron-emission of actinides. Principles and a theory of non-destructive radiometric assay of plutonium contaminated solid waste streams are explained. Guidelines for the calibration of instruments and interpretation of experimental data are given. Current theoretical and experimental development work in this problem area is reviewed. Evaluations concerning capabilities and limitations of monitoring systems for alpha-bearing solid wastes are very complex and out of the scope of this paper

A neutron well counter for plutonium assay in 200 l waste drums

International Nuclear Information System (INIS)

Eyrich, W.; Kuechle, M.; Shafiee, M.

1979-05-01

A neutron well counter is briefly described which will be used for monitoring the plutonium content of 200 l barrels in the waste treatment plant of the Kernforschungszentrum Karlsruhe. Measurements on simulated waste were made to study the influence of matrix material and non-homogeneous plutonium distribution. The variation in detection efficiency could be reduced from 28% to 10% when the signals from inner and outer neutron detectors in the polyethylene annulus are counted separately and a correction is applied, using this information. This method is superior to the source addition technique. Coincidence counting shows a larger variation which could not be reduced to below 18%. (orig.) [de

WRAP Module 1 waste characterization plan

International Nuclear Information System (INIS)

Mayancsik, B.A.

1995-01-01

The purpose of this document is to present the characterization methodology for waste generated, processed, or otherwise the responsibility of the Waste Receiving and Processing (WRAP) Module 1 facility. The scope of this document includes all solid low level waste (LLW), transuranic (TRU), mixed waste (MW), and dangerous waste. This document is not meant to be all-inclusive of the waste processed or generated within WRAP Module 1, but to present a methodology for characterization. As other streams are identified, the method of characterization will be consistent with the other streams identified in this plan. The WRAP Module 1 facility is located in the 200 West Area of the Hanford Site. The facility's function is two-fold. The first is to verify/characterize, treat and repackage contact handled (CH) waste currently in retrievable storage in the LLW Burial Grounds, Hanford Central Waste Complex, and the Transuranic Storage and Assay Facility (TRUSAF). The second is to verify newly generated CH TRU waste and LLW, including MW. The WRAP Module 1 facility provides NDE and NDA of the waste for both drums and boxes. The NDE is used to identify the physical contents of the waste containers to support waste characterization and processing, verification, or certification. The NDA results determine the radioactive content and distribution of the waste

Uncertainty analysis of a nondestructive radioassay system for transuranic waste

International Nuclear Information System (INIS)

Harker, Y.D.; Blackwood, L.G.; Meachum, T.R.; Yoon, W.Y.

1996-01-01

Radioassay of transuranic waste in 207 liter drums currently stored at the Idaho National Engineering Laboratory is achieved using a Passive Active Neutron (PAN) nondestructive assay system. In order to meet data quality assurance requirements for shipping and eventual permanent storage of these drums at the Waste Isolation Pilot Plant in Carlsbad, New Mexico, the total uncertainty of the PAN system measurements must be assessed. In particular, the uncertainty calculations are required to include the effects of variations in waste matrix parameters and related variables on the final measurement results. Because of the complexities involved in introducing waste matrix parameter effects into the uncertainty calculations, standard methods of analysis (e.g., experimentation followed by propagation of errors) could not be implemented. Instead, a modified statistical sampling and verification approach was developed. In this modified approach the total performance of the PAN system is simulated using computer models of the assay system and the resultant output is compared with the known input to assess the total uncertainty. This paper describes the simulation process and illustrates its application to waste comprised of weapons grade plutonium-contaminated graphite molds

The Hanford Site solid waste treatment project; Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

Roberts, R.J.

1991-01-01

The Waste Receiving and Processing (WRAP) Facility will provide treatment and temporary storage (consisting of in-process storage) for radioactive and radioactive/hazardous mixed waste. This facility must be constructed and operated in compliance with all appropriate US Department of Energy (DOE) orders and Resource Conservation and Recovery Act (RCRA) regulations. The WRAP Facility will examine and certify, segregate/sort, and treat for disposal suspect transuranic (TRU) wastes in drums and boxes placed in 20-yr retrievable storage since 1970; low-level radioactive mixed waste (RMW) generated and placed into storage at the Hanford Site since 1987; designated remote-handled wastes; and newly generated TRU and RMW wastes from high-level waste (HLW) recovery and processing operations. In order to accelerated the WRAP Project, a partitioning of the facility functions was done in two phases as a means to expedite those parts of the WRAP duties that were well understood and used established technology, while allowing more time to better define the processing functions needed for the remainder of WRAP. The WRAP Module 1 phase one, is to provide the necessary nondestructive examination and nondestructive assay services, as well as all transuranic package transporter (TRUPACT-2) shipping for both WRAP Project phases, with heating, ventilation, and air conditioning; change rooms; and administrative services. Phase two of the project, WRAP Module 2, will provide all necessary waste treatment facilities for disposal of solid wastes. 1 tab

Management of radioactive solid waste arisings from PFR reprocessing

International Nuclear Information System (INIS)

Allardice, R.H.; Hackney, S.; Bailey, G.; Bremner, W.; Lillyman, E.; Pugh, O.; Reekie, J.

1982-01-01

A description is given of the solid radioactive waste management facilities for dealing with the arisings from PFR reprocessing at the Dounreay Nuclear Power Development Establishment. Four major categories of solid waste are identified. The 'La Calhene' posting system for the transfer of active wastes which has been installed is discussed. The three new retrievable stores for high α#betta##betta#, high α low #betta##betta# and low α high #betta##betta# are described. The methods of waste categorisation by non-destructive assay techniques are outlined. Finally a review of operating experience with the facilities is presented. (U.K.)

Hidroquímica do carbonato e bicarbonato: efeito na qualidade de águas subterrâneas em Crateús, Ceará, Brasil

Directory of Open Access Journals (Sweden)

José Ossian Gadelha de Lima

2014-07-01

Full Text Available O município de Crateús está localizado na região semiárida do Nordeste do Brasil, onde as condições climáticas provocam escassez hídrica e baixa qualidade nas águas disponíveis. Este trabalho teve por objetivo estudar, durante um ano, o comportamento do pH e das concentrações dos íons carbonato (CO3 2- e bicarbonato (HCO3 - nas águas de oito poços utilizadas para irrigação de pequenas culturas e consumo doméstico. Os resultados mostraram que nenhuma das amostras apresentou valor de pH que comprometesse sua qualidade, tanto para uso na irrigação, quanto para consumo humano. No entanto, os íons bicarbonato e carbonato apresentaram grau de restrição que varia de leve a severo. Portanto, seu uso na agricultura demanda monitoramento e cuidados rigorosos para amenizar os efeitos negativos na produtividade e no solo.

Kinetic modelling of anaerobic hydrolysis of solid wastes, including disintegration processes

Energy Technology Data Exchange (ETDEWEB)

García-Gen, Santiago [Department of Chemical Engineering, Institute of Technology, University of Santiago de Compostela, 15782 Santiago de Compostela (Spain); Sousbie, Philippe; Rangaraj, Ganesh [INRA, UR50, Laboratoire de Biotechnologie de l’Environnement, Avenue des Etangs, Narbonne F-11100 (France); Lema, Juan M. [Department of Chemical Engineering, Institute of Technology, University of Santiago de Compostela, 15782 Santiago de Compostela (Spain); Rodríguez, Jorge, E-mail: jrodriguez@masdar.ac.ae [Department of Chemical Engineering, Institute of Technology, University of Santiago de Compostela, 15782 Santiago de Compostela (Spain); Institute Centre for Water and Environment (iWater), Masdar Institute of Science and Technology, PO Box 54224 Abu Dhabi (United Arab Emirates); Steyer, Jean-Philippe; Torrijos, Michel [INRA, UR50, Laboratoire de Biotechnologie de l’Environnement, Avenue des Etangs, Narbonne F-11100 (France)

2015-01-15

Highlights: • Fractionation of solid wastes into readily and slowly biodegradable fractions. • Kinetic coefficients estimation from mono-digestion batch assays. • Validation of kinetic coefficients with a co-digestion continuous experiment. • Simulation of batch and continuous experiments with an ADM1-based model. - Abstract: A methodology to estimate disintegration and hydrolysis kinetic parameters of solid wastes and validate an ADM1-based anaerobic co-digestion model is presented. Kinetic parameters of the model were calibrated from batch reactor experiments treating individually fruit and vegetable wastes (among other residues) following a new protocol for batch tests. In addition, decoupled disintegration kinetics for readily and slowly biodegradable fractions of solid wastes was considered. Calibrated parameters from batch assays of individual substrates were used to validate the model for a semi-continuous co-digestion operation treating simultaneously 5 fruit and vegetable wastes. The semi-continuous experiment was carried out in a lab-scale CSTR reactor for 15 weeks at organic loading rate ranging between 2.0 and 4.7 g VS/L d. The model (built in Matlab/Simulink) fit to a large extent the experimental results in both batch and semi-continuous mode and served as a powerful tool to simulate the digestion or co-digestion of solid wastes.

Westinghouse Hanford Company plan for certifying newly generated contact-handled transuranic waste for emplacement in the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Lipinski, R.M.; Sheehan, J.S.

1992-07-01

Westinghouse Hanford Company (Westinghouse Hanford) currently manages an interim storage site for Westinghouse Hanford and non-Westinghouse Hanford-generated transuranic (TRU) waste and operates TRU waste generating facilities within the Hanford Site in Washington State. Approval has been received from the Waste Acceptance Criteria Certification Committee (WACCC) and Westinghouse Hanford TRU waste generating facilities to certify newly generated contact-handled TRU (CH-TRU) solid waste to meet the Waste Acceptance Criteria (WAC). This document describes the plan for certifying newly generated CH-TRU solid waste to meet the WAC requirements for storage at the Waste Isolation Pilot Plant (WIPP) site. Attached to this document are facility-specific certification plans for the Westinghouse Hanford TRU waste generators that have received WACCC approval. The certification plans describe operations that generate CH-TRU solid waste and the specific procedures by which these wastes will be certified and segregated from uncertified wastes at the generating facilities. All newly generated CH-TRU solid waste is being transferred to the Transuranic Storage and Assay Facility (TRUSAF) and/or a controlled storage facility. These facilities will store the waste until the certified TRU waste can be sent to the WIPP site and the non-certified TRU waste can be sent to the Waste Receiving and Processing Facility. All non-certifiable TRU waste will be segregated and clearly identified

Treatment of alpha bearing wastes

International Nuclear Information System (INIS)

1988-01-01

This report deals with the current state of the art of alpha waste treatment, which is an integral part of the overall nuclear waste management system. The International Atomic Energy Agency (IAEA) defines alpha bearing waste as 'waste containing one or more alpha emitting radionuclides, usually actinides, in quantities above acceptable limits'. The limits are established by national regulatory bodies. The limits above which wastes are considered as alpha contaminated refer to the concentrations of alpha emitters that need special consideration for occupational exposures and/or potential safety, health, or environmental impact during one or more steps from generation through disposal. Owing to the widespread use of waste segregation by source - that is, based upon the 'suspect origin' of the material - significant volumes of waste are being handled as alpha contaminated which, in fact, do not require such consideration by reason of risk or environmental concern. The quantification of de minimis concepts by national regulatory bodies could largely contribute to the safe reduction of waste volumes and associated costs. Other factors which could significantly contribute to the reduction of alpha waste arisings are an increased application of assaying and sorting, instrumentation and the use of feedback mechanisms to control or modify the processes which generate these wastes. Alpha bearing wastes are generated during fabrication and reprocessing of nuclear fuels, decommissioning of alpha contaminated facilities, and other activities. Most alpha wastes are contact handled, but a small portion may require shielding or remote handling because of high levels of neutron (n), beta (β), or gamma (γ) emissions associated with the waste material. This report describes the sources and characteristics of alpha wastes and strategies for alpha waste management. General descriptions of treatment processes for solid and liquid alpha wastes are included. 71 refs, 14 figs, 9 tabs

Enzyme Activities in Waste Water and Activated Sludge

DEFF Research Database (Denmark)

Nybroe, Ole; Jørgensen, Per Elberg; Henze, Mogens

1992-01-01

The purpose of the present study was to evaluate the potential of selected enzyme activity assays to determine microbial abundance and heterotrophic activity in waste water and activated sludge. In waste water, esterase and dehydrogenase activities were found to correlate with microbial abundance...... measured as colony forming units of heterotrophic bacteria. A panel of four enzyme activity assays, α-glucosidase, alanine-aminopeptidase, esterase and dehydrogenase were used to characterize activated sludge and anaerobic hydrolysis sludge from a pilot scale plant. The enzymatic activity profiles were...... distinctly different, suggesting that microbial populations were different, or had different physiological properties, in the two types of sludge. Enzyme activity profiles in activated sludge from four full-scale plants seemed to be highly influenced by the composition of the inlet. Addition of hydrolysed...

ANALYSIS OF SPECIAL WASTE CONFIGURATIONS AT THE SRS WASTE MANAGEMENT FACILITIES

International Nuclear Information System (INIS)

Casella, V; Raymond Dewberry, R

2007-01-01

Job Control Waste (JCW) at the Savannah River Site (SRS) Solid Waste Management Facilities (SWMF) may be disposed of in special containers, and the analysis of these containers requires developing specific analysis methodologies. A method has been developed for the routine assay of prohibited items (liquids, etc.) contained in a 30-gallon drum that is then placed into a 55-gallon drum. Method development consisted of system calibration with a NIST standard at various drum-to-detector distances, method verification with a liquid sample containing a known amount of Pu-238, and modeling the inner container using Ortec Isotopic software. Using this method for measurement of the known standard in the drum-in-drum configuration produced excellent agreement (within 15%) with the known value. Savannah River Site Solid Waste Management also requested analysis of waste contained in large black boxes (commonly 18-feet x 12-feet x 7-feet) stored at the SWMF. These boxes are frequently stored in high background areas and background radiation must be considered for each analysis. A detection limit of less than 150 fissile-gram-equivalents (FGE) of TRU waste is required for the black-box analyses. There is usually excellent agreement for the measurements at different distances and measurement uncertainties of about 50% are obtained at distances of at least twenty feet from the box. This paper discusses the experimental setup, analysis and data evaluation for drum-in-drum and black box waste configurations at SRS

Acceptance and tracking of waste packages from nuclear power plants at the Centre de l'Aube

International Nuclear Information System (INIS)

Errera, J.; Tison, J.L.

2001-01-01

For 30 years, the French National Agency for Radioactive Waste Management (ANDRA) is in charge of the radioactive waste management and acquired a good knowledge relating to the control of low and intermediate level waste produced by nuclear power plants (NPP), the waste characteristics and the waste conditioning. The integrated waste management system for low-level radioactive waste in France implemented by ANDRA covers all stages from waste generation to final disposal at the Centre de I'Aube near surface facility. ANDRA defined a quality assurance program for waste management that specifies the level of quality to be achieved by solidification and packaging processes, defines quality control requirements and defines waste tracking requirements, from waste generation through final disposal. Verification of quality of waste packages is implemented at three levels of the waste management system. The first one consists of inspections of waste packages at the generator's premises and audits of the quality assurance organization of the waste generator. The second level of verification consists of the waste tracking system. It allows identifying and tracking each waste package from the step it is fabricated to its final disposal at the ANDRA site. The third level of verification is obtained by mean of non-destructive and destructive assays of waste packages. These assays allow to verify generator compliance with ANDRA's technical specifications and to investigate the accuracy of physical and radioactive characteristics reported to ANDRA by the generator. (author)

Feasibility study of a waste assay system and the possibility of volume reduction at the Puespoekszilagy RWTDF

International Nuclear Information System (INIS)

Takats, F.

2001-05-01

A review of the types and activities of the waste emplaced at the Pupokszilagy Radioactive Waste Treatment and Disposal Facility (RWTDF) was performed on the basis of the existing operational data. This provided a breakdown of all important parameters of the wastes as well as of the disposal conditions for each disposal unit. Prior to the detailed review, the behaviour of the compacted wastes, simulating those in the repository, was tested with a view to determine the efficiency of a further supercompaction. Based on the evaluation of market data, the cost of purchasing or renting a super-compactor unit and the resulting unit costs were calculated. A detailed review of the free release strategies and the available equipment was prepared. To provide an immediate remedy to the shortage of disposal volume, it is suggested to retrieve the old Institutional wastes and the sealed radioactive sources, and use the existing free space for further waste disposal. As an alternative, the use of residual free space in the vaults for further disposal, without waste recovery, is also reviewed. (author)

Characterization of transuranic solid wastes from a plutonium processing facility

International Nuclear Information System (INIS)

Mulkin, R.

1975-06-01

Transuranic-contaminated wastes generated in the processing areas of the Plutonium Chemistry and Metallurgy Group at the Los Alamos Scientific Laboratory (LASL) were studied in detail to identify their chemical and physical composition. Nondestructive Assay (NDA) equipment was developed to measure transuranic activity at the 10-nCi/g level in low-density residues typically found in room-generated waste. This information will supply the Waste Management Program with a more positive means of identifying concerns in waste storage and the challenge of optimizing the system of waste form, packaging, and environment of the storage area for 20-yr retrievable waste. A positive method of measuring transuranic activity in waste at the 10-nCi/g level will eliminate the need for administrative control in a sensitive area, and will provide the economic advantage of minimizing the volume of waste stored as retrievable waste. (U.S.)

Technologies for recovery of transuranics and immobilization of non-high-level wastes

International Nuclear Information System (INIS)

Richardson, G.L.

1976-06-01

This paper supplements the preceding Symposium paper on ''Treatment Technologies for Non-High-Level Wastes (U.S.A.)'' by C. R. Cooley and D. E. Clark (HEDL-SA-851), and covers the additional treatment technologies in use and under development for recovering transuranics and immobilizing non-high-level wastes for transportation and storage. Methods used for nondestructive assay (NDA) of TRU elements in non-high-level wastes are also discussed briefly

A prototype of radioactive waste drum monitor by non-destructive assays using gamma spectrometry

International Nuclear Information System (INIS)

Thanh, Tran Thien; Trang, Hoang Thi Kieu; Chuong, Huynh Dinh; Nguyen, Vo Hoang; Tran, Le Bao; Tam, Hoang Duc; Tao, Chau Van

2016-01-01

In this work, segmented gamma scanning and the gamma emission tomography were used to locate unknown sources in a radioactive waste drum. The simulated detector response function and full energy peak efficiency are compared to corresponding experimental data and show about 5.3% difference for an energy ranging from 81 keV to 1332.5 keV for point sources. Computation of the corresponding activity is in good agreement with the true values. - Highlights: • Segmented gamma scanning and gamma emission tomography are used to locate point source in waste drums. • The PENELOPE software is used to compute the detection efficiency of the localized point source in the waste drum. • The activity of "1"3"7Cs and "6"0Co point source could be determined with an accuracy better than 10% for air and sand matrices.

The Stored Waste Examination Pilot Plant program at the INEL

International Nuclear Information System (INIS)

McKinley, K.B.; Anderson, B.C.; Clements, T.L.; Hinckley, J.P.; Mayberry, J.L.; Smith, T.H.

1983-01-01

Since 1970, defense transuranic waste has been placed into 20-year retrievable storage at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL). A major objective of the U.S. Department of Energy (DOE) Nuclear Waste Management Program is to remove all retrievably stored transuranic waste from the INEL. The January 1981 DOE Record of Decision on the Waste Isolation Pilot Plant (WIPP) stated, ''The WIPP facility will dispose of defense transuranic waste stored retrievably at the Idaho National Engineering Laboratory.'' After retrieval and before shipment, processing may be necessary to prepare the waste for acceptance, handling, and enhanced long-term isolation in the WIPP. However, some of the waste is certifiable to the WIPP waste acceptance criteria without container opening or waste processing. To minimize costs, the Stored Waste Examination Pilot Plant (SWEPP) is being developed to certify INEL stored transuranic waste without container opening or waste processing. The SWEPP certification concept is based on records assessment, nondestructive examination techniques, assay techniques, health physics examinations, and limited opening of containers at another facility for quality control

Advances in measurement of alpha-contaminated wastes

International Nuclear Information System (INIS)

Close, D.A.; Crane, T.W.; Caldwell, J.T.; Kunz, W.E.; Shunk, E.R.; Pratt, J.C.; Franks, L.A.; Kominski, S.M.

1982-01-01

A comprehensive program is in progress at the Los Alamos National Laboratory for the development of sensitive, practical, nondestructive assay techniques for the quantification of low-level transuranics in bulk solid wastes. The program encompasses a broad range of techniques, including sophisticated active and passive gamma-ray spectroscopy, passive neutron detection systems, pulsed portable neutron generator interrogation systems, and electron accelerator-based techniques. The techniques can be used with either low-level or high-level beta-gamma wastes in either low-density or high-density matrices

Development of the remote-handled transuranic waste radioassay data quality objectives. An evaluation of RH-TRU waste inventories, characteristics, radioassay methods and capabilities

Energy Technology Data Exchange (ETDEWEB)

Meeks, A.M.; Chapman, J.A.

1997-09-01

The Waste Isolation Pilot Plant will accept remote-handled transuranic waste as early as October of 2001. Several tasks must be accomplished to meet this schedule, one of which is the development of Data Quality Objectives (DQOs) and corresponding Quality Assurance Objectives (QAOs) for the assay of radioisotopes in RH-TRU waste. Oak Ridge National Laboratory (ORNL) was assigned the task of providing to the DOE QAO, information necessary to aide in the development of DQOs for the radioassay of RH-TRU waste. Consistent with the DQO process, information needed and presented in this report includes: identification of RH-TRU generator site radionuclide data that may have potential significance to the performance of the WIPP repository or transportation requirements; evaluation of existing methods to measure the identified isotopic and quantitative radionuclide data; evaluation of existing data as a function of site waste streams using documented site information on fuel burnup, radioisotope processing and reprocessing, special research and development activities, measurement collection efforts, and acceptable knowledge; and the current status of technologies and capabilities at site facilities for the identification and assay of radionuclides in RH-TRU waste streams. This report is intended to provide guidance in developing the RH-TRU waste radioassay DQOs, first by establishing a baseline from which to work, second, by identifying needs to fill in the gaps between what is known and achievable today and that which will be required before DQOs can be formulated, and third, by recommending measures that should be taken to assure that the DQOs in fact balance risk and cost with an achievable degree of certainty.

Development of the remote-handled transuranic waste radioassay data quality objectives. An evaluation of RH-TRU waste inventories, characteristics, radioassay methods and capabilities

International Nuclear Information System (INIS)

Meeks, A.M.; Chapman, J.A.

1997-09-01

The Waste Isolation Pilot Plant will accept remote-handled transuranic waste as early as October of 2001. Several tasks must be accomplished to meet this schedule, one of which is the development of Data Quality Objectives (DQOs) and corresponding Quality Assurance Objectives (QAOs) for the assay of radioisotopes in RH-TRU waste. Oak Ridge National Laboratory (ORNL) was assigned the task of providing to the DOE QAO, information necessary to aide in the development of DQOs for the radioassay of RH-TRU waste. Consistent with the DQO process, information needed and presented in this report includes: identification of RH-TRU generator site radionuclide data that may have potential significance to the performance of the WIPP repository or transportation requirements; evaluation of existing methods to measure the identified isotopic and quantitative radionuclide data; evaluation of existing data as a function of site waste streams using documented site information on fuel burnup, radioisotope processing and reprocessing, special research and development activities, measurement collection efforts, and acceptable knowledge; and the current status of technologies and capabilities at site facilities for the identification and assay of radionuclides in RH-TRU waste streams. This report is intended to provide guidance in developing the RH-TRU waste radioassay DQOs, first by establishing a baseline from which to work, second, by identifying needs to fill in the gaps between what is known and achievable today and that which will be required before DQOs can be formulated, and third, by recommending measures that should be taken to assure that the DQOs in fact balance risk and cost with an achievable degree of certainty

Performance in the WIPP nondestructive assay performance demonstration program

Energy Technology Data Exchange (ETDEWEB)

Marcinkiewicz, C.J. [Consolidated Technical Services, Inc., Frederick, MD (United States); Connolly, M.J.; Becker, G.K. [Lockheed Martin Idaho Technologies Company, Idaho Falls, ID (United States)

1997-11-01

Measurement facilities performing nondestructive assay (NDA) of wastes intended for disposal at the United States Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) are required to demonstrate their ability to meet specific Quality Assurance Objectives (QAOs). This demonstration is performed, in part, by participation in the NDA Performance Demonstration Program (PDP). The PDP is funded and managed by the Carlsbad Area Office (CAO) of DOE and is conducted by the Idaho National Engineering Laboratory. It tests the characteristics of precision, system bias and/or total uncertainty through the measurement of variable, blind combinations of simulated waste drums and certified radioactive standards. Each facility must successfully participate in the PDP using each different type of measurement system planned for use in waste characterization. The first cycle of the PDP using each different type of measurement system planned for use in waste characterization. The first cycle of the PDP was completed in July 1996 and the second is scheduled for completion by December 1996. Seven sites reported data in cycle 1 for 11 different measurement systems. This paper describes the design and operation of the PDP and provides the performance data from cycle 1. It also describes the preliminary results from cycle 2 and updates the status and future plans for the NDA PDP. 4 refs., 9 figs., 11 tabs.

Relative mass resolution technique for optimum design of a gamma nondestructive assay system

International Nuclear Information System (INIS)

Koh, Duck Joon

1995-02-01

Nondestructive assay(NDA) is a widely used nuclear technology for quantitative elemental and isotopic assay. Nondestructive assay is performed by the detection of an identifying radiation emerging from the sample, which can be unambiguously related to the element or isotope of interest. In every assay we can identify two distinct factors that lead to measurement uncertainty. We refer to these as statistical and spatial uncertainties. If the spatial distribution of the analyte and the matrix material in the sample are known and fairly constant from sample to sample, then the major source of measurement uncertainty is the statistical uncertainty resulting from randomness in the counting process. The spatial uncertainty is independent of the measurement time and therefore sets a lower limit to the measurement uncertainty, which is inherent in the assay system in conjunction with the population of samples to be measured. The only way to minimize the spatial uncertainty is an optimized design of the assay system. Therefore we have to decide on the type and number of detectors to be used, their deployment around the sample, the type of radiation to be measured, the duration of each measurement, the size and shape of the sample drum. The design procedure leading to the optimal assay system should be based on a quantitative(RMR:Relative Mass Resolution) comparison of the performance of each proposed design. For NDA system design of low level radwaste, a specific purpose Monte Carlo code has been developed to simulate point-source responses for sources within an assayed radwaste drum and to analyze the effect of scattered gammas from higher energy gammas on the spectrum of a low energy gamma-ray. We could use the well-known Monte Carlo code, such as MCNP for the simulation of NDA in the case of low level radwaste. But, MCNP is a multi-purpose Monte Carlo transport code for several geometries which requires large memory and long CPU time. For some cases in nuclear

Preliminary concepts: materials management in an internationally safeguarded nuclear-waste geologic repository

International Nuclear Information System (INIS)

Ostenak, C.A.; Whitty, W.J.; Dietz, R.J.

1979-11-01

Preliminary concepts of materials accountability are presented for an internationally safeguarded nuclear-waste geologic repository. A hypothetical reference repository that receives nuclear waste for emplacement in a geologic medium serves to illustrate specific safeguards concepts. Nuclear wastes received at the reference repository derive from prior fuel-cycle operations. Alternative safeguards techniques ranging from item accounting to nondestructive assay and waste characteristics that affect the necessary level of safeguards are examined. Downgrading of safeguards prior to shipment to the repository is recommended whenever possible. The point in the waste cycle where international safeguards may be terminate depends on the fissile content, feasibility of separation, and practicable recoverability of the waste: termination may not be possible if spent fuels are declared as waste

Recent developments at Los Alamos for the measurement of alpha contaminated waste

International Nuclear Information System (INIS)

Caldwell, J.T.; Cates, M.R.; Close, D.A.; Crane, T.W.; Kunz, W.E.; Shunk, E.R.; Umbarger, C.J.; Franks, L.A.

1980-01-01

A comprehensive program is currently in progress for the development of sensitive, practical nondestructive assay techniques for the quantification of low level transuranics in bulk solid wastes. This program encompasses a broad range of nuclear and nonnuclear techniques including sophisticated passive gamma-ray and passive neutron detection systems, isotopic neutron source-based active interrogation systems, pulsed portable neutron generator active interrogation systems, electron accelerator based techniques and laser spectroscopy techniques. The mix of techniques ranges in development maturity from the well established (MEGAS, Shuffler, Passive 4π neutron counters) through the proof-of-principle stage (pulsed neutron generator techniques) to the under investigation stage (electron linac and laser spectroscopy techniques). Matrix compensation methods are being developed to improve the accuracy of waste screening and assay measurements. Specific detection systems have been designed to operate in the high level beta-gamma backgrounds associated with some commercial reactor wastes. The techniques being developed can be used with either low level or high level beta-gamma wastes in either low density or high density matrices

Recent developments at Los Alamos for the measurement of alpha contaminated waste

Energy Technology Data Exchange (ETDEWEB)

Caldwell, J.T.; Cates, M.R.; Close, D.A.; Crane, T.W.; Kunz, W.E.; Shunk, E.R.; Umbarger, C.J.; Franks, L.A.

1980-01-01

A comprehensive program is currently in progress for the development of sensitive, practical nondestructive assay techniques for the quantification of low level transuranics in bulk solid wastes. This program encompasses a broad range of nuclear and nonnuclear techniques including sophisticated passive gamma-ray and passive neutron detection systems, isotopic neutron source-based active interrogation systems, pulsed portable neutron generator active interrogation systems, electron accelerator based techniques and laser spectroscopy techniques. The mix of techniques ranges in development maturity from the well established (MEGAS, Shuffler, Passive 4..pi.. neutron counters) through the proof-of-principle stage (pulsed neutron generator techniques) to the under investigation stage (electron linac and laser spectroscopy techniques). Matrix compensation methods are being developed to improve the accuracy of waste screening and assay measurements. Specific detection systems have been designed to operate in the high level beta-gamma backgrounds associated with some commercial reactor wastes. The techniques being developed can be used with either low level or high level beta-gamma wastes in either low density or high density matrices.

Hombre y muerte en el Islam: o de cómo la muerte de Sócrates fue objeto de considerácion en la civilización árabe-musulmana

Directory of Open Access Journals (Sweden)

Guerrero, Rafael Ramón

2007-01-01

Full Text Available A la muerte, que afecta a todo hombre, alude en numerosas ocasiones el Corán. Quizá por ello pronto se planteó en el mundo islámico la cuestión del suicidio y de la muerte voluntaria. Desde el siglo IX, este problema se convirtió en objeto de consideración, provocado por el impacto de la filosofía antigua: parece que la figura de Sócrates ejerció un cierto influjo a través de las versiones que de su muerte, aceptada voluntariamente, llegaron al mundo islámico y fue motivo de reflexión por parte de muchos pensadores

Thermal and enzymatic recovering of proteins from untanned leather waste.

Science.gov (United States)

Bajza, Z; Vrucek, V

2001-01-01

The laboratory trials of a process to treat untanned leather waste to isolate valuable protein products are presented. In this comparative study, both thermal and enzymatic treatments of leather waste were performed. The enzymatic method utilizes commercially available alkaline protease at moderate temperatures and for short periods of time. The concentration of the enzyme was 500 units per gram of leather waste which makes the method cost-effective. Amino acid composition in the hydrolysate obtained by the enzyme hydrolysis of untanned leather waste is determined. Chemical and physical properties of protein powder products from untanned leather waste were evaluated by spectrophotometric and chromatographic methods and by use of electron microscope. The results of microbiological assays confirm that these products agree to food safety standards. This relatively simple treatment of untanned leather waste may provide a practical and economical solution to the disposal of potentially dangerous waste.

Development of techniques for measuring plutonium contents in TRU wastes by NDA methods

International Nuclear Information System (INIS)

Matsubayashi, Toshiyuki; Kuwana, Katsumi; Morita, Tomio; Izuhara, Shigeomi; Suzuki, Masahiro

1983-01-01

In order to develop a technique for measuring the amount of plutonium in plutonium-contaminated (TRU) wastes, a passive gamma method was selected from many candidate methods, and examined for the suitability by applying the method to low density wastes. A segmented gamma scanner was used for the experiment. The instrument is composed mainly of a Ge(Li) detector, multichannel analyser, data processing system, turntable and transmission radiation source of (75)Se. A sham waste was prepared by adding plutonium oxide powder as a radiation source to waste matrix in a 20-1 carton box. The sham waste was put on the turntable, and the detector was set at 50 cm distance from the center of the turntable. 414 keV gamma ray emitted from (239)Pu was utilized for the assay of plutonium in the experiment. The effects of combustible (paper) waste matrix, organic chlorinated material matrix, and the distribution of plutonium source in a box on the count rate were examined, and it was concluded that 1) about 10 mg of (239)Pu contained in both matrices should be assayed by the passive gamma method, 2) 50 mg of (239) Pu was measured at 30 % confidence level with 2000 sec measuring time, 3) the effect of distribution of plutonium in a waste was able to be reduced to a value of less than 15 % by rotating the waste on the turntable. (Yoshitake, I.)

Performance test results of noninvasive characterization of Resource Conservation and Recovery Act surrogate waste by prompt gamma neutron activation analysis

Energy Technology Data Exchange (ETDEWEB)

Gehrke, R.J.; Streier, G.G.

1997-03-01

During FY-96, a performance test was carried out with funding from the Mixed Waste Focus Area (MWFA) of the Department of Energy (DOE) to determine the noninvasive elemental assay capabilities of commercial companies for Resource Conservation and Recovery Act (RCRA) metals present in 8-gal drums containing surrogate waste. Commercial companies were required to be experienced in the use of prompt gamma neutron activation analysis (PGNAA) techniques and to have a prototype assay system with which to conduct the test assays. Potential participants were identified through responses to a call for proposals advertised in the Commerce Business Daily and through personal contacts. Six companies were originally identified. Two of these six were willing and able to participate in the performance test, as described in the test plan, with some subsidizing from the DOE MWFA. The tests were conducted with surrogate sludge waste because (1) a large volume of this type of waste awaits final disposition and (2) sludge tends to be somewhat homogeneous. The surrogate concentrations of the above RCRA metals ranged from {approximately} 300 ppm to {approximately} 20,000 ppm. The lower limit was chosen as an estimate of the expected sensitivity of detection required by noninvasive, pretreatment elemental assay systems to be of value for operational and compliance purposes and to still be achievable with state-of-the-art methods of analysis. The upper limit of {approximately} 20,000 ppm was chosen because it is the opinion of the author that assay above this concentration level is within current state-of-the-art methods for most RCRA constituents. This report is organized into three parts: Part 1, Test Plan to Evaluate the Technical Status of Noninvasive Elemental Assay Techniques for Hazardous Waste; Part 2, Participants` Results; and Part 3, Evaluation of and Comments on Participants` Results.

Performance test results of noninvasive characterization of Resource Conservation and Recovery Act surrogate waste by prompt gamma neutron activation analysis

International Nuclear Information System (INIS)

Gehrke, R.J.; Streier, G.G.

1997-03-01

During FY-96, a performance test was carried out with funding from the Mixed Waste Focus Area (MWFA) of the Department of Energy (DOE) to determine the noninvasive elemental assay capabilities of commercial companies for Resource Conservation and Recovery Act (RCRA) metals present in 8-gal drums containing surrogate waste. Commercial companies were required to be experienced in the use of prompt gamma neutron activation analysis (PGNAA) techniques and to have a prototype assay system with which to conduct the test assays. Potential participants were identified through responses to a call for proposals advertised in the Commerce Business Daily and through personal contacts. Six companies were originally identified. Two of these six were willing and able to participate in the performance test, as described in the test plan, with some subsidizing from the DOE MWFA. The tests were conducted with surrogate sludge waste because (1) a large volume of this type of waste awaits final disposition and (2) sludge tends to be somewhat homogeneous. The surrogate concentrations of the above RCRA metals ranged from ∼ 300 ppm to ∼ 20,000 ppm. The lower limit was chosen as an estimate of the expected sensitivity of detection required by noninvasive, pretreatment elemental assay systems to be of value for operational and compliance purposes and to still be achievable with state-of-the-art methods of analysis. The upper limit of ∼ 20,000 ppm was chosen because it is the opinion of the author that assay above this concentration level is within current state-of-the-art methods for most RCRA constituents. This report is organized into three parts: Part 1, Test Plan to Evaluate the Technical Status of Noninvasive Elemental Assay Techniques for Hazardous Waste; Part 2, Participants' Results; and Part 3, Evaluation of and Comments on Participants' Results

Neutron Assay System for Con?nement Vessel Disposition

International Nuclear Information System (INIS)

Frame, Katherine C.; Bourne, Mark M.; Crooks, William J.; Evans, Louise; Mayo, Douglas R.; Miko, David K.; Salazar, William R.; Stange, Sy; Valdez, Jose I.; Vigil, Georgiana M.

2012-01-01

Waste will be removed from confinement vessels remaining from 1970s-era experiments. Los Alamos has 9+ spherical confinement vessels remaining from experiments. Each vessel contains ∼ 500 lbs of radioactive debris such as actinide metals and oxides, metals, powdered silica, graphite, and wires and hardware. In order to dispose of the vessels, debris and contamination must be removed. Neutron assay system was designed to assay vessels before and after cleanout. System requirements are: (1) Modular and moveable; (2) Capable of detecting ∼100g 239 Pu equivalent in a 2-inch thick steel sphere with 6 foot diameter; and (3) Capable of safeguards-quality assays. Initial design parameters arethe use of 4-atm 3 He tubes with length of 6 feet, and 3 He tubes embedded in polyethelene for moderation. This paper describes the calibration of the Confinement Vessel Assay System (CVAS) and quantification of its uncertainties. Assay uncertainty depends on five factors: (1) Statistical uncertainty in the assay measurement; (2) Statistical uncertainty in the background measurement; (3) Statistical uncertainty in the isotopics determination - This should be much smaller than the other uncertainties; (4) Systematic uncertainty due to position bias; and (5) Systematic uncertainty due to fluctuations in cosmic ray spallation. This one can be virtually eliminated by performing the background measurement with an empty vessel - but that may not be possible. We used modeling and experiments to quantify the systematic uncertainties. The calibration assumes a uniform distribution of material, but reality will be different. MCNPX modeling was used to quantify the positional bias. The model was benchmarked to build confidence in its results. Material at top of vessel is 44% greater than amount assayed, according to singles. Material near 19-tube detector is 38% less than amount assayed, according to singles. Cosmic ray spallation contributes significantly to the background. Comparing rates

Evaluation of low-level waste analysis using the MADAM system

Energy Technology Data Exchange (ETDEWEB)

Foster, L.A.; Wachter, J.R.; Hagan, R.C. [Los Alamos National Lab., NM (United States). Nuclear Materials Measurement and Accountability

1994-08-01

Previously, the important hardware features and capabilities for the Multiple Assay Dual Analysis Measurement (MADAM) system were reported. MADAM is a combined low-level and transuranic waste assay system. The system integrated commercially available Segmented Gamma Scanner (SGS) capability together with multienergy X-ray and gamma-ray analysis to measure these two waste forms. In addition, the system incorporated a small neutron slab detector to satisfy safeguards concerns and high resolution gamma-ray isotopics analysis proficiency. Since delivery of the system to this facility, an evaluation of its low-level waste measurement performance has been conducted using a set of specially constructed NIST-traceable standards. The evaluation studied existing analysis algorithms, matrix and attenuation effects, source position as a function of detector response, instrument stability, and sensitivity. Based on these studies, several modifications to the existing analysis algorithms have been performed, new correction factors for matrix attenuation have been devised, and measurement error estimates have been calculated and incorporated into the software. This report discusses the results of the evaluation program and the software modifications that have been developed.

Evaluation of low-level waste analysis using the MADAM system

International Nuclear Information System (INIS)

Foster, L.A.; Wachter, J.R.; Hagan, R.C.

1994-01-01

Previously, the important hardware features and capabilities for the Multiple Assay Dual Analysis Measurement (MADAM) system were reported. MADAM is a combined low-level and transuranic waste assay system. The system integrated commercially available Segmented Gamma Scanner (SGS) capability together with multienergy X-ray and gamma-ray analysis to measure these two waste forms. In addition, the system incorporated a small neutron slab detector to satisfy safeguards concerns and high resolution gamma-ray isotopics analysis proficiency. Since delivery of the system to this facility, an evaluation of its low-level waste measurement performance has been conducted using a set of specially constructed NIST-traceable standards. The evaluation studied existing analysis algorithms, matrix and attenuation effects, source position as a function of detector response, instrument stability, and sensitivity. Based on these studies, several modifications to the existing analysis algorithms have been performed, new correction factors for matrix attenuation have been devised, and measurement error estimates have been calculated and incorporated into the software. This report discusses the results of the evaluation program and the software modifications that have been developed

US enrichment safeguards program development activities with potential International Atomic Energy Agency safeguards applications. Part 1. Executive summaries

International Nuclear Information System (INIS)

Swindle, D.W. Jr.

1984-07-01

The most recent progress, results, and plans for future work on the US Enrichment Safeguards Program's principal development activities are summarized. Nineteen development activities are reported that have potential International Atomic Energy Agency (IAEA) safeguards applications. Part 1 presents Executive Summaries for these, each of which includes information on (1) the purpose and scope of the development activity; (2) the potential IAEA safeguards application and/or use if adopted; (3) significant development work, results, and/or conclusions to date; and where appropriate (4) future activities and plans for continued work. Development activities cover: measurement technology for limited-frequency-unannounced-access stategy inspections; integrated data acquisition system; enrichment-monitoring system; load-cell-based weighing system for UF 6 cylinder mass verifications; vapor phase versus liquid phase sampling of UF 6 cylinders; tamper-safing hardware and systems; an alternative approach to IAEA nuclear material balance verifications resulting from intermittent inspections; UF 6 sample bottle enrichment analyzer; crated waste assay monitor; and compact 252 Cf shuffler for UF 6 measurements

Molten salt processing of mixed wastes with offgas condensation

International Nuclear Information System (INIS)

Cooper, J.F.; Brummond, W.; Celeste, J.; Farmer, J.; Hoenig, C.; Krikorian, O.H.; Upadhye, R.; Gay, R.L.; Stewart, A.; Yosim, S.

1991-01-01

We are developing an advanced process for treatment of mixed wastes in molten salt media at temperatures of 700--1000 degrees C. Waste destruction has been demonstrated in a single stage oxidation process, with destruction efficiencies above 99.9999% for many waste categories. The molten salt provides a heat transfer medium, prevents thermal surges, and functions as an in situ scrubber to transform the acid-gas forming components of the waste into neutral salts and immobilizes potentially fugitive materials by a combination of particle wetting, encapsulation and chemical dissolution and solvation. Because the offgas is collected and assayed before release, and wastes containing toxic and radioactive materials are treated while immobilized in a condensed phase, the process avoids the problems sometimes associated with incineration processes. We are studying a potentially improved modification of this process, which treats oxidizable wastes in two stages: pyrolysis followed by catalyzed molten salt oxidation of the pyrolysis gases at ca. 700 degrees C. 15 refs., 5 figs., 1 tab

Standard test method for nondestructive assay of special nuclear material in low density scrap and waste by segmented passive gamma-Ray scanning

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 This test method covers the transmission-corrected nondestructive assay (NDA) of gamma-ray emitting special nuclear materials (SNMs), most commonly 235U, 239Pu, and 241Am, in low-density scrap or waste, packaged in cylindrical containers. The method can also be applied to NDA of other gamma-emitting nuclides including fission products. High-resolution gamma-ray spectroscopy is used to detect and measure the nuclides of interest and to measure and correct for gamma-ray attenuation in a series of horizontal segments (collimated gamma detector views) of the container. Corrections are also made for counting losses occasioned by signal processing limitations (1-3). 1.2 There are currently several systems in use or under development for determining the attenuation corrections for NDA of radioisotopic materials (4-8). A related technique, tomographic gamma-ray scanning (TGS), is not included in this test method (9, 10, 11). 1.2.1 This test method will cover two implementations of the Segmented Gamma Scanning ...

Quantitative radiological characterization of waste. Integration of gamma spectrometry and passive/active neutron assay

Energy Technology Data Exchange (ETDEWEB)

Simone, Gianluca; Mauro, Egidio; Gagliardi, Filippo; Gorello, Edoardo [Nucleco S.p.A., Rome (Italy)

2016-06-15

The radiological characterization of drums through Non-Destructive Assay (NDA) techniques commonly relies on gamma spectrometry. This paper introduces the procedure developed in Nucleco for the NDA radiological characterization of drums when the presence of Special Nuclear Material (SNM) is expected/observed. The procedure is based on the integration of a gamma spectrometry in SGS mode (Segmented Gamma Scanner) and a passive/active neutron assay. The application of this procedure is discussed on a real case of drums. The extension of the integration procedure to other gamma spectrometry systems is also discussed.

Bulk monitoring and segregation of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Beddow, H.; Adsley, I.; Pearman, I.; Sweeney, A.; Davies, M., E-mail: helen.beddow@nuvia.co.uk [Nuvia Limited, Harwell Oxford, Didcot, Oxfordshire (United Kingdom)

2014-07-01

Several sites in the UK are contaminated by radioactive legacy wastes. These include; radium luminising sites and more recently the oil, and (potentially) fracking industries; sites contaminated from thorium gas mantle factories; old nuclear research sites; nuclear power sites, and the Sellafield reprocessing site. Nuvia has developed a suite of technologies to map the location of and to recover and process wastes during remedial operations. The main method for delineating contaminated areas in-situ is by use of the Groundhog system, whilst bulk monitoring methods employ the Gamma Excavation Monitor, the High Resolution Assay Monitor, and the Conveyor Active Particle System. (author)

Bulk monitoring and segregation of radioactive wastes

International Nuclear Information System (INIS)

Beddow, H.; Adsley, I.; Pearman, I.; Sweeney, A.; Davies, M.

2014-01-01

Several sites in the UK are contaminated by radioactive legacy wastes. These include; radium luminising sites and more recently the oil, and (potentially) fracking industries; sites contaminated from thorium gas mantle factories; old nuclear research sites; nuclear power sites, and the Sellafield reprocessing site. Nuvia has developed a suite of technologies to map the location of and to recover and process wastes during remedial operations. The main method for delineating contaminated areas in-situ is by use of the Groundhog system, whilst bulk monitoring methods employ the Gamma Excavation Monitor, the High Resolution Assay Monitor, and the Conveyor Active Particle System. (author)

The comparison of fossil carbon fraction and greenhouse gas emissions through an analysis of exhaust gases from urban solid waste incineration facilities.

Science.gov (United States)

Kim, Seungjin; Kang, Seongmin; Lee, Jeongwoo; Lee, Seehyung; Kim, Ki-Hyun; Jeon, Eui-Chan

2016-10-01

In this study, in order to understand accurate calculation of greenhouse gas emissions of urban solid waste incineration facilities, which are major waste incineration facilities, and problems likely to occur at this time, emissions were calculated by classifying calculation methods into 3 types. For the comparison of calculation methods, the waste characteristics ratio, dry substance content by waste characteristics, carbon content in dry substance, and (12)C content were analyzed; and in particular, CO2 concentration in incineration gases and (12)C content were analyzed together. In this study, 3 types of calculation methods were made through the assay value, and by using each calculation method, emissions of urban solid waste incineration facilities were calculated then compared. As a result of comparison, with Calculation Method A, which used the default value as presented in the IPCC guidelines, greenhouse gas emissions were calculated for the urban solid waste incineration facilities A and B at 244.43 ton CO2/day and 322.09 ton CO2/day, respectively. Hence, it showed a lot of difference from Calculation Methods B and C, which used the assay value of this study. It is determined that this was because the default value as presented in IPCC, as the world average value, could not reflect the characteristics of urban solid waste incineration facilities. Calculation Method B indicated 163.31 ton CO2/day and 230.34 ton CO2/day respectively for the urban solid waste incineration facilities A and B; also, Calculation Method C indicated 151.79 ton CO2/day and 218.99 ton CO2/day, respectively. This study intends to compare greenhouse gas emissions calculated using (12)C content default value provided by the IPCC (Intergovernmental Panel on Climate Change) with greenhouse gas emissions calculated using (12)C content and waste assay value that can reflect the characteristics of the target urban solid waste incineration facilities. Also, the concentration and (12)C content

Methods of Reducing Bias in Combined Thermal/Epithermal Neutron (CTEN) Assays of Heterogeneous Waste

Energy Technology Data Exchange (ETDEWEB)

Estep, R.J.; Melton, S.; Miko, D.

1998-11-17

We examined the effectiveness of two different methods for correcting CTEN passive and active assays for bias due to variations in the source position in different drum types. Both use the same drum-averaged correction determined from a neural network trained to active flux monitor ratios as a starting point. One method then uses a neural network to obtain a spatial correction factor sensitive to the source location. The other method uses emission tomography. Both methods were found to give significantly improved assay accuracy over the drum-averaged correction, although more study is needed to determine which method works better.

Methods of Reducing Bias in Combined Thermal/Epithermal Neutron (CTEN) Assays of Heterogeneous Waste

International Nuclear Information System (INIS)

Estep, R.J.; Melton, S.; Miko, D.

1998-01-01

We examined the effectiveness of two different methods for correcting CTEN passive and active assays for bias due to variations in the source position in different drum types. Both use the same drum-averaged correction determined from a neural network trained to active flux monitor ratios as a starting point. One method then uses a neural network to obtain a spatial correction factor sensitive to the source location. The other method uses emission tomography. Both methods were found to give significantly improved assay accuracy over the drum-averaged correction, although more study is needed to determine which method works better

An improved enzyme-linked immunosorbent assay for whole-cell determination of methanogens in samples from anaerobic reactors

DEFF Research Database (Denmark)

Sørensen, A.H.; Ahring, B.K.

1997-01-01

An enzyme-linked immunosorbent assay was developed for the detection of whole cells of methanogens in samples from anaerobic continuously stirred tank digesters treating slurries of solid waste. The assay was found to allow for quantitative analysis of the most important groups of methanogens......-quality microtiter plates and the addition of dilute hydrochloric acid to the samples. In an experiment on different digester samples, the test demonstrated a unique pattern of different methanogenic strains present in each sample. The limited preparatory work required for the assay and the simple assay design make...... in samples from anaerobic digesters in a reproducible manner. Polyclonal antisera against eight strains of methanogens were employed in the test, The specificities of the antisera were increased by adsorption with cross-reacting cells. The reproducibility of the assay depended on the use of high...

Matrix effects corrections in DDT assay of {sup 239}Pu with the CTEN instrument

Energy Technology Data Exchange (ETDEWEB)

Hollas, C.L.; Arnone, G.; Brunson, G.; Coop, K. [Los Alamos National Lab., NM (United States)

1997-11-01

The accuracy of transuranic (TRU) waste assay using the differential die-away technique depends upon significant corrections to compensate for the effects of the matrix material in which the TRU waste is located. We have used a new instrument, the combined thermal/epithermal neutron (CTEN) instrument for the assay of TRU waste, to develop methods to improve the accuracy of these corrections. Neutrons from a pulsed 14-MeV neutron generator are moderated in the walls of the CTEN cavity and induce fission in the TRU material. The prompt neutrons from these fission events are detected in cadmium-wrapped {sup 3}He neutron detectors. We have developed methods of data acquisition and analysis to extract correlation in the neutron signals resulting from fission during active interrogation. This correlation information, in conjunction with the total number of neutrons detected, is used to determine the fraction of fission neutrons transmitted through the matrix material into the {sup 3}He detectors. This determination allows us to cleanly separate the matrix effects into two processes: matrix modification upon the neutron interrogating flux and matrix modification upon the fraction of fission neutrons transmitted to the neutron detectors. Recent results indicate that for some matrix systems, corrections for position dependent effects within the matrix are possible. 7 refs., 7 figs., 1 tab.

Safety evaluation for packaging (onsite) for concrete-shielded RHTRU waste drum for the 327 postirradiation testing laboratory

Energy Technology Data Exchange (ETDEWEB)

Adkins, H.E.

1996-10-29

This safety evaluation for packaging authorizes onsite transport of Type B quantities of radioactive material in the Concrete- Shielded Remote-Handled Transuranic Waste (RH TRU) Drum per WHC-CM-2-14, Hazardous Material Packaging and Shipping. The drum will be used for transport of 327 Building legacy waste from the 300 Area to the Transuranic Waste Storage and Assay Facility in the 200 West Area and on to a Solid Waste Storage Facility, also in the 200 Area.

Transuranic-waste program at EG and G Idaho, Inc. Annual technical report

International Nuclear Information System (INIS)

McKinley, K.B.

1982-11-01

This report summarizes the objectives and accomplishments of Transuranic (TRU) Waste Program conducted at EG and G Idaho, Inc., during FY 1982. The TRU Waste Program included: (1) Preparation of a revised draft of the Recommendation of a Long-Term Strategy (RLTS) document; (2) Preparation of environmental documentation, including a technical report, Environmental and Other Evaluations of Alternatives for Management of Defense Transuranic Waste at the Idaho National Engineering Laboratory, IDO-10103, as well as two environmental evaluations; (3) Preparation of a certification plan and procedures; (4) A nondestructive examination (NDE) project, which includes development of real-time radiography for waste certification, and container integrity equipment for waste container certification; (5) Development of an assay system; (6) Completion of a conceptual design for the Stored Waste Examination Pilot Plant (SWEPP) and SWEPP Support; and (7) Gas-generation analyses and tests. These TRU waste projects were funded at $1640K

Comprehensive evaluation of dioxins and dioxin-like compounds in surface soils and river sediments from e-waste-processing sites in a village in northern Vietnam: Heading towards the environmentally sound management of e-waste

OpenAIRE

Go Suzuki; Masayuki Someya; Hidenori Matsukami; Nguyen Minh Tue; Natsuyo Uchida; Le Huu Tuyen; Pham Hung Viet; Shin Takahashi; Shinsuke Tanabe; Abraham Brouwer; Hidetaka Takigami

2016-01-01

The management of electronic waste (e-waste), which can be a source of both useful materials and toxic substances, depending on the processing method, is important for promoting material cycling. In this study, we used the dioxin-responsive chemical-activated luciferase gene expression (DR-CALUX) assay combined with gas chromatography–high-resolution mass spectrometry to evaluate the levels of dioxin-like compounds in surface soils and river sediments collected in and around an e-waste-proces...

Design of an integrated non-destructive plutonium assay facility

International Nuclear Information System (INIS)

Moore, C.B.

1984-01-01

The Department of Energy requires improved technology for nuclear materials accounting as an essential part of new plutonium processing facilities. New facilities are being constructed at the Savannah River Plant by the Du Pont Company, Operating Contractor, to recover plutonium from scrap and waste material generated at SRP and other DOE contract processing facilities. This paper covers design concepts and planning required to incorporate state-of-the-art plutonium assay instruments developed at several national laboratories into an integrated, at-line nuclear material accounting facility operating in the production area. 3 figures

Classification of solid industrial waste based on ecotoxicology tests using Daphnia magna: an alternative

Directory of Open Access Journals (Sweden)

William Gerson Matias

2005-11-01

Full Text Available The adequate treatment and final disposal of solid industrial wastes depends on their classification into class I or II. This classification is proposed by NBR 10.004; however, it is complex and time-consuming. With a view to facilitating this classification, the use of assays with Daphnia magna is proposed. These assays make possible the identification of toxic chemicals in the leach, which denotes the presence of one of the characteristics described by NBR 10.004, the toxicity, which is a sufficient argument to put the waste into class I. Ecotoxicological tests were carried out with ten samples of solid wastes of frequent production and, on the basis of the results from EC(I50/48h of those samples in comparison with the official classification of NBR 10.004, limits were established for the classification of wastes into class I or II. A coincidence in the classification of 50% of the analyzed samples was observed. In cases in which there is no coherence between the methods, the method proposed in this work classifies the waste into class I. These data are preliminary, but they reveal that the classification system proposed here is promising because of its quickness and economic viability.

High-sensitivity measurements for low-level TRU wastes using advanced passive neutron techniques

International Nuclear Information System (INIS)

Menlove, H.O.; Eccleston, G.W.

1992-01-01

In recent years, both passive- and active-neutron nondestructive assay (NDA) systems have been used to measure the uranium and plutonium content in 200-ell drums. Because of the heterogeneity of the wastes, representative sampling is not possible and NDA methods are preferred over destructive analysis. Active-neutron assay systems are used to measure the fissile isotopes such as 235 U, 23 Pu, and 241 Pu; the isotopic ratios are used to infer the total plutonium content and thus the specific disintegration rate. The active systems include 14-MeV-neutron (DT) generators with delayed-neutron counting, (D,T) generators with the differential die-away technique, and 252 Cf delayed-neutron shufflers. Passive assay systems (for example, segmented gamma-ray scanners)5 have used gamma-ray sessions, while others (for example, passive drum counters) used passive-neutron signals. We have developed a new passive-neutron measurement technique to improve the accuracy and sensitivity of the NDA of plutonium scrap and waste. This new 200-ell-drum assay system combines the classical NDA method of counting passive-neutron totals and coincidences from plutonium with the new features of ''add-a-source'' (AS) and multiplicity counting to improve the accuracy of matrix corrections and statistical techniques that improve the low-level detectability limits. This paper describes the improvements we have made in passive-neutron assay systems and compares the accuracies and detectability limits of passive- and active-neutron assay systems

Project B-589, 300 Area transuranic waste interim storage project engineering study

International Nuclear Information System (INIS)

Greenhalgh, W.O.

1985-08-01

The purpose of the study was to look at various alternatives of taking newly generated, remote-handled transuranic waste (caisson waste) in the 300 Area, performing necessary transloading operations and preparing the waste for storage. The prepared waste would then be retrieved when the Waste Isolation Pilot Plant becomes operational and transshipped to the repository in New Mexico with a minimum of inspection and packaging. The scope of this study consisted of evaluating options for the transloading of the TRU wastes for shipment to a 200 Area storage site. Preconceptual design information furnished as part of the engineering study is listed below: produce a design for a clean, sealed waste canister; hot cell loadout system for the waste; in-cell loading or handling equipment; determine transshipment cask options; determine assay system requirements (optional); design or specify transport equipment required; provide a SARP cost estimate; determine operator training requirements; determine waste compaction equipment needs if desirable; develop a cost estimate and approximate schedule for a workable system option; and update the results presented in WHC Document TC-2025

Process Description for the Retrieval of Earth Covered Transuranic (TRU) Waste Containers at the Hanford Site

International Nuclear Information System (INIS)

DEROSA, D.C.

2000-01-01

This document describes process and operational options for retrieval of the contact-handled suspect transuranic waste drums currently stored below grade in earth-covered trenches at the Hanford Site. Retrieval processes and options discussed include excavation, container retrieval, venting, non-destructive assay, criticality avoidance, incidental waste handling, site preparation, equipment, and shipping

Process Description for the Retrieval of Earth Covered Transuranic (TRU) Waste Containers at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

DEROSA, D.C.

2000-01-13

This document describes process and operational options for retrieval of the contact-handled suspect transuranic waste drums currently stored below grade in earth-covered trenches at the Hanford Site. Retrieval processes and options discussed include excavation, container retrieval, venting, non-destructive assay, criticality avoidance, incidental waste handling, site preparation, equipment, and shipping.

Transuranic (TRU) Waste Phase I Retrieval Plan

International Nuclear Information System (INIS)

MCDONALD, K.M.

1999-01-01

From 1970 to 1987, TRU and suspect TRU wastes at Hanford were placed in the SWBG. At the time of placement in the SWBG these wastes were not regulated under existing Resource Conservation and Recovery Act (RCRA) regulations, since they were generated and disposed of prior to the effective date of RCRA at the Hanford Site (1987). From the standpoint of DOE Order 5820.2A', the TRU wastes are considered retrievably stored, and current plans are to retrieve these wastes for shipment to WIPP for disposal. This plan provides a strategy for the Phase I retrieval that meets the intent of TPA milestone M-91 and Project W-113, and incorporates the lessons learned during TRU retrieval campaigns at Hanford, LANL, and SRS. As in the original Project W-I13 plans, the current plan calls for examination of approximately 10,000 suspect-TRU drums located in the 218-W-4C burial ground followed by the retrieval of those drums verified to contain TRU waste. Unlike the older plan, however, this plan proposes an open-air retrieval scenario similar to those used for TRU drum retrieval at LANL and SRS. Phase I retrieval consists of the activities associated with the assessment of approximately 10,000 55-gallon drums of suspect TRU-waste in burial ground 218-W-4C and the retrieval of those drums verified to contain TRU waste. Four of the trenches in 218-W-4C (Trenches 1,4,20, and 29) are prime candidates for Phase I retrieval because they contain large numbers of suspect TRU drums, stacked from 2 to 5 drums high, on an asphalt pad. In fact, three of the trenches (Trenches 1,20, and 29) contain waste that has not been covered with soil, and about 1500 drums can be retrieved without excavation. The other three trenches in 218-W-4C (Trenches 7, 19, and 24) are not candidates for Phase I retrieval because they contain significant numbers of boxes. Drums will be retrieved from the four candidate trenches, checked for structural integrity, overpacked, if necessary, and assayed at the burial

Transuranic (TRU) Waste Phase I Retrieval Plan

International Nuclear Information System (INIS)

MCDONALD, K.M.

2000-01-01

From 1970 to 1987, TRU and suspect TRU wastes at Hanford were placed in the SWBG. At the time of placement in the SWBG these wastes were not regulated under existing Resource Conservation and Recovery Act (RCRA) regulations, since they were generated and disposed of prior to the effective date of RCRA at the Hanford Site (1987). From the standpoint of DOE Order 5820.2A1, the TRU wastes are considered retrievably stored, and current plans are to retrieve these wastes for shipment to WIPP for disposal. This plan provides a strategy for the Phase I retrieval that meets the intent of TPA milestone M-91 and Project W-113, and incorporates the lessons learned during TRU retrieval campaigns at Hanford, LANL, and SRS. As in the original Project W-113 plans, the current plan calls for examination of approximately 10,000 suspect-TRU drums located in the 218-W-4C burial ground followed by the retrieval of those drums verified to contain TRU waste. Unlike the older plan, however, this plan proposes an open-air retrieval scenario similar to those used for TRU drum retrieval at LANL and SRS. Phase I retrieval consists of the activities associated with the assessment of approximately 10,000 55-gallon drums of suspect TRU-waste in burial ground 218-W-4C and the retrieval of those drums verified to contain TRU waste. Four of the trenches in 218-W-4C (Trenches 1, 4, 20, and 29) are prime candidates for Phase I retrieval because they contain large numbers of suspect TRU drums, stacked from 2 to 5 drums high, on an asphalt pad. In fact, three of the trenches (Trenches 1 , 20, and 29) contain waste that has not been covered with soil, and about 1500 drums can be retrieved without excavation. The other three trenches in 218-W-4C (Trenches 7, 19, and 24) are not candidates for Phase I retrieval because they contain significant numbers of boxes. Drums will be retrieved from the four candidate trenches, checked for structural integrity, overpacked, if necessary, and assayed at the burial

Antioxidative properties of some phototropic microalgae grown in waste water

DEFF Research Database (Denmark)

Safafar, Hamed; Jacobsen, Charlotte; Møller, Peter

for the screening and selection of the species. In this study,the potential antioxidant activities of 12 micro algal sample from Chlorella., Spirulina., Euglena, Scenedesmus and Haematococcus species grown in waste water in Kalundborg micro algal facilities were evaluated using three antioxidant assays, including...

Application for approval to construct the Waste Receiving And Processing facility

International Nuclear Information System (INIS)

1993-02-01

The following Application For Approval Of Construction is being submitted by the US Department of Energy, Richland Field Office pursuant to 40 CFR 61.07, ''Application for Approval of Construction or Modification,'' for the Waste Receiving and Processing (WRAP) Module 1 facility (also referred to as WRAP 1). The WRAP 1 facility will be a new source of radioactive emissions to the atmosphere. The WRAP 1 facility will be housed in the new 2336-W Building, which will be located in the 200 West Area south of 23rd Street and west of Dayton Avenue. The 200 West Area is located within the boundary of the Hanford Site. The mission of the WRAP 1 facility is to examine, assay, characterize, treat, and repackage solid radioactive and mixed waste to enable permanent disposal of the waste in accordance with all applicable regulations. The solid wastes to be handled in the WRAP 1 facility include low-level waste (LLW), Transuranic (TRU) waste, TRU mixed waste, and low-level mixed waste (LLMW). The WRAP 1 facility will only accept contact handled (CH) waste containers. CH waste is a waste category whose external surface dose rate does not exceed 200 mrem/h. These containers have a surface dose rate of less than 200 mrem/h

Ante-mortem detection of chronic wasting disease in recto-anal mucosa-associated lymphoid tissues from elk (Cervus elaphus nelsoni) using real-time quaking-induced conversion (RT-QuIC) assay: A blinded collaborative study.

Science.gov (United States)

Manne, Sireesha; Kondru, Naveen; Nichols, Tracy; Lehmkuhl, Aaron; Thomsen, Bruce; Main, Rodger; Halbur, Patrick; Dutta, Somak; Kanthasamy, Anumantha G

2017-11-02

Prion diseases are transmissible spongiform encephalopathies (TSEs) characterized by fatal, progressive neurologic diseases with prolonged incubation periods and an accumulation of infectious misfolded prion proteins. Antemortem diagnosis is often difficult due to a long asymptomatic incubation period, differences in the pathogenesis of different prions, and the presence of very low levels of infectious prion in easily accessible samples. Chronic wasting disease (CWD) is a TSE affecting both wild and captive populations of cervids, including mule deer, white-tailed deer, elk, moose, muntjac, and most recently, wild reindeer. This study represents a well-controlled evaluation of a newly developed real-time quaking-induced conversion (RT-QuIC) assay as a potential CWD diagnostic screening test using rectal biopsy sections from a depopulated elk herd. We evaluated 69 blinded samples of recto-anal mucosa-associated lymphoid tissue (RAMALT) obtained from USDA Veterinary Services. The results were later un-blinded and statistically compared to immunohistochemical (IHC) results from the USDA National Veterinary Services Laboratories (NVSL) for RAMALT, obex, and medial retropharyngeal lymph node (MRPLN). Comparison of RAMALT RT-QuIC assay results with the IHC results of RAMALT revealed 92% relative sensitivity (95% confidence limits: 61.52-99.8%) and 95% relative specificity (95% confidence limits: 85.13-99%). Collectively, our results show a potential utility of the RT-QuIC assay to advance the development of a rapid, sensitive, and specific prion diagnostic assay for CWD prions.

WRAP Module 1 sampling strategy and waste characterization alternatives study

Energy Technology Data Exchange (ETDEWEB)

Bergeson, C.L.

1994-09-30

The Waste Receiving and Processing Module 1 Facility is designed to examine, process, certify, and ship drums and boxes of solid wastes that have a surface dose equivalent of less than 200 mrem/h. These wastes will include low-level and transuranic wastes that are retrievably stored in the 200 Area burial grounds and facilities in addition to newly generated wastes. Certification of retrievably stored wastes processing in WRAP 1 is required to meet the waste acceptance criteria for onsite treatment and disposal of low-level waste and mixed low-level waste and the Waste Isolation Pilot Plant Waste Acceptance Criteria for the disposal of TRU waste. In addition, these wastes will need to be certified for packaging in TRUPACT-II shipping containers. Characterization of the retrievably stored waste is needed to support the certification process. Characterization data will be obtained from historical records, process knowledge, nondestructive examination nondestructive assay, visual inspection of the waste, head-gas sampling, and analysis of samples taken from the waste containers. Sample characterization refers to the method or methods that are used to test waste samples for specific analytes. The focus of this study is the sample characterization needed to accurately identify the hazardous and radioactive constituents present in the retrieved wastes that will be processed in WRAP 1. In addition, some sampling and characterization will be required to support NDA calculations and to provide an over-check for the characterization of newly generated wastes. This study results in the baseline definition of WRAP 1 sampling and analysis requirements and identifies alternative methods to meet these requirements in an efficient and economical manner.

WRAP Module 1 sampling strategy and waste characterization alternatives study

International Nuclear Information System (INIS)

Bergeson, C.L.

1994-01-01

The Waste Receiving and Processing Module 1 Facility is designed to examine, process, certify, and ship drums and boxes of solid wastes that have a surface dose equivalent of less than 200 mrem/h. These wastes will include low-level and transuranic wastes that are retrievably stored in the 200 Area burial grounds and facilities in addition to newly generated wastes. Certification of retrievably stored wastes processing in WRAP 1 is required to meet the waste acceptance criteria for onsite treatment and disposal of low-level waste and mixed low-level waste and the Waste Isolation Pilot Plant Waste Acceptance Criteria for the disposal of TRU waste. In addition, these wastes will need to be certified for packaging in TRUPACT-II shipping containers. Characterization of the retrievably stored waste is needed to support the certification process. Characterization data will be obtained from historical records, process knowledge, nondestructive examination nondestructive assay, visual inspection of the waste, head-gas sampling, and analysis of samples taken from the waste containers. Sample characterization refers to the method or methods that are used to test waste samples for specific analytes. The focus of this study is the sample characterization needed to accurately identify the hazardous and radioactive constituents present in the retrieved wastes that will be processed in WRAP 1. In addition, some sampling and characterization will be required to support NDA calculations and to provide an over-check for the characterization of newly generated wastes. This study results in the baseline definition of WRAP 1 sampling and analysis requirements and identifies alternative methods to meet these requirements in an efficient and economical manner

Inter-laboratory and inter-assay comparison on two real-time PCR techniques for quantification of PCV2 nucleic acid extracted from field samples

DEFF Research Database (Denmark)

Hjulsager, Charlotte Kristiane; Grau-Roma, L.; Sibila, M.

2009-01-01

Several real-time PCR assays for quantification of PCV2 DNA (qPCR) have been described in the literature. and different in-house assays are being used by laboratories around the world. A general threshold of it copies of PCV2 per millilitre serum for postweaning multisystemic wasting syndrome (PMWS......) diagnosis has been suggested. However, neither inter-laboratory nor inter-assay comparisons have been published so far. In the present study two different qPCR probe assays Used routinely in two laboratories were compared on DNA extracted From serum, nasal and rectal swabs. Results showed a significant...

Development of a solid-phase assay for measurement of proteolytic enzyme activity

International Nuclear Information System (INIS)

Varani, J.; Johnson, K.; Kaplan, J.

1980-01-01

A solid-phase, plate assay was developed for the measurement of proteolytic enzyme activity. In this assay procedure, radiolabeled substrates were dried onto the surface of microtiter wells. Following drying, the wells were washed two times with saline to remove the nonadherent substrate. When proteolytic enzymes were added to the wells, protein hydrolysis occurred, releasing radioactivity into the supernatant fluid. The amount of protein hydrolysis that occurred was reflected by the amount of radioactivity in the supernatant fluid. When 125 I-hemoglobin was used as the substrate, it was as susceptible to hydrolysis by trypsin in the solid-phase assay as it was in solution in a standard assay procedure. Protease activity from a variety of sources (including from viable cells as well as from extracellular sources) were also able to hydrolyze the hemoglobin on the plate. 125 I-Labeled serum albumen, fibrinogen, and rat pulmonary basement membrane were also susceptible to hydrolysis by trypsin in the solid phase. When [ 14 C]elastin was dried onto the plate, it behaved in a similar manner to elastin in solution. It was resistant to hydrolysis by nonspecific proteases such as trypsin and chymotrypsin but was highly susceptible to hydrolysis by elastase. The solid-phase plate assay has several features which recommended it for routine use. It is as sensitive as standard tube assays (and much more sensitive than routinely used colormetric assays). It is quick and convenient; there are no precipitation, centrifugation, or filtration steps. In addition, very small volumes of radioactive wastes are generated. Another advantage of the solid-phase plate assay is the resistance of the dried substrates to spontaneous breakdown and to microbial contamination. Finally, this assay is suitable for use with viable cells as well as for extracellular proteases

Research on the assessment technology of the radionuclide inventory for the radioactive waste disposal(I)

Energy Technology Data Exchange (ETDEWEB)

Lee, K. J.; Hong, D. S.; Hwang, G. H.; Shin, J. J.; Yuk, D. S. [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

2002-03-15

Characteristics and states of management of low and intermediate level radioactive waste in site : state of management for each type of wastes, characteristics of low and intermediate level solid radioactive waste, stage of management of low and intermediate level solid radioactive waste. Survey of state of management and characteristics of low and intermediate level radioactive waste disposal facility in foreign countries : state of management of disposal facilities, classification criteria and target radionuclides for assessment in foreign disposal facilities. Survey of the assessment methods of the radionuclides inventory and establishing the direction of requirement : assessment methods of the radionuclides inventory, analysis of radionuclides assay system in KORI site, establishment the direction of requirement in the assessment methods.

Development of an integrated assay facility

International Nuclear Information System (INIS)

Molesworth, T.V.; Bailey, M.; Findlay, D.J.S.; Sene, M.R.; Swinhoe, M.T.

1990-01-01

Initial results of active neutron and active gamma-ray interrogation of a 500 liter cemented simulated CAGR intermediate level radioactive waste drum are described. The basis of the interrogation systems was the Harwell electron linear accelerator HELIOS, which was used to produce the interrogating neutrons and gamma-rays. Several sets of neutron detectors were located around the drum to count signature neutrons. The responses of the system were measured by placing known samples at many different locations within the drum. In general, measured responses confirmed calculated responses. Good agreement was obtained for the azimuthal angle dependences. The absolute responses agreed well for gamma-ray interrogation, but the calculations were apparently over-estimates for neutron interrogation. Those aspects requiring consideration in the practical application of assay techniques are identified. 8 refs., 6 figs

Standard test method for nondestructive assay of radioactive material by tomographic gamma scanning

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 This test method describes the nondestructive assay (NDA) of gamma ray emitting radionuclides inside containers using tomographic gamma scanning (TGS). High resolution gamma ray spectroscopy is used to detect and quantify the radionuclides of interest. The attenuation of an external gamma ray transmission source is used to correct the measurement of the emission gamma rays from radionuclides to arrive at a quantitative determination of the radionuclides present in the item. 1.2 The TGS technique covered by the test method may be used to assay scrap or waste material in cans or drums in the 1 to 500 litre volume range. Other items may be assayed as well. 1.3 The test method will cover two implementations of the TGS procedure: (1) Isotope Specific Calibration that uses standards of known radionuclide masses (or activities) to determine system response in a mass (or activity) versus corrected count rate calibration, that applies to only those specific radionuclides for which it is calibrated, and (2) Respo...

"From safe source to safe sink" development of colorimetric assay for gabapentin in bulk drug and capsules using naturally derived genipin.

Science.gov (United States)

Winotapun, Weerapath; Kongpakwattana, Khachen; Dejpittayanunt, Sirirat; Pathomcharoensukchai, Suwaparp; Suksaran, Udomluck; Nuntharatanapong, Nopparat; Rojanarata, Theerasak

2012-09-15

A novel colorimetric assay for gabapentin in bulk drug and capsules has been developed via a safety-and-sustainability concerning concept. The method relied on the reaction of primary amino group of drug with non-toxic and eco-friendly genipin in totally aqueous medium to form the blue product which was subsequently measured by visible spectrophotometry at 590 nm. Under the optimized conditions, Beer's law was obeyed in the concentration range of 0.15-0.50 mM (r(2)=0.9998). It was accurate, precise and insensitive to the interferences from all related compounds specified in the United States Pharmacopeia as well as commonly used excipients. Furthermore, it gave the assay results in agreement with the pharmacopeial chromatographic method. Owing to the environmental concern and responsibility, a fast and facile method was also proposed for the treatment of waste generated from the assay based on the decoloration by using gypsum as a cheap and commonly available adsorbent. After the treatment, more than 95% of the initial blue product was removed from the waste solution and the treated waste was proven to be safe for aquatic organisms, as studied in brine shrimp and guppy fishes. Therefore, this work not only reports for the first time the application of naturally derived genipin to drug analysis, but also presents a new and contemporary paradigm that illustrates the fully benign-by-design development of the analytical methodologies in the era of Green Chemistry, starting from the safe source of reagents toward the safe sink when waste is released into the environment. Copyright © 2012 Elsevier B.V. All rights reserved.

Evaluating the toxicity of food processing wastes as co-digestion substrates with dairy manure.

Science.gov (United States)

Lisboa, Maria Sol; Lansing, Stephanie

2014-07-01

Studies have shown that including food waste as a co-digestion substrate in the anaerobic digestion of livestock manure can increase energy production. However, the type and inclusion rate of food waste used for co-digestion need to be carefully considered in order to prevent adverse conditions in the digestion environment. This study determined the effect of increasing the concentration (2%, 5%, 15% and 30%, by volume) of four food-processing wastes (meatball, chicken, cranberry and ice cream processing wastes) on methane production. Anaerobic toxicity assay (ATA) and specific methanogenic activity (SMA) tests were conducted to determine the concentration at which each food waste became toxic to the digestion environment. Decreases in methane production were observed at concentrations above 5% for all four food waste substrates, with up to 99% decreases in methane production at 30% food processing wastes (by volume). Copyright © 2014 Elsevier Ltd. All rights reserved.

Phenotypic and genotypic characterization of clinically relevant bacteria isolated from dental waste and waste workers' hands, mucosas and coats.

Science.gov (United States)

Tagliaferri, T L; Vieira, C D; de Carvalho, M A R; Ladeira, L C D; Magalhães, P P; de Macêdo Farias, L; Dos Santos, S G

2017-10-01

Infectious wastes are potential sources of pathogenic micro-organisms, which may represent a risk to the professionals who manage them. In this study, we aimed to characterize the infectious bacteria present in dental waste and waste workers. The dental waste produced over 24 h was collected and waste workers were sampled by swabbing. Isolate resistance profiles were characterized by Vitek ® and PCR and biofilm formation by Congo Red agar, string test and microtitre assay. To assess similarity between the waste and the workers' samples, a random amplified polymorphic DNA test was used. Twenty-eight bacteria were identified as clinically relevant. The most frequent gene was bla TEM present in five Gram-negative micro-organisms, and one bla SHV in Klebsiella pneumoniae. All Pseudomonas aeruginosa were positive to extracellular polymeric substances formation, except one isolated from a worker. Klebsiella pneumoniae had negative results for the string test. Pseudomonas aeruginosa showed better adherence at 25°C after 48 h of incubation and K. pneumonia had the best biofilm formation at the same temperature, after 24 h. The similarity between P. aeruginosa recovered from dental waste and from workers was low, however, it is important to note that a pathogen was found on a worker's hands and that improvements in biosafety are required. Infectious dental waste can contain clinically relevant bacteria with important resistance and biofilm profiles. These micro-organisms could be transmitted to waste workers, other professionals and patients if the principles of biosafety measures are neglected. To our knowledge, no study has ever evaluated the microbial characterization and the potential contamination risk of dental infectious waste and waste handlers. The presence of clinically relevant bacteria in the hands and nasal mucosa of waste workers highlights the need for studies in this field to clarify the risk of these pathogens in dental healthcare services, and to

Waste management, waste resource facilities and waste conversion processes

International Nuclear Information System (INIS)

Demirbas, Ayhan

2011-01-01

In this study, waste management concept, waste management system, biomass and bio-waste resources, waste classification, and waste management methods have been reviewed. Waste management is the collection, transport, processing, recycling or disposal, and monitoring of waste materials. A typical waste management system comprises collection, transportation, pre-treatment, processing, and final abatement of residues. The waste management system consists of the whole set of activities related to handling, treating, disposing or recycling the waste materials. General classification of wastes is difficult. Some of the most common sources of wastes are as follows: domestic wastes, commercial wastes, ashes, animal wastes, biomedical wastes, construction wastes, industrial solid wastes, sewer, biodegradable wastes, non-biodegradable wastes, and hazardous wastes.

A survey of monitoring and assay systems for release of metals from radiation controlled areas at LANL.

Energy Technology Data Exchange (ETDEWEB)

Gruetzmacher, K. M. (Kathleen M.); MacArthur, D. W. (Duncan W.)

2002-01-01

At Los Alamos National Laboratory (LANL), a recent effort in waste minimization has focused on scrap metal from radiological controlled areas (RCAs). In particular, scrap metal from RCAs needs to be dispositioned in a reasonable and cost effective manner. Recycling of DOE scrap metals from RCAs is currently under a self-imposed moratorium. Since recycling is not available and reuse is difficult, often metal waste from RCAs, which could otherwise be recycled, is disposed of as low-level waste. Estimates at LANL put the cost of low-level waste disposal at $550 to $4000 per cubic meter, depending on the type of waste and the disposal site. If the waste is mixed, the cost for treatment and disposal can be as high as $50,000 per cubic meter. Disposal of scrap metal as low-level waste uses up valuable space in the low-level waste disposal areas and requires transportation to the disposal site under Department of Transportation (DOT) regulations for low-level waste. In contrast, disposal as non-radioactive waste costs as little as $2 per cubic meter. While recycling is unavailable, disposing of the metal at an industrial waste site could be the best solution for this waste stream. A Green Is Clean (GIC) type verification program needs to be in place to provide the greatest assurance that the waste does not contain DOE added radioactivity. This paper is a review of available and emerging radiation monitoring and assay systems that could be used for scrap metal as part of the LANL GIC program.

Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in the Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization.

A combined approach to investigate the toxicity of an industrial landfill's leachate: Chemical analyses, risk assessment and in vitro assays

International Nuclear Information System (INIS)

Baderna, D.; Maggioni, S.; Boriani, E.; Gemma, S.; Molteni, M.; Lombardo, A.; Colombo, A.; Bordonali, S.; Rotella, G.; Lodi, M.; Benfenati, E.

2011-01-01

Solid wastes constitute an important and emerging problem. Landfills are still one of the most common ways to manage waste disposal. The risk assessment of pollutants from landfills is becoming a major environmental issue in Europe, due to the large number of sites and to the importance of groundwater protection. Furthermore, there is lack of knowledge for the environmental, ecotoxicological and toxicological characteristics of most contaminants contained into landfill leacheates. Understanding leachate composition and creating an integrated strategy for risk assessment are currently needed to correctly face the landfill issues and to make projections on the long-term impacts of a landfill, with particular attention to the estimation of possible adverse effects on human health and ecosystem. In the present study, we propose an integrated strategy to evaluate the toxicity of the leachate using chemical analyses, risk assessment guidelines and in vitro assays using the hepatoma HepG2 cells as a model. The approach was applied on a real case study: an industrial waste landfill in northern Italy for which data on the presence of leachate contaminants are available from the last 11 years. Results from our ecological risk models suggest important toxic effects on freshwater fish and small rodents, mainly due to ammonia and inorganic constituents. Our results from in vitro data show an inhibition of cell proliferation by leachate at low doses and cytotoxic effect at high doses after 48 h of exposure. - Research highlights: → We study the toxicity of leachate from a non-hazardous industrial waste landfill. → We perform chemical analyses, risk assessments and in vitro assays on HepG2 cells. → Risk models suggest toxic effects due to ammonia and inorganic constituents. → In vitro assays show that leachate inhibits cell proliferation at low doses. → Leachate can induce cytotoxic effects on HepG2 cells at high doses.

Lessons learned from a criticality safety case for historic PCM waste retrieval

International Nuclear Information System (INIS)

Kirkwood, David

2003-01-01

Plutonium Contaminated Material arises as a solid waste at the United Kingdom Sellafield Site. Its disposal route entails it being packaged into 200 litre mild steel drums which are currently placed in interim surface stores in large multi-layered arrays. Within one of the original Sellafield buildings, a large number of such drums accumulated in an area known as the South Solvent Cells during the late 1960s and early 1970s. They have remained there largely untouched until retrieval operations commenced in 2002. From the out-set, significant operational difficulties were encountered which led to a cessation of the retrieval operations after the processing of only twelve historic drums. These difficulties had their origins in the requirements of the criticality safety case and calibration of the plutonium assay instrumentation which supported the retrieval operations. This paper describes the remedial actions taken to address these difficulties which have allowed a successful resumption of waste retrieval operations and highlights learning points which have general applicability to any decommissioning or historic waste retrieval project that involves the fissile assay of plutonium (and 235 U) contaminated plant. (author)

Neutralization potential as an assay of alkalinity of environmental solids

International Nuclear Information System (INIS)

Grube, W.E.Jr.; Ammons, J.T.

1993-01-01

The method to determine neutralizing equivalence of agricultural limestone has been applied to quantify the amount of bases present in a broad diversity of mineral materials, solid reagents, and products involved in environmental processes. The capacity to neutralize native or imposed acidity must be known in many processes in order to preserve near-neutral material. The standard method for assaying agricultural limestones was adapted to quantify native alkalinity in calcareous rocks exposed by coal surface mining. Data from these analyses continue to provide the surface mining industry and regulating agencies with a measure of the extent to which acidic mine drainage may be neutralized by the natural components of surrounding rock strata and disturbed materials. This approach to determine base content has also been applied to commercially available industrial byproducts added to soils or wastes. Kiln dust, fly ash, sludge, and other additives have been evaluated routinely to measure their alkalinity contribution and also batch-to-batch uniformity. The application of this technique to monitor amounts of reagents added to neutralize acid waste materials by adding alkalis is discussed. Use of this procedure to evaluate different materials is documented with exemplary data. Results of analyses of a broad variety of rock and soil materials, amended soils, soil additives or amendments, industrial waste byproducts, sludge, and treated wastes are presented. Utility of the procedure for routine quality control in soil treatment, amendment uniformity, and product analysis is discussed

Influence of chemical composition of civil construction waste in the cement paste

International Nuclear Information System (INIS)

Cunha, G.A.; Andrade, A.C.D.; Souza, J.M.M.; Evangelista, A.C.J.; Almeida, V.C.

2009-01-01

The construction and demolition waste when disposed inappropriately might cause serious public health problems. Its reutilization focusing on the development of new products using simple production techniques, assuring a new product life cycle and not damaging the environment is inserted in sustainable concept. The aim of this work was identifying the characteristics of types of waste generated in a residential reform (glassy ceramic and fill dirt leftovers) verifying separately its influence on cement pastes mechanical behavior. Cement pastes + wastes were prepared in 25% and 50% proportions with an approximately 0,35 water/cement relation and, glue time determination, water absorption, resistance to compression and X-ray fluorescence assays were taken. The results indicate that the chemical composition of the waste causes changes in the behavior of cement pastes, reflecting on their resistance to compression. (author)

Fusion of microlitre water-in-oil droplets for simple, fast and green chemical assays.

Science.gov (United States)

Chiu, S-H; Urban, P L

2015-08-07

A simple format for microscale chemical assays is proposed. It does not require the use of test tubes, microchips or microtiter plates. Microlitre-range (ca. 0.7-5.0 μL) aqueous droplets are generated by a commercial micropipette in a non-polar matrix inside a Petri dish. When two droplets are pipetted nearby, they spontaneously coalesce within seconds, priming a chemical reaction. Detection of the reaction product is accomplished by colorimetry, spectrophotometry, or fluorimetry using simple light-emitting diode (LED) arrays as the sources of monochromatic light, while chemiluminescence detection of the analytes present in single droplets is conducted in the dark. A smartphone camera is used as the detector. The limits of detection obtained for the developed in-droplet assays are estimated to be: 1.4 nmol (potassium permanganate by colorimetry), 1.4 pmol (fluorescein by fluorimetry), and 580 fmol (sodium hypochlorite by chemiluminescence detection). The format has successfully been used to monitor the progress of chemical and biochemical reactions over time with sub-second resolution. A semi-quantitative analysis of ascorbic acid using Tillman's reagent is presented. A few tens of individual droplets can be scanned in parallel. Rapid switching of the LED light sources with different wavelengths enables a spectral analysis of multiple droplets. Very little solid waste is produced. The assay matrix is readily recycled, thus the volume of liquid waste produced each time is also very small (typically, 1-10 μL per analysis). Various water-immiscible translucent liquids can be used as the reaction matrix: including silicone oil, 1-octanol as well as soybean cooking oil.

Design of an error-free nondestructive plutonium assay facility

International Nuclear Information System (INIS)

Moore, C.B.; Steward, W.E.

1987-01-01

An automated, at-line nondestructive assay (NDA) laboratory is installed in facilities recently constructed at the Savannah River Plant. The laboratory will enhance nuclear materials accounting in new plutonium scrap and waste recovery facilities. The advantages of at-line NDA operations will not be realized if results are clouded by errors in analytical procedures, sample identification, record keeping, or techniques for extracting samples from process streams. Minimization of such errors has been a primary design objective for the new facility. Concepts for achieving that objective include mechanizing the administrative tasks of scheduling activities in the laboratory, identifying samples, recording and storing assay data, and transmitting results information to process control and materials accounting functions. These concepts have been implemented in an analytical computer system that is programmed to avoid the obvious sources of error encountered in laboratory operations. The laboratory computer exchanges information with process control and materials accounting computers, transmitting results information and obtaining process data and accounting information as required to guide process operations and maintain current records of materials flow through the new facility

Reliability of plant root comet assay in comparison with human leukocyte comet assay for assessment environmental genotoxic agents.

Science.gov (United States)

Reis, Gabriela Barreto Dos; Andrade-Vieira, Larissa Fonseca; Moraes, Isabella de Campos; César, Pedro Henrique Souza; Marcussi, Silvana; Davide, Lisete Chamma

2017-08-01

Comet assay is an efficient test to detect genotoxic compounds based on observation of DNA damage. The aim of this work was to compare the results obtained from the comet assay in two different type of cells extracted from the root tips from Lactuca sativa L. and human blood. For this, Spent Pot Liner (SPL), and its components (aluminum and fluoride) were applied as toxic agents. SPL is a solid waste generated in industry from the aluminum mining and processing with known toxicity. Three concentrations of all tested solutions were applied and the damages observed were compared to negative and positive controls. It was observed an increase in the frequency of DNA damage for human leukocytes and plant cells, in all treatments. On human leukocytes, SPL induced the highest percentage of damage, with an average of 87.68%. For root tips cells of L. sativa the highest percentage of damage was detected for aluminum (93.89%). Considering the arbitrary units (AU), the average of nuclei with high levels of DNA fragmentation was significant for both cells type evaluated. The tested cells demonstrated equal effectiveness for detection of the genotoxicity induced by the SPL and its chemical components, aluminum and fluoride. Further, using a unique method, the comet assay, we proved that cells from root tips of Lactuca sativa represent a reliable model to detect DNA damage induced by genotoxic pollutants is in agreement of those observed in human leukocytes as model. So far, plant cells may be suggested as important system to assess the toxicological risk of environmental agents. Copyright © 2017 Elsevier Inc. All rights reserved.

Assaying Cellular Viability Using the Neutral Red Uptake Assay.

Science.gov (United States)

Ates, Gamze; Vanhaecke, Tamara; Rogiers, Vera; Rodrigues, Robim M

2017-01-01

The neutral red uptake assay is a cell viability assay that allows in vitro quantification of xenobiotic-induced cytotoxicity. The assay relies on the ability of living cells to incorporate and bind neutral red, a weak cationic dye, in lysosomes. As such, cytotoxicity is expressed as a concentration-dependent reduction of the uptake of neutral red after exposure to the xenobiotic under investigation. The neutral red uptake assay is mainly used for hazard assessment in in vitro toxicology applications. This method has also been introduced in regulatory recommendations as part of 3T3-NRU-phototoxicity-assay, which was regulatory accepted in all EU member states in 2000 and in the OECD member states in 2004 as a test guideline (TG 432). The present protocol describes the neutral red uptake assay using the human hepatoma cell line HepG2, which is often employed as an alternative in vitro model for human hepatocytes. As an example, the cytotoxicity of acetaminophen and acetyl salicylic acid is assessed.

WIPP WAC Equivalence Support Measurements for Low-Level Sludge Waste at Los Alamos National Laboratory - 12242

Energy Technology Data Exchange (ETDEWEB)

Gruetzmacher, Kathleen M.; Bustos, Roland M.; Ferran, Scott G.; Gallegos, Lucas E. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Lucero, Randy P. [Pajarito Scientific Corporation, Santa Fe, New Mexico 87507 (United States)

2012-07-01

Los Alamos National Laboratory (LANL) uses the Nevada National Security Site (NNSS) as an off-site disposal facility for low-level waste (LLW), including sludge waste. NNSS has issued a position paper that indicates that systems that are not certified by the Carlsbad Field Office (CBFO) for Waste Isolation Pilot Plant (WIPP) disposal of Transuranic (TRU) waste must demonstrate equivalent practices to the CBFO certified systems in order to assign activity concentration values to assayed items without adding in the Total Measurement Uncertainty (TMU) when certifying waste for NNSS disposal. Efforts have been made to meet NNSS requirements to accept sludge waste for disposal at their facility. The LANL LLW Characterization Team uses portable high purity germanium (HPGe) detector systems for the nondestructive assay (NDA) of both debris and sludge LLW. A number of performance studies have been conducted historically by LANL to support the efficacy and quality of assay results generated by the LANL HPGe systems, and, while these detector systems are supported by these performance studies and used with LANL approved procedures and processes, they are not certified by CBFO for TRU waste disposal. Beginning in 2009, the LANL LLW Characterization Team undertook additional NDA measurements of both debris and sludge simulated waste containers to supplement existing studies and procedures to demonstrate full compliance with the NNSS position paper. Where possible, Performance Demonstration Project (PDP) drums were used for the waste matrix and PDP sources were used for the radioactive sources. Sludge drums are an example of a matrix with a uniform distribution of contaminants. When attempting to perform a gamma assay of a sludge drum, it is very important to adequately simulate this uniform distribution of radionuclides in order to accurately model the assay results. This was accomplished by using a spiral radial source tube placement in a sludge drum rather than the standard

Leaching of coal solid waste; Lixiviacion de Residuos de Combustion de Carbon

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

Combustion process to generate electrical energy in Thermal power Stations causes a big volume of solid wastes. Their store and removal has to be check for possible risks in the Environment. In this study, ashes and slags from eleven Spanish Thermal power Station has been selected. Physical chemical assays have been developed for determining twenty four parameters by; ionic chromatography, atomic absorption spectrophotometry liquid chromatography. (HPLC): UV and selective electrodes, selective electrodes espectrophotometry. Moreover, six biological tests have been realized: Bioluminescence with Photobacterium phosphoreum, Daphnia magna assay. Inhibition on Algae, Inhibition of respiration of Activated Sludges, Acute Toxicity on Fish and Earth-worm Toxicity tests. Samples treatment has been carrying out by two leaching methods: 1 o EP and DIN 38414-4 No toxic level has been found for physical-chemical parameters. The CE50 values of biological tests have allowed to stablish organisms sensibilities to waste samples, differences between ashes and slags and relationship between the carbon type and his effects on the biological organisms. (Author)

Radiological Characterization Methodology for INEEL-Stored Remote-Handled Transuranic (RH TRU) Waste from Argonne National Laboratory-East

International Nuclear Information System (INIS)

Kuan, P.; Bhatt, R.N.

2003-01-01

An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-based characterization methodology offers a superior alternative to traditional waste assay techniques. Using the methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits

Random assay in radioimmunoassay: Feasibility and application compared with batch assay

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Min; Lee, Hwan Hee; Park, Sohyun; Kim, Tae Sung; Kim, Seok Ki [Dept. of Nuclear MedicineNational Cancer Center, Goyang (Korea, Republic of)

2016-12-15

The batch assay has been conventionally used for radioimmunoassay (RIA) because of its technical robustness and practical convenience. However, it has limitations in terms of the relative lag of report time due to the necessity of multiple assays in a small number of samples compared with the random assay technique. In this study, we aimed to verify whether the random assay technique can be applied in RIA and is feasible in daily practice. The coefficients of variation (CVs) of eight standard curves within a single kit were calculated in a CA-125 immunoradiometric assay (IRMA) for the reference of the practically ideal CV of the CA-125 kit. Ten standard curves of 10 kits from 2 prospectively collected lots (pLot) and 85 standard curves of 85 kits from 3 retrospectively collected lots (Lot) were obtained. Additionally, the raw measurement data of both 170 control references and 1123 patients' sera were collected retrospectively between December 2015 and January 2016. A standard curve of the first kit of each lot was used as a master standard curve for a random assay. The CVs of inter-kits were analyzed in each lot, respectively. All raw measurements were normalized by decay and radioactivity. The CA-125 values from control samples and patients' sera were compared using the original batch assay and random assay. In standard curve analysis, the CVs of inter-kits in pLots and Lots were comparable to those within a single kit. The CVs from the random assay with normalization were similar to those from the batch assay in the control samples (CVs % of low/high concentration; Lot1 2.71/1.91, Lot2 2.35/1.83, Lot3 2.83/2.08 vs. Lot1 2.05/1.21, Lot2 1.66/1.48, Lot3 2.41/2.14). The ICCs between the batch assay and random assay using patients' sera were satisfactory (Lot1 1.00, Lot2 0.999, Lot3 1.00). The random assay technique could be successfully applied to the conventional CA-125 IRMA kits. The random assay showed strong agreement with the batch assay. The

Q2 - a very low level quantitative and qualitative waste assay and release certification system

International Nuclear Information System (INIS)

Bronson, F.L.

1990-01-01

Low level radioactive waste disposal is very expensive, especially when all of the handling transportation and documentation costs are included. However for most generators, a large fraction of this low level waste is not contaminated at all, or only slightly so. The paper describes the development and performance of a low level counter that is convenient to use, and that can accurately identify and quantify the radioactivity of any gamma emitter thing that can be placed in a 55 gallon (200 liter) container. These measurement results can be used to verify the absence of radioactivity at a very low levels (10 nCi (370 Bq)/sample), and to identify the nuclides and quantities present, while differentiating against natural radioactivity (Radium, Thorium, Potassium). These results can be used as part of a 10CFR20.302 waste stream exemption program, and thus allow significant savings and a less than 1 year payback at a typical nuclear power plant. The Q1 system is fully shielded to allow it's use in the low level radwaste storage area. The detectors are either 3 Intrinsic Germanium detectors or 2 large NaI detectors. The software is fully automated for simple operation. Correlation factors can be entered to estimate non-gamma emitters from pre-established correlations to other nuclides. Typical Ge detector sensitivities are 8 nCi (300 Bq) LLD for Cs-137 at 0.8 g/cc for a 10 minute count time. NaI detector systems can achieve the same LLD in a 1 minute count. 5 figs., 1 tab

Comparative evaluation of environmental contamination and DNA damage induced by electronic-waste in Nigeria and China

Energy Technology Data Exchange (ETDEWEB)

Alabi, Okunola A. [Analytic Cytology Laboratory and the Key Immunopathology Laboratory of Guangdong Province, Shantou University Medical College, Shantou (China); Biosciences and Biotechnology Department, Babcock University, Ilisan-remo, Ogun State (Nigeria); Cell Biology and Genetics Unit, Department of Zoology, University of Ibadan, Ibadan (Nigeria); Bakare, Adekunle A. [Cell Biology and Genetics Unit, Department of Zoology, University of Ibadan, Ibadan (Nigeria); Xu, Xijin; Li, Bin; Zhang, Yuling [Analytic Cytology Laboratory and the Key Immunopathology Laboratory of Guangdong Province, Shantou University Medical College, Shantou (China); Huo, Xia, E-mail: xhuo@stu.edu.cn [Analytic Cytology Laboratory and the Key Immunopathology Laboratory of Guangdong Province, Shantou University Medical College, Shantou (China)

2012-04-15

In the last decade, China and Nigeria have been prime destinations for the world's e-waste disposal leading to serious environmental contamination. We carried out a comparative study of the level of contamination using soils and plants from e-waste dumping and processing sites in both countries. Levels of polyaromatic hydrocarbons (PAHs), polychlorinated biphenyls (PCBs), and polybrominated diphenyl ethers (PBDEs) were analyzed using gas chromatography/spectrophotometry and heavy metals using atomic absorption spectrophotometry. DNA damage was assayed in human peripheral blood lymphocytes using an alkaline comet assay. Soils and plants were highly contaminated with toxic PAHs, PCBs, PBDEs, and heavy metals in both countries. Soil samples from China and plant samples from Nigeria were more contaminated. There was a positive correlation between the concentrations of organics and heavy metals in plant samples and the surrounding soils. In human lymphocytes, all tested samples induced significant (p < 0.05) concentration-dependent increases in DNA damage compared with the negative control. These findings suggest that e-waste components/constituents can accumulate, in soil and surrounding vegetation, to toxic and genotoxic levels that could induce adverse health effects in exposed individuals. - Highlights: Black-Right-Pointing-Pointer The study showed that Nigeria environment is highly contaminated by electronic waste. Black-Right-Pointing-Pointer The contamination level by heavy metals and organics in soils and plants in Nigeria as a result of the electronic waste is as high as the environment in China, even though China is the recipient of about 70% of the world's e-waste. Black-Right-Pointing-Pointer The study showed that e-waste leachate is genotoxic and mutagenic.

Comparison of Batch Assay and Random Assay Using Automatic Dispenser in Radioimmunoassay

Energy Technology Data Exchange (ETDEWEB)

Moon, Seung Hwan; Jang, Su Jin; Kang, Ji Yeon; Lee, Dong Soo; Chung, June Key; Lee, Myung Chul [Seoul Metropolitan Government Seoul National University Boramae Medical Center, Seoul (Korea, Republic of); Lee, Ho Young; Shin, Sun Young; Min, Gyeong Sun; Lee, Hyun Joo [Seoul National University college of Medicine, Seoul (Korea, Republic of)

2009-08-15

Radioimmunoassay (RIA) was usually performed by the batch assay. To improve the efficiency of RIA without increase of the cost and time, random assay could be a choice. We investigated the possibility of the random assay using automatic dispenser by assessing the agreement between batch assay and random assay. The experiments were performed with four items; Triiodothyronine (T3), free thyroxine (fT4), Prostate specific antigen (PSA), Carcinoembryonic antigen (CEA). In each item, the sera of twenty patients, the standard, and the control samples were used. The measurements were done 4 times with 3 hour time intervals by random assay and batch assay. The coefficient of variation (CV) of the standard samples and patients' data in T3, fT4, PSA, and CEA were assessed. ICC (Intraclass correlation coefficient) and coefficient of correlation were measured to assessing the agreement between two methods. The CVs (%) of T3, fT4, PSA, and CEA measured by batch assay were 3.2+-1.7%, 3.9+-2.1%, 7.1+-6.2%, 11.2+-7.2%. The CVs by random assay were 2.1+-1.7%, 4.8+-3.1%, 3.6+-4.8%, and 7.4+-6.2%. The ICC between the batch assay and random assay were 0.9968 (T3), 0.9973 (fT4), 0.9996 (PSA), and 0.9901 (CEA). The coefficient of correlation between the batch assay and random assay were 0.9924(T3), 0.9974 (fT4), 0.9994 (PSA), and 0.9989 (CEA) (p<0.05). The results of random assay showed strong agreement with the batch assay in a day. These results suggest that random assay using automatic dispenser could be used in radioimmunoassay

Comparison of Batch Assay and Random Assay Using Automatic Dispenser in Radioimmunoassay

International Nuclear Information System (INIS)

Moon, Seung Hwan; Jang, Su Jin; Kang, Ji Yeon; Lee, Dong Soo; Chung, June Key; Lee, Myung Chul; Lee, Ho Young; Shin, Sun Young; Min, Gyeong Sun; Lee, Hyun Joo

2009-01-01

Radioimmunoassay (RIA) was usually performed by the batch assay. To improve the efficiency of RIA without increase of the cost and time, random assay could be a choice. We investigated the possibility of the random assay using automatic dispenser by assessing the agreement between batch assay and random assay. The experiments were performed with four items; Triiodothyronine (T3), free thyroxine (fT4), Prostate specific antigen (PSA), Carcinoembryonic antigen (CEA). In each item, the sera of twenty patients, the standard, and the control samples were used. The measurements were done 4 times with 3 hour time intervals by random assay and batch assay. The coefficient of variation (CV) of the standard samples and patients' data in T3, fT4, PSA, and CEA were assessed. ICC (Intraclass correlation coefficient) and coefficient of correlation were measured to assessing the agreement between two methods. The CVs (%) of T3, fT4, PSA, and CEA measured by batch assay were 3.2±1.7%, 3.9±2.1%, 7.1±6.2%, 11.2±7.2%. The CVs by random assay were 2.1±1.7%, 4.8±3.1%, 3.6±4.8%, and 7.4±6.2%. The ICC between the batch assay and random assay were 0.9968 (T3), 0.9973 (fT4), 0.9996 (PSA), and 0.9901 (CEA). The coefficient of correlation between the batch assay and random assay were 0.9924(T3), 0.9974 (fT4), 0.9994 (PSA), and 0.9989 (CEA) (p<0.05). The results of random assay showed strong agreement with the batch assay in a day. These results suggest that random assay using automatic dispenser could be used in radioimmunoassay

Genotoxicity studies in semiconductor industry. 1. In vitro mutagenicity and genotoxicity studies of waste samples resulting from plasma etching

Energy Technology Data Exchange (ETDEWEB)

Braun, R.; Huettner, E.M.; Merten, H.; Raabe, F. (Institute of Plant Genetics and Crop Plant Research, Gatersleben (Germany))

1993-07-01

Solid waste samples taken from the etching reactor, the turbo pump, and the waste air system of a plasma etching technology line in semiconductor production were studied as to their genotoxic properties in a bacterial repair test, in the Ames/Salmonella microsome assay, in the SOS chromotest, in primary mouse hepatocytes, and in Chinese hamster V79 cell cultures. All three waste samples were found to be active by inducing of unscheduled DNA-synthesis in mouse hepatocytes in vitro. In the bacterial rec-type repair test with Proteus mirabilis, waste samples taken from the turbo pump and the vacuum pipe system were not genotoxic. The waste sample taken from the chlorine-mediated plasma reactor was clearly positive in the bacterial repair assay and in the SOS chromotest with Escherichia coli. Mutagenic activity was demonstrated for all samples in the presence and absence of S9 mix made from mouse liver homogenate. Again, highest mutagenic activity was recorded for the waste sample taken from the plasma reactor, while samples collected from the turbo pump and from the waste air system before dilution and liberation of the air were less mutagenic. For all samples chromosomal damage in V79 cells was not detected, indicating absence of clastogenic activity in vitro. Altogether, these results indicate generation of genotoxic and mutagenic products as a consequence of chlorine-mediated plasma etching in the microelectronics industry and the presence of genotoxins even in places distant from the plasma reactor. Occupational exposure can be expected both from the precipitated wastes and from chemicals reaching the environment with the air stream.

Assessing transmissible spongiform encephalopathy species barriers with an in vitro prion protein conversion assay

Science.gov (United States)

Johnson, Christopher J.; Carlson, Christina M.; Morawski, Aaron R.; Manthei, Alyson; Cashman, Neil R.

2015-01-01

Studies to understanding interspecies transmission of transmissible spongiform encephalopathies (TSEs, prion diseases) are challenging in that they typically rely upon lengthy and costly in vivo animal challenge studies. A number of in vitro assays have been developed to aid in measuring prion species barriers, thereby reducing animal use and providing quicker results than animal bioassays. Here, we present the protocol for a rapid in vitroprion conversion assay called the conversion efficiency ratio (CER) assay. In this assay cellular prion protein (PrPC) from an uninfected host brain is denatured at both pH 7.4 and 3.5 to produce two substrates. When the pH 7.4 substrate is incubated with TSE agent, the amount of PrPC that converts to a proteinase K (PK)-resistant state is modulated by the original host’s species barrier to the TSE agent. In contrast, PrPC in the pH 3.5 substrate is misfolded by any TSE agent. By comparing the amount of PK-resistant prion protein in the two substrates, an assessment of the host’s species barrier can be made. We show that the CER assay correctly predicts known prion species barriers of laboratory mice and, as an example, show some preliminary results suggesting that bobcats (Lynx rufus) may be susceptible to white-tailed deer (Odocoileus virginianus) chronic wasting disease agent.

Repackaging of High Fissile TRU Waste at the Transuranic Waste Processing Center - 13240

Energy Technology Data Exchange (ETDEWEB)

Oakley, Brian; Heacker, Fred [WAI, TRU Waste Processing Center, 100 WIPP Road Lenoir City, TN 37771 (United States); McMillan, Bill [DOE, Oak Ridge Operations, Bldg. 2714, Oak Ridge, TN 37830 (United States)

2013-07-01

to be 1-3 mSv/hr (100-300 mrem/hr) with an unshielded dose rate on the waste itself of over 10 mSv/hr (1 rem/hr). Additional equipment to be installed at the TWPC will include a new perma-con enclosure and a shielded/inert glovebox in the process building to repackage and stabilize the waste. All of the waste will be repackaged into Standard Pipe Overpacks. Most of the waste (21 of the 26 drums) is expected to be repackaged at the food-pack can level (i.e. the food-pack cans will not be opened). Five of the incoming waste containers are expected to be repackaged at the primary waste level. Three of the containers exceed the 200 gram Pu-239 Fissile Gram Equivalent (FGE) limit for the Standard Pipe Overpack. These three containers will be repackaged down to the primary waste level and divided into eight Standard Pipe Overpacks for shipment to WIPP. Two containers must be stabilized to eliminate any reactive plutonium hydrides that may be present. These containers will be opened in the inert, shielded glovebox, and the remaining corroded plutonium metal converted to a stable oxide form by using a 600 deg. C tube furnace with controlled oxygen feed in a helium carrier gas. The stabilized waste will then be packaged into two Standard Pipe Overpacks. Design and build out activities for the additional repackaging capabilities at the TWPC are scheduled to begin in Fiscal Year 2013 with repackaging, stabilization, and certification activities scheduled to begin in Fiscal Year 2014. Following repackaging and stabilization activities, the Standard Pipe Overpacks will be certified for disposal at WIPP utilizing Non-Destructive Examination (NDE) to verify the absence of prohibited items and Non-Destructive Assay (NDA) to verify the isotopic content under the TWPC WIPP certification program implemented by the Central Characterization Project (CCP). (authors)

Radioreceptor opioid assay

International Nuclear Information System (INIS)

Miller, R.J.; Chang, K.-J.

1981-01-01

A radioreceptor assay is described for assaying opioid drugs in biological fluids. The method enables the assay of total opioid activity, being specific for opioids as a class but lacking specificity within the class. A radio-iodinated opioid and the liquid test sample are incubated with an opiate receptor material. The percentage inhibition of the binding of the radio-iodinated compound to the opiate receptor is calculated and the opioid activity of the test liquid determined from a standard curve. Examples of preparing radio-iodinated opioids and assaying opioid activity are given. A test kit for the assay is described. Compared to other methods, this assay is cheap, easy and rapid. (U.K.)

Canine scent detection and microbial source tracking of human waste contamination in storm drains.

Science.gov (United States)

Van De Werfhorst, Laurie C; Murray, Jill L S; Reynolds, Scott; Reynolds, Karen; Holden, Patricia A

2014-06-01

Human fecal contamination of surface waters and drains is difficult to diagnose. DNA-based and chemical analyses of water samples can be used to specifically quantify human waste contamination, but their expense precludes routine use. We evaluated canine scent tracking, using two dogs trained to respond to the scent of municipal wastewater, as a field approach for surveying human fecal contamination. Fecal indicator bacteria, as well as DNA-based and chemical markers of human waste, were analyzed in waters sampled from canine scent-evaluated sites (urban storm drains and creeks). In the field, the dogs responded positively (70% and 100%) at sites for which sampled waters were then confirmed as contaminated with human waste. When both dogs indicated a negative response, human waste markers were absent. Overall, canine scent tracking appears useful for prioritizing sampling sites for which DNA-based and similarly expensive assays can confirm and quantify human waste contamination.

Classification of solid industrial waste based on ecotoxicology tests using Daphnia magna: an alternative

OpenAIRE

William Gerson Matias; Vanessa Guimarães Machado; Cátia Regina Silva de Carvalho-Pinto; Débora Monteiro Brentano; Letícia Flohr

2005-01-01

The adequate treatment and final disposal of solid industrial wastes depends on their classification into class I or II. This classification is proposed by NBR 10.004; however, it is complex and time-consuming. With a view to facilitating this classification, the use of assays with Daphnia magna is proposed. These assays make possible the identification of toxic chemicals in the leach, which denotes the presence of one of the characteristics described by NBR 10.004, the toxicity, which is a s...

Waste management - sewage - special wastes

International Nuclear Information System (INIS)

1987-01-01

The 27 papers represent a cross-section of the subject waste management. Particular attention is paid to the following themes: waste avoidance, waste product utilization, household wastes, dumping technology, sewage sludge treatments, special wastes, seepage from hazardous waste dumps, radioactive wastes, hospital wastes, purification of flue gas from waste combustion plants, flue gas purification and heavy metals, as well as combined sewage sludge and waste product utilization. The examples given relate to plants in Germany and other European countries. 12 papers have been separately recorded in the data base. (DG) [de

Performance test results of noninvasive characterization of RCRA surrogate waste by prompt gamma neutron activation analysis

International Nuclear Information System (INIS)

Gehrke, R.J.; Propp, W.A.

1997-11-01

A performance evaluation to determine the feasibility of using prompt gamma neutron activation analysis (PGNAA) for noninvasive, quantitative assay of mixed waste containers was sponsored by DOE's Office of Technology Development (OTD), the Mixed Waste Focus Area (MWFA), and the Idaho National Engineering and Environmental Laboratory (INEEL). The evaluation was conducted using a surrogate waste, based on Portland cement, that was spiked with three RCRA metals, mercury, cadmium, and lead. The results indicate that PGNAA has potential as a process monitor. However, further development is required to improve its sensitivity to meet regulatory requirements for determination of these RCRA metals

Nondestructive assay system for use in decommissioning a plutonium-handling facility

International Nuclear Information System (INIS)

Roche, C.T.; Vronich, J.J.; Bellinger, F.O.; Perry, R.B.

1979-07-01

Argonne National Laboratory is decommissioning a facility used to fabricate reactor fuel elements. The equipment is contaminated with alpha emitters at levels up to 10 12 dpm/100 cm 2 . The objective of decontamination is to reduce the TRU concentrations below 10 nCi/g of waste. A portable NDA procedure using NaI(T1) gamma-spectrometric techniques was selected to measure the residual Pu and 241 Am in the glove boxes. Assays were performed at different stages in the decontamination process to estimate the detection system sensitivity and the effectiveness of the cleaning efforts

Radioactive material inventory control at a waste characterization facility

International Nuclear Information System (INIS)

Yong, L.K.; Chapman, J.A.; Schultz, F.J.

1996-01-01

Due to the recent introduction of more stringent Department of Energy (DOE) regulations and requirements pertaining to nuclear and criticality safety, the control of radioactive material inventory has emerged as an important facet of operations at DOE nuclear facilities. In order to comply with nuclear safety regulations and nuclear criticality requirements, radioactive material inventories at each nuclear facility have to be maintained below limits specified for the facility in its safety authorization basis documentation. Exceeding these radioactive material limits constitutes a breach of the facility's nuclear and criticality safety envelope and could potentially result in an accident, cause a shut-down of the facility, and bring about imminent regulatory repercussions. The practice of maintaining control of radioactive material, especially sealed and unsealed sources, is commonplace and widely implemented; however, the requirement to track the entire radioactivity inventory at each nuclear facility for the purpose of ensuring nuclear safety is a new development. To meet the new requirements, the Applied Radiation Measurements Department at Oak Ridge National Laboratory (ORNL) has developed an information system, called the open-quotes Radioactive Material Inventory Systemclose quotes (RMIS), to track the radioactive material inventory at an ORNL facility, the Waste Examination and Assay Facility (WEAF). The operations at WEAF, which revolve around the nondestructive assay and nondestructive examination of waste and related research and development activities, results in an ever-changing radioactive material inventory. Waste packages and radioactive sources are constantly being brought in or taken out of the facility; hence, use of the RMIS is necessary to ensure that the radioactive material inventory limits are not exceeded

Nondestructive assay technology and automated ''real-time'' materials control

International Nuclear Information System (INIS)

Keepin, G.R.

1977-01-01

Significant advances in nondestructive assay techniques and instrumentation now enable rapid, accurate and direct in-plant measurement of nuclear material on a continuous or ''real-time'' basis as it progresses through a nuclear facility. A variety of passive and active assay instruments are required for the broad range of materials measurement problems encountered by safeguards inspectors and facility operators in various types of nuclear plants. Representative NDA techniques and instruments are presented and reviewed with special attention to their assay capabilities and areas of applicability in the nuclear fuel cycle. An advanced system of materials control - called ''DYMAC'', for Dynamic Materials Control - is presently under development by the U.S. Energy Research and Development Administration; the DYMAC program integrates new nondestructive assay instrumentation and modern data-processing methods, with the overall objective of demonstrating a workable, cost-effective system of stringent safeguards and materials control in various generic types of facilities found in the nuclear fuel cycle. Throughout the program, emphasis will be placed on devloping practical solutions to generic measurement problems so that resulting techniques and instrumentation will have widespread utility. Projected levels of safeguards assurance, together with other vital - and cost-sensitive - plant operational factors such as process and quality control, criticality safety and waste management are examined in an evaluation of the impact of future advanced materials control systems on overall plant operations, efficiency and productivity. The task of implementing effective and stringent safeguards includes the transfer of new safeguards technology to the nuclear industry. Clearly the training of inspectors (both IAEA and national), plant people, etc., in the effective use of new NDA equipment is of paramount importance; thus in the United States, the Energy Research and Development

Characterization of radioactive-waste drum contents using real-time x-radiography

International Nuclear Information System (INIS)

Barna, B.A.; Bishoff, J.R.; Reinhardt, W.W.

1982-01-01

Low-level transuranic (TRU) waste is stored in a retrievable manner at the Radioactive Waste Management Complex (RWMC) operated by EG and G Idaho, Inc., for the Department of Energy. The waste, consisting of contaminated rags, paper, plastic, laboratory glassware, tools, scrap metal, wood, electrical components and parts, sludges, etc., is packed in various sized sealed containers, including 55 gallon drums. Waste which can be accurately characterized will be sent to the Waste Isolation Pilot Plant (WIPP) in New Mexico for long term storage if it is certified to meet the WIPP waste acceptance criteria. EG and G Idaho, Inc. is planning to install a real-time x-ray system designed for the automated and semi-automated examination of low-level TRU waste containers including 30, 55, and 83 gallon drums, 4 x 4 x 7 foot plywood boxes, and 4 x 5 x 6 foot metal bins during 1982. This system, designed for production, is capable of examining up to 20,000 waste containers per year using automated container handling, and features real-time x-ray imaging with a 420 kV, 10 ma constant potential source, digital image processing equipment, and video taping facilities (every container examination is required to be taped, for archival documentation). Work planned for the near future involves tests using real-time neutron radiography for waste characterization as a complement to real-time x-ray radiography. Ultimately, the NDE examinations will be combined with automated nondestructive assay (NDA) techniques for complete characterization of a given waste container's contents

Feasibility Study of Neutron Multiplicity Assay for a Heterogeneous Sludge Sample containing Na, Pu and other Impurities

International Nuclear Information System (INIS)

Nakamura, H.; Nakamichi, H.; Mukai, Y.; Yoshimoto, K.; Beddingfield, D.H.

2010-01-01

To reduce radioactivity of liquid waste generated at PCDF, a neutralization precipitation processes of radioactive nuclides by sodium hydroxide is used. We call the precipitate a 'sludge' after calcination. Pu mass in the sludge is normally determined by sampling and DA within the required uncertainty on DIQ. Annual yield of the mass is small but it accumulates and reaches to a few kilograms, so it is declared as retained waste and verified at PIV. A HM-5-based verification is applied for sludge verification. The sludge contains many chemical components. For example, Pu (-10wt%), U, Am, SUS components, halogens, NaNO 3 (main component), residual NaOH, and moisture. They are mixed together as an impure heterogeneous sludge sample. As a result, there is a large uncertainty in the sampling and DA that is currently used at PCDF. In order to improve the material accounting, we performed a feasibility study using neutron multiplicity assay for impure sludge samples. We have measured selected sludge samples using a multiplicity counter which is called FCAS (Fast Carton Assay System) which was designed by JAEA and Canberra. The PCDF sludge materials fall into the category of 'difficult to measure' because of the high levels of impurities, high alpha values and somewhat small Pu mass. For the sludge measurements, it was confirmed that good consistency between Pu mass in a pure sludge standard (PuO 2 -Na 2 U 2 O 7 , alpha=7) and the DA could be obtained. For unknown samples, using 14-hour measurements, we could obtain quite low statistical uncertainty on Doubles (-1%) and Triples (-10%) count rate although the alpha value was extremely high (15-25) and FCAS efficiency was relatively low (40%) for typical multiplicity counters. Despite the detector efficiency challenges and the material challenges (high alpha, low Pu mass, heterogeneous matrix), we have been able to obtain assay results that greatly exceed the accountancy requirements for retained waste materials. We have

Advanced conceptual design report solid waste retrieval facility, phase I, project W-113

International Nuclear Information System (INIS)

Smith, K.E.

1994-01-01

Project W-113 will provide the equipment and facilities necessary to retrieve suspect transuranic (TRU) waste from Trench 04 of the 218W-4C burial ground. As part of the retrieval process, waste drums will be assayed, overpacked, vented, head-gas sampled, and x-rayed prior to shipment to the Phase V storage facility in preparation for receipt at the Waste Receiving and Processing Facility (WRAP). Advanced Conceptual Design (ACD) studies focused on project items warranting further definition prior to Title I design and areas where the potential for cost savings existed. This ACD Report documents the studies performed during FY93 to optimize the equipment and facilities provided in relation to other SWOC facilities and to provide additional design information for Definitive Design

Effects of substrate to inoculum ratio on the biochemical methane potential of piggery slaughterhouse wastes.

Science.gov (United States)

Yoon, Young-Man; Kim, Seung-Hwan; Shin, Kook-Sik; Kim, Chang-Hyun

2014-04-01

The aim of this study was to assess the effect of substrate to inoculum ratio (S/I ratio) on the biochemical methane potential (BMP) and anaerobic biodegradability (Ddeg) of different piggery slaughterhouse wastes, such as piggery blood, intestine residue, and digestive tract content. These wastes were sampled from a piggery slaughterhouse located in Kimje, South Korea. Cumulative methane production curves for the wastes were obtained from the anaerobic batch fermentation having different S/I ratios of 0.1, 0.5, 1.0, and 1.5. BMP and anaerobic biodegradabilities (Ddeg) of the wastes were calculated from cumulative methane production data for the tested conditions. At the lowest S/I ration of 0.1, BMPs of piggery blood, intestine residue, and digestive tract content were determined to be 0.799, 0.848, and 1.076 Nm(3) kg(-1)-VSadded, respectively, which were above the theoretical methane potentials of 0.539, 0.644, and 0.517 Nm(3) kg(-1)-VSadded for blood, intestine residue, and digestive tract content, respectively. However, BMPs obtained from the higher S/I ratios of 0.5, 1.0, and 1.5 were within the theoretical range for all three types of waste and were not significantly different for the different S/I ratios tested. Anaerobic biodegradabilities calculated from BMP data showed a similar tendency. These results imply that, for BMP assay in an anaerobic reactor, the S/I ratio of anaerobic reactor should be above 0.1 and the inoculum should be sufficiently stabilized to avoid further degradation during the assay.

Effects of Substrate to Inoculum Ratio on the Biochemical Methane Potential of Piggery Slaughterhouse Wastes

Directory of Open Access Journals (Sweden)

Young-Man Yoon

2014-04-01

Full Text Available The aim of this study was to assess the effect of substrate to inoculum ratio (S/I ratio on the biochemical methane potential (BMP and anaerobic biodegradability (Ddeg of different piggery slaughterhouse wastes, such as piggery blood, intestine residue, and digestive tract content. These wastes were sampled from a piggery slaughterhouse located in Kimje, South Korea. Cumulative methane production curves for the wastes were obtained from the anaerobic batch fermentation having different S/I ratios of 0.1, 0.5, 1.0, and 1.5. BMP and anaerobic biodegradabilities (Ddeg of the wastes were calculated from cumulative methane production data for the tested conditions. At the lowest S/I ration of 0.1, BMPs of piggery blood, intestine residue, and digestive tract content were determined to be 0.799, 0.848, and 1.076 Nm3 kg−1-VSadded, respectively, which were above the theoretical methane potentials of 0.539, 0.644, and 0.517 Nm3 kg−1-VSadded for blood, intestine residue, and digestive tract content, respectively. However, BMPs obtained from the higher S/I ratios of 0.5, 1.0, and 1.5 were within the theoretical range for all three types of waste and were not significantly different for the different S/I ratios tested. Anaerobic biodegradabilities calculated from BMP data showed a similar tendency. These results imply that, for BMP assay in an anaerobic reactor, the S/I ratio of anaerobic reactor should be above 0.1 and the inoculum should be sufficiently stabilized to avoid further degradation during the assay.

Performance evaluation and operational experience with a semi-automatic monitor for the radiological characterization of low-level wastes

International Nuclear Information System (INIS)

Davey, E.C.; Csullog, G.W.

1987-03-01

Chalk River Nuclear Laboratories (CRNL) have undertaken a Waste Disposal Project to co-ordinate the transition from the current practice of interim storage to permanent disposal for low-level radioactive wastes (LLW). The strategy of the project is to classify and segregate waste segments according to their hazardous radioactive lifetimes and to emplace them in disposal facilities engineered to isolate and contain them. To support this strategy, a waste characterization program was set up to estimate the volume and radioisotope inventories of the wastes managed by CRNL. A key element of the program is the demonstration of a non-invasive measurement technique for the isotope-specific characterization of solid LLW. This paper describes the approach taken at CRNL for the non-invasive assay of LLW and the field performance and early operational experience with a waste characterization monitor to be used in a waste processing facility

Performance evaluation and operational experience with a semi-automatic monitor for the radiological characterization of low-level wastes

International Nuclear Information System (INIS)

Davey, E.C.; Csullog, G.W.

1987-01-01

Chalk River Nuclear Laboratories (CRNL) have undertaken a Waste Disposal Project to co-ordinate the transition from the current practice of interim storage to permanent disposal for low-level radioactive wastes (LLW). The strategy of the project is to classify and segregate waste segments according to their hazardous radioactive lifetimes and to emplace them in disposal facilities engineered to isolate and contain them. To support this strategy, a waste characterization program was set up to estimate the volume and radioisotope inventories of the wastes managed by CRNL. A key element of the program is the demonstration of a non-invasive measurement technique for the isotope-specific characterization of solid LLW. This paper describes the approach taken at CRNL for the non-invasive assay of LLW and the field performance and early operational experience with a waste characterization monitor to be used in a waste processing facility

The waste-to-energy framework for integrated multi-waste utilization: Waste cooking oil, waste lubricating oil, and waste plastics

Energy Technology Data Exchange (ETDEWEB)

Singhabhandhu, Ampaitepin; Tezuka, Tetsuo [Energy Economics Laboratory, Department of Socio-Environmental Energy Science, Graduate School of Energy Science, Kyoto University, Yoshida-honmachi, Sakyo-ku, Kyoto 606-8501 (Japan)

2010-06-15

Energy generation by wastes is considered one method of waste management that has the benefit of energy recovery. From the waste-to-energy point of view, waste cooking oil, waste lubricating oil, and waste plastics have been considered good candidates for feedstocks for energy conversion due to their high heating values. Compared to the independent management of these three wastes, the idea of co-processing them in integration is expected to gain more benefit. The economies of scale and the synergy of co-processing these wastes results in higher quality and higher yield of the end products. In this study, we use cost-benefit analysis to evaluate the integrated management scenario of collecting the three wastes and converting them to energy. We report the total heat of combustion of pyrolytic oil at the maximum and minimum conversion rates, and conduct a sensitivity analysis in which the parameters of an increase of the electricity cost for operating the process and increase of the feedstock transportation cost are tested. We evaluate the effects of economy of scale in the case of integrated waste management. We compare four cases of waste-to-energy conversion with the business as usual (BAU) scenario, and our results show that the integrated co-processing of waste cooking oil, waste lubricating oil, and waste plastics is the most profitable from the viewpoints of energy yield and economics. (author)

Integration of GC-MSD and ER-Calux® assay into a single protocol for determining steroid estrogens in environmental samples.

Science.gov (United States)

Avberšek, Miha; Žegura, Bojana; Filipič, Metka; Heath, Ester

2011-11-01

There are many published studies that use either chemical or biological methods to investigate steroid estrogens in the aquatic environment, but rarer are those that combine both. In this study, gas chromatography with mass selective detection (GC-MSD) and the ER-Calux(®) estrogenicity assay were integrated into a single protocol for simultaneous determination of natural (estrone--E1, 17β-estradiol--E2, estriol--E3) and synthetic (17α-ethinylestradiol--EE2) steroid estrogens concentrations and the total estrogenic potential of environmental samples. For integration purposes, several solvents were investigated and the commonly used dimethyl sulphoxide (DMSO) in the ER-Calux(®) assay was replaced by ethyl acetate, which is more compatible with gas chromatography and enables the same sample to be analysed by both GC-MSD and the ER-Calux(®) assay. The integrated protocol was initially tested using a standard mixture of estrogens. The results for pure standards showed that the estrogenicity calculated on the basis of GC-MSD and the ER-Calux(®) assay exhibited good correlation (r(2)=0.96; α=0.94). The result remained the same when spiked waste water extracts were tested (r(2)=0.92, α=1.02). When applied to real waste water influent and effluent samples the results proved (r(2)=0.93; α=0.99) the applicability of the protocol. The main advantages of this newly developed protocol are simple sample handling for both methods, and reduced material consumption and labour. In addition, it can be applied as either a complete or sequential analysis where the ER-Calux(®) assay is used as a pre-screening method prior to the chemical analysis. Copyright © 2011 Elsevier B.V. All rights reserved.

Correlation between the genotoxicity endpoints measured by two different genotoxicity assays: comet assay and CBMN assay

Directory of Open Access Journals (Sweden)

Carina Ladeira

2015-06-01

The results concerning of positive findings by micronuclei and non significant ones by comet assay, are corroborated by Deng et al. (2005 study performed in workers occupationally exposed to methotrexate, also a cytostatic drug. According to Cavallo et al. (2009, the comet assay seems to be more suitable for the prompt evaluation of the genotoxic effects, for instance, of polycyclic aromatic hydrocarbons mixtures containing volatile substances, whereas the micronucleus test seems more appropriate to evaluate the effects of exposure to antineoplastic agents. However, there are studies that observed an increase in both the comet assay and the micronucleus test in nurses handling antineoplastic drugs, although statistical significance was only seen in the comet assay, quite the opposite of our results (Maluf & Erdtmann, 2000; Laffon et al. 2005.

Evaluation of low-level radioactive waste characterization and classification programs of the West Valley Demonstration Project

International Nuclear Information System (INIS)

Taie, K.R.

1994-01-01

The West Valley Demonstration Project (WVDP) is preparing to upgrade their low-level radioactive waste (LLW) characterization and classification program. This thesis describes a survey study of three other DOE sites conducted in support of this effort. The LLW characterization/classification programs of Oak Ridge National Laboratory, Savannah River Site, and Idaho National Engineering Laboratory were critically evaluated. The evaluation was accomplished through tours of each site facility and personnel interviews. Comparative evaluation of the individual characterization/classification programs suggests the WVDP should purchase a real-time radiography unit and a passive/active neutron detection system, make additional mechanical modifications to the segmented gamma spectroscopy assay system, provide a separate building to house characterization equipment and perform assays away from waste storage, develop and document a new LLW characterization/classification methodology, and make use of the supercompactor owned by WVDP

Transuranic (TRU) Waste Repackaging at the Nevada Test Site

International Nuclear Information System (INIS)

Di Sanza, E.F.; Pyles, G.; Ciucci, J.; Arnold, P.

2009-01-01

This paper describes the activities required to modify a facility and the process of characterizing, repackaging, and preparing for shipment the Nevada Test Site's (NTS) legacy transuranic (TRU) waste in 58 oversize boxes (OSB). The waste, generated at other U.S. Department of Energy (DOE) sites and shipped to the NTS between 1974 and 1990, requires size-reduction for off-site shipment and disposal. The waste processing approach was tailored to reduce the volume of TRU waste by employing decontamination and non-destructive assay. As a result, the low-level waste (LLW) generated by this process was packaged, with minimal size reduction, in large sea-land containers for disposal at the NTS Area 5 Radioactive Waste Management Complex (RWMC). The remaining TRU waste was repackaged and sent to the Idaho National Laboratory Consolidation Site for additional characterization in preparation for disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. The DOE National Nuclear Security Administration Nevada Site Office and the NTS Management and Operating (M and O) contractor, NSTec, successfully partnered to modify and upgrade an existing facility, the Visual Examination and Repackaging Building (VERB). The VERB modifications, including a new ventilation system and modified containment structure, required an approved Preliminary Documented Safety Analysis prior to project procurement and construction. Upgrade of the VERB from a radiological facility to a Hazard Category 3 Nuclear Facility required new rigor in the design and construction areas and was executed on an aggressive schedule. The facility Documented Safety Analysis required that OSBs be vented prior to introduction into the VERB. Box venting was safely completed after developing and implementing two types of custom venting systems for the heavy gauge box construction. A remotely operated punching process was used on boxes with wall thickness of up to 3.05 mm (0.120 in) to insert aluminum

Co-digestion of pig slaughterhouse waste with sewage sludge.

Science.gov (United States)

Borowski, Sebastian; Kubacki, Przemysław

2015-06-01

Slaughterhouse wastes (SHW) are potentially very attractive substrates for biogas production. However, mono-digestion of these wastes creates great technological problems associated with the inhibitory effects of ammonia and fatty acids on methanogens as well as with the foaming in the digesters. In the following study, the co-digestion of slaughterhouse wastes with sewage sludge (SS) was undertaken. Batch and semi-continuous experiments were performed at 35°C with municipal sewage sludge and pig SHW composed of meat tissue, intestines, bristles and post-flotation sludge. In batch assays, meat tissue and intestinal wastes gave the highest methane productions of 976 and 826 dm(3)/kg VS, respectively, whereas the methane yield from the sludge was only 370 dm(3)/kg VS. The co-digestion of sewage sludge with 50% SHW (weight basis) provided the methane yield exceeding 600 dm(3)/kg VS, which was more than twice as high as the methane production from sewage sludge alone. However, when the loading rate exceeded 4 kg VS/m(3) d, a slight inhibition of methanogenesis was observed, without affecting the digester stability. The experiments showed that the co-digestion of sewage sludge with large amount of slaughterhouse wastes is feasible, and the enhanced methane production does not affect the digester stability. Copyright © 2015 Elsevier Ltd. All rights reserved.

Microbead agglutination based assays

KAUST Repository

Kodzius, Rimantas

2013-01-21

We report a simple and rapid room temperature assay for point-of-care (POC) testing that is based on specific agglutination. Agglutination tests are based on aggregation of microbeads in the presence of a specific analyte thus enabling the macroscopic observation. Such tests are most often used to explore antibody-antigen reactions. Agglutination has been used for protein assays using a biotin/streptavidin system as well as a hybridization based assay. The agglutination systems are prone to selftermination of the linking analyte, prone to active site saturation and loss of agglomeration at high analyte concentrations. We investigated the molecular target/ligand interaction, explaining the common agglutination problems related to analyte self-termination, linkage of the analyte to the same bead instead of different microbeads. We classified the agglutination process into three kinds of assays: a two- component assay, a three-component assay and a stepped three- component assay. Although we compared these three kinds of assays for recognizing DNA and protein molecules, the assay can be used for virtually any molecule, including ions and metabolites. In total, the optimized assay permits detecting analytes with high sensitivity in a short time, 5 min, at room temperature. Such a system is appropriate for POC testing.

Maximizing DOE R and D efforts in tru waste management learning from international programs

International Nuclear Information System (INIS)

Saxman, P.A.; Loughead, J.S.C.

1990-01-01

Through the International Technology Exchange Program, Department of Energy (DOE) technical specialists maintain a formal dialogue with research and Development (R and D) specialists from nuclear programs in other countries. The objective of these exchanges is to seek innovative waste management solutions, maximize progress for ongoing R and D activities, and minimize the development time required for implementation of transuranic (TRU) waste processing technologies and waste assay developments. Based on information provided by PNC during the exchange, DOE specialists evaluated PNC's efforts to implement technologies and techniques from their R and D program activities. This paper presents several projects with particular potential for DOE operations, and suggests several ways that these concepts could be used to advantage by DOE or commercial programs

Anaerobic co-digestion of food waste and septage – A waste to energy project in Nashik city

Directory of Open Access Journals (Sweden)

Meghanath Prabhu

2015-04-01

Full Text Available The samples for food waste (FW and septage were collected from six localities of Nashik city. Physical and chemical characterizations of the wastes were carried out. A Biomethanation potential (BMP assay was developed to determine the ultimate biodegradability and associated methane yield during the anaerobic methanogenic fermentation of organic substrates. BMP assays of individual substrate, FW and septage were carried out by taking into account the volatile solids/total solids (VS/TS ratio of each while keeping the inoculum’s VS constant. BMP of FW and septage mixture was carried out in different ratios (1:1, 1.5:1, 2:1, 1:1.5 and 1:2 to find the optimum mixing ratio for maximum biogas production. The average methane yield for different locality FW was found to be 503±17.6 ml/g VS and for septage it was 56 ±10.8 ml/g VS. Based on the above results, the total biogas yield and total methane yield for 10 tons of FW would be 2178 m3/d and 1306 m3/d respectively. The total biogas yield and total methane yield for 20 m3 of septage would be 65m3/d and 39m3/d respectively. From our co-digestion studies we also conclude that the mixture of FW to septage at 1:2 ratio gives 2896 m3/day of biogas. The role of septage is to provide essential trace elements that are required for methanogens.

Increasing operational efficiency in a radioactive waste processing plant - 16100

International Nuclear Information System (INIS)

Turner, T.W.; Watson, S.N.

2009-01-01

The solid waste plant at Harwell in Oxfordshire, contains a purpose built facility to input, assay, visually inspect and sort remote handled intermediate level radioactive waste (RHILW). The facility includes a suite of remote handling cells, known as the head-end cells (HEC), which waste must pass through in order to be repackaged. Some newly created waste from decommissioning works on site passes through the cells, but the vast majority of waste for processing is historical waste, stored in below ground tube stores. Existing containers are not suitable for long term storage, many are already badly corroded, so the waste must be efficiently processed and repackaged in order to achieve passive safety. The Harwell site is currently being decommissioned and the land is being restored. The site is being progressively de-licensed, and redeveloped as a business park, which can only be completed when all the nuclear liabilities have been removed. The recovery and processing of old waste in the solid waste plant is a key project linked to de-licensing of a section of the site. Increasing the operational efficiency of the waste processing plant could shorten the time needed to clear the site and has the potential to save money for the Nuclear Decommissioning Authority (NDA). The waste processing facility was constructed in the mid 1990's, and commissioned in 1999. Since operations began, the yearly throughput of the cells has increased significantly every year. To achieve targets set out in the lifetime plan (LTP) for the site, throughput must continue to increase. The operations department has measured the overall equipment effectiveness (OEE) of the process for the last few years, and has used continuous improvement techniques to decrease the average cycle time. Philosophies from operational management practices such as 'lean' and 'kaizen' have been employed successfully to drive out losses and increase plant efficiency. This paper will describe how the solid waste plant

Development of an integrated facility for processing transuranium solid wastes at the Savannah River Plant

International Nuclear Information System (INIS)

Boersma, M.D.; Hootman, H.E.; Permar, P.H.

1978-01-01

An integrated facility is being designed for processing solid wastes contaminated with long-lived alpha emitting (TRU) nuclides; this waste has been stored retrievably at the Savannah River Plant since 1965. The stored waste, having a volume of 10 4 m 3 and containing 3x10 5 Ci of transuranics, consists of both mixed combustible trash and failed and obsolete equipment primarily from transuranic production and associated laboratory operations. The facility for processing solid transuranic waste will consist of five processing modules: 1) unpackaging, sorting, and assaying; 2) treatment of combustibles by controlled air incineration; 3) size reduction of noncombustibles by plasma-arc cutting followed by decontamination by electropolishing; 4) fixation of the processed waste in cement; and 5) packaging for shipment to a federal repository. The facility is projected for construction in the mid-1980's. Pilot facilities, sized to manage currently generated wastes, will also demonstrate the key process steps of incineration of combustibles and size reduction/decontamination of noncombustibles; these facilities are projected for 1980-81. Development programs leading to these extensive new facilities are described

Development of an integrated facility for processing TRU solid wastes at the Savannah River Plant

International Nuclear Information System (INIS)

Boersma, M.D.; Hootman, H.E.; Permar, P.H.

1977-01-01

An integrated facility is being designed for processing solid wastes contaminated with long-lived alpha emitting (TRU) nuclides; this waste has been stored retrievably at the Savannah River Plant since 1965. The stored waste, having a volume of 10 4 m 3 and containing 3 x 10 5 Ci of transuranics, consists of both mixed combustible trash and failed and obsolete equipment primarily from transuranic production and associated laboratory operations. The facility for processing solid transuranic waste will consist of five processing modules: (1) unpackaging, sorting, and assaying; (2) treatment of combustibles by controlled air incineration; (3) size reduction of noncombustibles by plasma-arc cutting followed by decontamination by electropolishing; (4) fixation of the processed waste in cement; and (5) packaging for shipment to a federal repository. The facility is projected for construction in the mid-1980's. Pilot facilities, sized to manage currently generated wastes, will also demonstrate the key process steps of incineration of combustibles and size reduction/decontamination of noncombustibles; these facilities are projected for 1980-81. Development programs leading to these extensive new facilities are described

Characterization of different types of ceramic waste and its incorporation to the cement paste

International Nuclear Information System (INIS)

Cunha, G.A.; Evangelista, A.C.J.; Almeida, V.C. de

2009-01-01

The porcelain tike is a product resulting from the technological development of ceramic plating industry. Its large acceptation by the consumer market is probably linked with certain properties, such as low porosity, high mechanical resistance, facility in maintenance, besides being a material of modern and versatile characteristics. The aim of this work was characterizing the different ceramic wastes (enameled and porcelain tike) and evaluating its influence on the mechanical behavior in cement pastes. The wastes were characterized through the determination of its chemical composition, size particle distribution and X-ray diffraction. Cement pastes + wastes were prepared in 25% and 50% proportions and glue time determination, water absorption and resistance to compression assays were taken. The results indicate that although the wastes don't show any variation in the elementary chemical composition, changes in the cement paste behavior related to the values of resistance to compression were observed. (author)

Waste Sites - Municipal Waste Operations

Data.gov (United States)

NSGIC Education | GIS Inventory — A Municipal Waste Operation is a DEP primary facility type related to the Waste Management Municipal Waste Program. The sub-facility types related to Municipal Waste...

Physico-chemical studies on amylases from fermented cassava waste water

International Nuclear Information System (INIS)

Oboh, G.; Akindahunsi, A.A.

2001-09-01

Waste water from cassava mash fermented with pure strain of Saccharomycees cerevisae together with Lactobacillus delbruckii and Lactobacillus coryneformis (3 days) was assayed for amylase activity. The result of the study indicated that the fermentation waste water had amylase activity, the unit activity and the specific activity of the amylase in the waste water was 0.22μmole/min and 0.06μmole/min/mg, respectively. The amylase was partially purified using Gel filtration (Sephadex-G150). The partially purified enzyme was maximally activity at pH 6.0 and 60 deg. C temperature. It had its maximum stability between pH 6-7 for 4hr, and 30 deg. C for 50 mins. NaCl, NH 4 Cl, FeCl 3 , KCl, NaNO 3 activates the enzyme activity while CUSO 4 and HgCl 2 inhibit the activity of the amylase. It could be concluded that these amylases from the fermented cassava waste amylase were active at wide temperature and pH ranges, this quality could be explored in the industrial sector (most especially food industry) as a source of industrial amylase that requires a wide range of conditions (temperature and pH). (author)

Passive neutron design study for 200-L waste drums

International Nuclear Information System (INIS)

Menlove, H.O.; Beddingfield, D.B.; Pickrell, M.M.

1997-09-01

We have developed a passive neutron counter for the measurement of plutonium in 200-L drums of scrap and waste. The counter incorporates high efficiency for the multiplicity counting in addition to the traditional coincidence counting. The 252 Cf add-a-source feature is used to provide an accurate assay over a wide range of waste matrix materials. The room background neutron rate is reduced by using 30 cm of external polyethylene shielding and the cosmic-ray background is reduced by statistical filtering techniques. Monte Carlo Code calculations were used to determine the optimum detector design, including the gas pressure, size, number, and placement of the 3 He tubes in the moderator. Various moderators, including polyethylene, plastics, teflon, and graphite, were evaluated to obtain the maximum efficiency and minimum detectable mass of plutonium

Transuranic solid waste management programs. Progress report, July--December 1975

International Nuclear Information System (INIS)

1976-09-01

Progress is reported for three transuranic solid waste management programs funded at the Los Alamos Scientific Laboratory (LASL) by the Energy Research and Development Administration (ERDA) Division of Fuel Cycle and Production (NFCP). Under the Transuranic Waste Research and Development Program, continued studies have shown the potential attractiveness of fiber drums as an acceptable substitute for the current mild steel storage containers. Various fire retardants have been evaluated, with one indicating significant ability to inhibit fire propagation. Continued radiolysis studies, under laboratory and field conditions, continue to reaffirm earlier LASL results indicating no significant hazard from radiolytic reactions, assuming no change in current allowable loadings. Care must be exercised to differentiate between radiolytic and chemical reactions. Other efforts have identified a modification of chemical processing to reduce the amounts of plutonium requiring retrievable storage. Studies are also in progress to enhance the sensitivity of the LASL MEGAS assay system. The Transuranic-Contaminated Solid Waste Treatment Development Facility building was 72 percent complete as of December 31, 1975, which is in accord with the existing schedule. Procurement of process components is also on schedule. Certain modifications to the facility have been made, and various pre-facility experiments on waste container handling and processing have been completed. The program for the Evaluation of Transuranic-Contaminated Radioactive Waste Disposal Areas continued development of various computer modules for simulation of radionuclide transport within the biosphere. In addition, program staff contributed to an ERDA document on radioactive waste management through the preparation of a report on burial of radioactive waste at ERDA-contractor and commercial sites

Transuranic solid waste management programs. Progress report, July--December 1975

Energy Technology Data Exchange (ETDEWEB)

1976-09-01

Progress is reported for three transuranic solid waste management programs funded at the Los Alamos Scientific Laboratory (LASL) by the Energy Research and Development Administration (ERDA) Division of Fuel Cycle and Production (NFCP). Under the Transuranic Waste Research and Development Program, continued studies have shown the potential attractiveness of fiber drums as an acceptable substitute for the current mild steel storage containers. Various fire retardants have been evaluated, with one indicating significant ability to inhibit fire propagation. Continued radiolysis studies, under laboratory and field conditions, continue to reaffirm earlier LASL results indicating no significant hazard from radiolytic reactions, assuming no change in current allowable loadings. Care must be exercised to differentiate between radiolytic and chemical reactions. Other efforts have identified a modification of chemical processing to reduce the amounts of plutonium requiring retrievable storage. Studies are also in progress to enhance the sensitivity of the LASL MEGAS assay system. The Transuranic-Contaminated Solid Waste Treatment Development Facility building was 72 percent complete as of December 31, 1975, which is in accord with the existing schedule. Procurement of process components is also on schedule. Certain modifications to the facility have been made, and various pre-facility experiments on waste container handling and processing have been completed. The program for the Evaluation of Transuranic-Contaminated Radioactive Waste Disposal Areas continued development of various computer modules for simulation of radionuclide transport within the biosphere. In addition, program staff contributed to an ERDA document on radioactive waste management through the preparation of a report on burial of radioactive waste at ERDA-contractor and commercial sites.

Bench-scale magnetic separation of Department of Energy wastes

International Nuclear Information System (INIS)

Hoegler, J.M.

1987-07-01

Criteria were developed for selection of candidate wastes for testing magnetic separation of uranium and/or other paramagnetic materials. A survey of Department of Energy (DOE) hazardous wastes was conducted to determine good candidates for bench-scale magnetic separation tests. Representatives of 21 DOE sites were contacted, and 11 materials were identified as potential candidates for magnetic separation. To date, seven samples have been obtained and tested for separability of uranium with a bench-scale magnetic assaying device. The samples tested have been obtained from the K-1401B and K-1401C ponds in Oak Ridge, Tennessee; from waste piles in Maywood, New Jersey; from North and South Ponds in Richland, Washington; and from magnesium fluoride drums in Fernald, Ohio. The magnetic device utilized in these tests can be used in an open-gradient mode with dry particulate or liquid-suspended materials. Uranium separation from magnesium fluoride has shown exceptionally good performance in both open- and high-gradient modes and could be an important application of the technology

Implementation of a level 1 trigger system using high speed serial (VXS) techniques for the 12GeV high luminosity experimental programs at Thomas Jefferson National Accelerator Facility

International Nuclear Information System (INIS)

Cuevas, C.; Raydo, B.; Dong, H.; Gupta, A.; Barbosa, F.J.; Wilson, J.; Taylor, W.M.; Jastrzembski, E.; Abbott, D.

2009-01-01

We will demonstrate a hardware and firmware solution for a complete fully pipelined multi-crate trigger system that takes advantage of the elegant high speed VXS serial extensions for VME. This trigger system includes three sections starting with the front end crate trigger processor (CTP), a global Sub-System Processor (SSP) and a Trigger Supervisor that manages the timing, synchronization and front end event readout. Within a front end crate, trigger information is gathered from each 16 Channel, 12 bit Flash ADC module at 4 nS intervals via the VXS backplane, to a Crate Trigger Processor (CTP). Each Crate Trigger Processor receives these 500 MB/S VXS links from the 16 FADC-250 modules, aligns skewed data inherent of Aurora protocol, and performs real time crate level trigger algorithms. The algorithm results are encoded using a Reed-Solomon technique and transmission of this Level 1 trigger data is sent to the SSP using a multi-fiber link. The multi-fiber link achieves an aggregate trigger data transfer rate to the global trigger at 8 Gb/s. The SSP receives and decodes Reed-Solomon error correcting transmission from each crate, aligns the data, and performs the global level trigger algorithms. The entire trigger system is synchronous and operates at 250 MHz with the Trigger Supervisor managing not only the front end event readout, but also the distribution of the critical timing clocks, synchronization signals, and the global trigger signals to each front end readout crate. These signals are distributed to the front end crates on a separate fiber link and each crate is synchronized using a unique encoding scheme to guarantee that each front end crate is synchronous with a fixed latency, independent of the distance between each crate. The overall trigger signal latency is <3 uS, and the proposed 12GeV experiments at Jefferson Lab require up to 200KHz Level 1 trigger rate.

Feasibility of nondestructive assay measurements in uranium enrichment plants

Energy Technology Data Exchange (ETDEWEB)

Walton, R.B.

1978-04-01

Applications of nondestructive assay methods to measurement problems in uranium enrichment facilities are reviewed. The results of a number of test and evaluation projects that were performed over the last decade at ORGDP and Portsmouth are presented. Measurements of the residual holdup in the top enrichment portion of the shut-down K-25 cascade were made with portable neutron and gamma-ray detectors, and inventory estimates based on these data were in good agreement with ORGDP estimates. In the operating cascade, the tests showed that portable NaI detectors are effective for monitoring NaF and alumina media for gaseous effluent traps and that gas phase enrichments and inventories, as well as large deposits of uranium, can be detected with portable neutron and gamma-ray instrumentation. A wide variety of scrap and waste materials, including barrier and compressor blades, incinerator ash and trapping media, and miscellaneous waste, were measured using passive gamma-ray and neutron methods and 14-MeV neutron interrogation. Methods developed for rapid verification of UF/sub 6/ in shipping containers with portable neutron and gamma-ray instruments are now used routinely by safeguards inspectors. Passive assay methods can also be used to measure continuously the enrichments of /sup 235/U and /sup 234/U in the UF/sub 6/ product and tails withdrawals of a gaseous diffusion plant. A system that was developed and installed in the extended-range product withdrawal station of the Portsmouth facility measures enrichment with a relative accuracy of 0.5%. A stand-alone neutron detector has also been successfully evaluated for the measurement of the isotopic abundance of /sup 234/U in UF/sub 6/ in sample cylinders, an application of potential importance to Minor Isotope Safeguards Technology. Recommendations are made on the role of NDA measurements for enrichment plant safeguards, including additional tests and evaluations that may be needed, particularly for advanced uranium

Bread enriched in lycopene and other bioactive compounds by addition of dry tomato waste.

Science.gov (United States)

Nour, Violeta; Ionica, Mira Elena; Trandafir, Ion

2015-12-01

The tomato processing industry generates high amounts of waste, mainly tomato skins and seeds, which create environmental problems. These residues are attractive sources of valuable bioactive components and pigments. A relatively simple recovery technology could consist of production of powders to be directly incorporated into foods. Tomato waste coming from a Romanian tomato processing unit were analyzed for the content of several bioactive compounds like ascorbic acid, β-carotene, lycopene, total phenolics, mineral and trace elements. In addition, its antioxidant capacity was assayed. Results revealed that tomato waste (skins and seeds) could be successfully utilized as functional ingredient for the formulation of antioxidant rich functional foods. Dry tomato processing waste were used to supplement wheat flour at 6 and 10 % levels (w/w flour basis) and the effects on the bread's physicochemical, baking and sensorial characteristics were studied. The following changes were observed: increase in moisture content, titratable acidity and bread crumb elasticity, reduction in specific volume and bread crumb porosity. The addition of dry tomato waste at 6 % resulted in bread with good sensory characteristics and overall acceptability but as the amount of dry tomato waste increased to 10 %, bread was less acceptable.

Assay-specific decision limits for two new automated parathyroid hormone and 25-hydroxyvitamin D assays.

Science.gov (United States)

Souberbielle, Jean-Claude; Fayol, Véronique; Sault, Corinne; Lawson-Body, Ethel; Kahan, André; Cormier, Catherine

2005-02-01

The recent development of nonradioactive automated assays for serum parathyroid hormone (PTH) and 25-hydroxyvitamin D (25OHD) has made measurement of these two hormones possible in many laboratories. In this study, we compared two new assays for PTH and 25OHD adapted on an automated analyzer, the LIAISON, with two manual immunoassays used worldwide. We studied 228 osteoporotic patients, 927 healthy individuals, 38 patients with primary hyperparathyroidism, and 167 hemodialyzed patients. Serum PTH was measured with the Allegro and the LIAISON assays, and 25OHD was measured with DiaSorin RIA and the LIAISON assay. Regression analysis was used to calculate decision thresholds for the LIAISON assays that were equivalent to those of the Allegro PTH and DiaSorin 25OHD assays. The 25OHD concentrations obtained with the LIAISON assay and the RIA in osteoporotic patients were well correlated (r = 0.83; P 50 nmol/L as eligible for the reference population for the LIAISON PTH assay. In this group, the 3rd-97th percentile interval for LIAISON PTH was 3-51 ng/L. Considering upper reference limits of 46 and 51 ng/L for the Allegro and LIAISON assays, respectively, the frequency of above-normal PTH concentrations in patients with primary hyperparathyroidism was similar in both assays. Regression analysis between serum PTH measured by the Allegro and LIAISON assays in 167 hemodialyzed patients and the corresponding Bland-Altman analysis of these data suggest that the LIAISON PTH assay tends to read higher than the Allegro assay at low concentrations but lower at high concentrations (>300 ng/L). Because clinical decision limits for both PTH and 25OHD should be assay specific, we propose equivalences between these assays and two manual assays used worldwide. These assay-specific decision limits should help potential users of the LIAISON PTH and 25OHD assays.

Application of biosorbents in treatment of the radioactive liquid waste

International Nuclear Information System (INIS)

Ferreira, Rafael Vicente de Padua

2014-01-01

Radioactive liquid waste containing organic compounds need special attention, because the treatment processes available are expensive and difficult to manage. The biosorption is a potential treatment technique that has been studied in simulated wastes. The biosorption term is used to describe the removal of metals, non-metals and/or radionuclides by a material from a biological source, regardless of its metabolic activity. Among the potential biomasses, agricultural residues have very attractive features, as they allow for the removal of radionuclides present in the waste using a low cost biosorbent. The aim of this study was to evaluate the potential use of different biomass originating from agricultural products (coconut fiber, coffee husk and rice husk) in the treatment of real radioactive liquid organic waste. Experiments with these biomass were made including 1) Preparation, activation and characterization of biomasses; 2) Conducting biosorption assays; and 3) Evaluation of the product of immobilization of biomasses in cement. The biomasses were tested in raw and activated forms. The activation was carried out with diluted HNO 3 and NaOH solutions. Biosorption assays were performed in polyethylene bottles, in which were added 10 mL of radioactive waste or waste dilutions in deionized water with the same pH and 2% of the biomass (w/v). At the end of the experiment, the biomass was separated by filtration and the remaining concentration of radioisotopes in the filtrate was determined by ICP-OES and gamma spectrometry. The studied waste contains natural uranium, americium-241 and cesium-137. The adopted contact times were 30 min, 1, 2 and 4 hours and the concentrations tested ranged between 10% and 100%. The results were evaluated by maximum experimental sorption capacity and isotherm and kinetics ternary models. The highest sorption capacity was observed with raw coffee husk, with approximate values of 2 mg/g of U (total), 40 x 10 -6 mg/g of Am-241 and 50 x10 -9

Biomonitoring of genotoxic risk in radar facility workers: comparison of the comet assay with micronucleus assay and chromatid breakage assay

International Nuclear Information System (INIS)

Garaj-Vrhovac, V.; Kopjar, N.

2003-01-01

Genotoxic risks of occupational exposure in a radar facility were evaluated by using alkaline comet assay, micronucleus assay and chromatid breakage assay on peripheral blood leukocytes in exposed subjects and corresponding controls. Results show that occupational exposure to microwave radiation correlates with an increase of genome damage in somatic cells. The levels of DNA damage in exposed subjects determined by using alkaline comet assay were increased compared to control and showed interindividual variations. Incidence of micronuclei was also significantly increased compared to baseline control values. After short exposure of cultured lymphocytes to bleomycin, cells of occupationally exposed subjects responded with high numbers of chromatid breaks. Although the level of chromosome damage generated by bleomycin varied greatly between individuals, in exposed subjects a significantly elevated number of chromatid breaks was observed. Our results support data reported in literature indicating that microwave radiation represents a potential DNA-damaging hazard. Alkaline comet assay is confirmed as a sensitive and highly reproducible technique for detection of primary DNA damage inflicted in somatic cells. Micronucleus assay was confirmed as reliable bio-markers of effect and chromatid breakage assay as sensitive bio-marker of individual cancer susceptibility. The results obtained also confirm the necessity to improve measures and to perform accurate health surveillance of individuals occupationally exposed to microwave radiation

Physico-chemical and toxicological assessment of liquid wastes from olive processing-related industries.

Science.gov (United States)

Pierantozzi, Pierluigi; Zampini, Catiana; Torres, Mariela; Isla, María I; Verdenelli, Romina A; Meriles, José M; Maestri, Damián

2012-01-30

In the last few years, agricultural uses of waste waters from olive processing-related industries have been gaining interest mainly with a view to composting or bio-fertilizers. The present work examines physico-chemical, toxicological and geno-toxicological properties of three liquid wastes, namely olive mill wastewater (OMWW), olive wet husk and olive brine. The effect of OMWW spreading on soil microbial activity and biomass was also evaluated. Data from Artemia salina and Lactuca sativa toxicity tests indicated high levels of lethality, and inhibitory effects on seed germination and seedling growth of all olive wastes. The genotoxicity assays using Allium cepa tests showed contrasting results. At high concentrations, olive wastes caused inhibition or suppression of mitosis. However, they did not produce induced anaphase aberrations. Data on reversion of Salmonella thyphimurium strains using the Ames test indicated that the olive wastes did not present mutagenic activity. Results from the field experiment showed that OMWW at a 500 m(3) ha(-1) had the highest values of both soil microbial activity and biomass after 3 months of the amendment application. This work adds new data for environmental risk assessment of olive industrial wastes. Direct use of olive wastes for agricultural purposes should be limited owing to their possible chemotoxic, phytotoxic and antimicrobial effects. Copyright © 2011 Society of Chemical Industry.

Application of macrophytes as biosorbents for radioactive liquid waste treatment

International Nuclear Information System (INIS)

Vieira, Ludmila Cabreira

2016-01-01

Radioactive waste as any other type of waste should be treated and disposed adequately. It is necessary to consider its physical, chemical and radiological characteristics for choosing the appropriate action for the treatment and final disposal. Many treatment techniques currently used are economically costly, often invalidating its use and favoring the study of other treatment techniques. One of these techniques is biosorption, which demonstrates high potential when applied to radioactive waste. This technology uses materials of biological origin for removing metals. Among potential biosorbents found, macrophyte aquatics are useful because they may remove uranium present in the liquid radioactive waste at low cost. This study aims to evaluate the biosorption capacity of macrophyte aquatics Pistia stratiotes, Limnobium laevigatum, Lemna sp and Azolla sp in the treatment of liquid radioactive waste. This study was divided into two stages, the first one is characterization and preparation of biosorption and the other is tests, carried out with uranium solutions and real samples. The biomass was tested in its raw form and biosorption assays were performed in polypropylene vials containing 10 ml of solution of uranium or 10ml of radioactive waste and 0.20g of biomass. The behavior of biomass was evaluated by sorption kinetics and isotherm models. The highest sorption capacities found was 162.1 mg / g for the macrophyte Lemna sp and 161.8 mg / g for the Azolla sp. The equilibrium times obtained were 1 hour for Lemna sp, and 30 minutes for Azolla sp. With the real waste, the macrophyte Azolla sp presented a sorption capacity of 2.6 mg / g. These results suggest that Azolla sp has a larger capacity of biosorption, therefore it is more suitable for more detailed studies of treatment of liquid radioactive waste. (author)

Wet oxidation pre-treatment of woody yard waste: Parameter optimization and enzymatic digestibility for ethanol production

DEFF Research Database (Denmark)

Lissens, G.; Klinke, H.B.; Verstraete, W.

2004-01-01

, 58-67% and 80-83% of the cellulose and hemicellulose contained in the waste were converted into monomeric sugars. The cellulose conversion efficiency during a simultaneous saccharification and fermentation (SSF) assay at 10% DM was 79% for the highest enzyme loading (25 FPU g(-1) DM) while 69...

Assay strategies and methods for phospholipases

International Nuclear Information System (INIS)

Reynolds, L.J.; Washburn, W.N.; Deems, R.A.; Dennis, E.A.

1991-01-01

Of the general considerations discussed, the two issues which are most important in choosing an assay are (1) what sensitivity is required to assay a particular enzyme and (2) whether the assay must be continuous. One can narrow the options further by considering substrate availability, enzyme specificity, assay convenience, or the presence of incompatible side reactions. In addition, the specific preference of a particular phospholipase for polar head group, micellar versus vesicular substrates, and anionic versus nonionic detergents may further restrict the options. Of the many assays described in this chapter, several have limited applicability or serious drawbacks and are not commonly employed. The most commonly used phospholipase assays are the radioactive TLC assay and the pH-stat assay. The TLC assay is probably the most accurate, sensitive assay available. These aspects often outweigh the disadvantages of being discontinuous, tedious, and expensive. The radioactive E. coli assay has become popular recently as an alternative to the TLC assay for the purification of the mammalian nonpancreatic phospholipases. The assay is less time consuming and less expensive than the TLC assay, but it is not appropriate when careful kinetics are required. Where less sensitivity is needed, or when a continuous assay is necessary, the pH-stat assay is often employed. With purified enzymes, when free thiol groups are not present, a spectrophotometric thiol assay can be used. This assay is ∼ as sensitive as the pH-stat assay but is more convenient and more reproducible, although the substrate is not available commercially. Despite the many assay choices available, the search continues for a convenient, generally applicable assay that is both sensitive and continuous

Valorization of Bone Waste of Saudi Arabia by Synthesizing Hydroxyapatite.

Science.gov (United States)

Amna, Touseef

2018-05-09

At present, hydroxyapatite is being frequently used for diverse biomedical applications as it possesses excellent biocompatibility, osteoconductivity, and non-immunogenic characteristics. The aim of the present work was to recycle bone waste for synthesis of hydroxyapatite nanoparticles to be used as bone extracellular matrix. For this reason, we for the first time utilized bio-waste of cow bones of Albaha city. The residual bones were utilized for the extraction of natural bone precursor hydroxyapatite. A facile scientific technique has been used to synthesize hydroxyapatite nanoparticles through calcinations of wasted cow bones without further supplementation of chemicals/compounds. The obtained hydroxyapatite powder was ascertained using physicochemical techniques such as XRD, SEM, FTIR, and EDX. These analyses clearly show that hydroxyapatite from native cow bone wastes is biologically and physicochemically comparable to standard hydroxyapatite, commonly used for biomedical functions. The cell viability and proliferation over the prepared hydroxyapatite was confirmed with CCk-8 colorimetric assay. The morphology of the cells growing over the nano-hydroxyapatite shows that natural hydroxyapatite promotes cellular attachment and proliferation. Hence, the as-prepared nano-hydroxyapatite can be considered as cost-effective source of bone precursor hydroxyapatite for bone tissue engineering. Taking into account the projected demand for reliable bone implants, the present research work suggested using environment friendly methods to convert waste of Albaha city into nano-hydroxyapatite scaffolds. Therefore, besides being an initial step towards accomplishment of projected demands of bone implants in Saudi Arabia, our study will also help in reducing the environmental burden by recycling of bone wastes of Albaha city.

Treatment of supermarket vegetable wastes to be used as alternative substrates in bioprocesses.

Science.gov (United States)

Díaz, Ana Isabel; Laca, Amanda; Laca, Adriana; Díaz, Mario

2017-09-01

Fruits and vegetables have the highest wastage rates at retail and consumer levels. These wastes have promising potential for being used as substrates in bioprocesses. However, an effective hydrolysis of carbohydrates that form these residues has to be developed before the biotransformation. In this work, vegetable wastes from supermarket (tomatoes, green peppers and potatoes) have been separately treated by acid, thermal and enzymatic hydrolysis processes in order to maximise the concentration of fermentable sugars in the final broth. For all substrates, thermal and enzymatic processes have shown to be the most effective. A new combined hydrolysis procedure including these both treatments was also assayed and the enzymatic step was successfully modelled. With this combined hydrolysis, the percentage of reducing sugars extracted was increased, in comparison with the amount extracted from non-hydrolysed samples, approximately by 30% in the case of tomato and green peeper wastes. For potato wastes this percentage increased from values lower than 1% to 77%. In addition, very low values of fermentation inhibitors were found in the final broth. Copyright © 2017. Published by Elsevier Ltd.

Waste acceptance and waste loading for vitrified Oak Ridge tank waste

International Nuclear Information System (INIS)

Harbour, J.R.; Andrews, M.K.

1997-01-01

The Office of Science and Technology of the DOE has funded a joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) to evaluate vitrification and grouting for the immobilization of sludge from ORNL tank farms. The radioactive waste is from the Gunite and Associated Tanks (GAAT), the Melton Valley Storage Tanks (MVST), the Bethel Valley Evaporator Service Tanks (BVEST), and the Old Hydrofractgure Tanks (OHF). Glass formulation development for sludge from these tanks is discussed in an accompanying article for this conference (Andrews and Workman). The sludges contain transuranic radionuclides at levels which will make the glass waste form (at reasonable waste loadings) TRU. Therefore, one of the objectives for this project was to ensure that the vitrified waste form could be disposed of at the Waste Isolation Pilot Plant (WIPP). In order to accomplish this, the waste form must meet the WIPP Waste Acceptance Criteria (WAC). An alternate pathway is to send the glass waste forms for disposal at the Nevada Test Site (NTS). A sludge waste loading in the feed of 6 wt percent will lead to a waste form which is non-TRU and could potentially be disposed of at NTS. The waste forms would then have to meet the requirements of the NTS WAC. This paper presents SRTC''s efforts at demonstrating that the glass waste form produced as a result of vitrification of ORNL sludge will meet all the criteria of the WIPP WAC or NTS WAC

EXAMPLE OF A RISK-BASED DISPOSAL APPROVAL: SOLIDIFICATION OF HANFORD SITE TRANSURANIC (TRU) WASTE

International Nuclear Information System (INIS)

PRIGNANO AL

2007-01-01

The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained polychlorinated biphenyls (PCBs) regulated under TSCA. The prescribed disposal method for liquid PCB waste under TSCA regulations is either thermal treatment or decontamination. Due to the radioactive nature of the waste, however, neither thermal treatment nor decontamination was a viable option. As a result, the proposed treatment consisted of solidifying the material to comply with waste acceptance criteria at the Waste Isolation Pilot Plant (WPP) in Carlsbad, New Mexico, or possibly the Environmental Restoration Disposal Facility at the Hanford Site, depending on the resulting transuranic (TRU) content of the stabilized waste. The RBDA evaluated environmental risks associated with potential airborne PCBs. In addition, the RBDA made use of waste management controls already in place at the treatment unit. The treatment unit, the T Plant Complex, is a Resource Conservation and Recovery Act of 1976 (RCRA)-permitted facility used for storing and treating radioactive waste. The EPA found that the proposed activities did not pose an unreasonable risk to human health or the environment. Treatment took place from October 26,2005 to June 9,2006, and 332 208-liter (55-gallon) containers of solidified waste were produced. All treated drums assayed to date are TRU and will be disposed at WIPP

IMPROVEMENTS IN CONTAINER MANAGEMENT OF TRANSURANIC (TRU) AND LOW LEVEL RADIOACTIVE WASTE STORED AT THE CENTRAL WASTE COMPLEX (CWC) AT HANFORD

International Nuclear Information System (INIS)

UYTIOCO EM

2007-01-01

The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation and Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE'S) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at the Site, with minor quantities of newly generated waste from on-site and off-site waste generators. The CWC comprises 18 storage buildings that house 13,000 containers. Each waste container within the facility is scanned into its location by building, module, tier and position and the information is stored in a site-wide database. As waste is retrieved from the burial grounds, a preliminary non-destructive assay is performed to determine if the waste is transuranic (TRU) or low-level waste (LLW) and subsequently shipped to the CWC. In general, the TRU and LLW waste containers are stored in separate locations within the CWC, but the final disposition of each waste container is not known upon receipt. The final disposition of each waste container is determined by the appropriate program as process knowledge is applied and characterization data becomes available. Waste containers are stored within the CWC based on their physical chemical and radiological hazards. Further segregation within each building is done by container size (55-gallon, 85-gallon, Standard Waste Box) and waste stream. Due to this waste storage scheme, assembling waste containers for shipment out of the CWC has been time consuming and labor intensive. Qualitatively, the ratio of containers moved to containers in the outgoing shipment has been excessively high, which correlates to additional worker exposure, shipment delays, and operational inefficiencies. These inefficiencies impacted the LLW Program's ability to meet commitments established by the Tri-Party Agreement, an agreement between the State of Washington

Evaluation of antioxidant potential of Artocarpus heterophyllus L. J33 variety fruit waste from different extraction methods and identification of phenolic constituents by LCMS.