WorldWideScience

Sample records for facility development efforts

  1. States and compacts: Issues and events affecting facility development efforts, including the Barnwell opening

    Energy Technology Data Exchange (ETDEWEB)

    Larson, G.S.

    1995-12-31

    Ten years have passed since the first regional low-level radioactive waste compacts received Congressional consent and initiated their efforts to develop new disposal capacity. During these 10 years, both significant achievements and serious setbacks have marked our efforts and affect our current outlook. Recent events in the waste marketplace, particularly in the operating status of the Barnwell disposal facility, have now raised legitimate questions about the continued rationale for the regional framework that grew out of the original legislation enacted by Congress in 1980. At the same time, licensing activities for new regional disposal facilities are under way in three states, and a fourth awaits the final go-ahead to begin construction. Uncertainty over the meaning and reliability of the marketplace events makes it difficult to gauge long-term implications. In addition, differences in the status of individual state and compact facility development efforts lead to varying assessments of the influence these events will, or should, have on such efforts.

  2. States and compacts: Issues and events affecting facility development efforts, including the Barnwell opening

    International Nuclear Information System (INIS)

    Larson, G.S.

    1995-01-01

    Ten years have passed since the first regional low-level radioactive waste compacts received Congressional consent and initiated their efforts to develop new disposal capacity. During these 10 years, both significant achievements and serious setbacks have marked our efforts and affect our current outlook. Recent events in the waste marketplace, particularly in the operating status of the Barnwell disposal facility, have now raised legitimate questions about the continued rationale for the regional framework that grew out of the original legislation enacted by Congress in 1980. At the same time, licensing activities for new regional disposal facilities are under way in three states, and a fourth awaits the final go-ahead to begin construction. Uncertainty over the meaning and reliability of the marketplace events makes it difficult to gauge long-term implications. In addition, differences in the status of individual state and compact facility development efforts lead to varying assessments of the influence these events will, or should, have on such efforts

  3. Examining Regionalization Efforts to Develop Lessons Learned and Consideration for Department of Defense Medical Facilities

    Science.gov (United States)

    2017-03-23

    outsourcing effects of military maintenance depots. They found maintenance depots were not working at full capacity and in some cases privatizing the...need to look at the impact of the consolidated departments and if a common goal can be achieved. Funding differences can also affect regionalization...therefore be out of service until fixed. Mitchell & Pasch [5] added that there could be a customer service impact consolidating local facilities into

  4. Program management plan for development, demonstration, testing, and evaluation efforts associated with Oak Ridge Reservation's Land Disposal Restrictions Federal Facility Compliance Agreement

    International Nuclear Information System (INIS)

    Conley, T.B.

    1994-04-01

    This program management plan covers the development, demonstration, testing, and evaluation efforts necessary to identify treatment methods for all the waste listed in Appendix B of the ORR's LDR/FFCA as well as any new wastes which meet Appendix B criteria. To successfully identify a treatment method, at least a proof-of-principle level of understanding must be obtained: that is, the candidate processes must be demonstrated as effective in treating the wastes to the LDR; however, an optimized process is not required. Where applicable and deemed necessary and where the budgets will support them, pilot-scale demonstrations will be pursued. The overall strategy being adopted in this program will be composed of the following activities: Scoping of the study; characterization; development and screening of alternatives; treatability investigations; and detailed analysis of alternatives

  5. Superconducting cavities developments efforts at RRCAT

    International Nuclear Information System (INIS)

    Puntambekar, A.; Bagre, M.; Dwivedi, J.; Shrivastava, P.; Mundra, G.; Joshi, S.C.; Potukuchi, P.N.

    2011-01-01

    Superconducting RE cavities are the work-horse for many existing and proposed linear accelerators. Raja Ramanna Centre for Advanced Technology (RRCAT) has initiated a comprehensive R and D program for development of Superconducting RF cavities suitable for high energy accelerator application like SNS and ADS. For the initial phase of technology demonstration several prototype 1.3 GHz single cell-cavities have been developed. The work began with development of prototype single cell cavities in aluminum and copper. This helped in development of cavity manufacturing process, proving various tooling and learning on various mechanical and RF qualification processes. The parts manufacturing was done at RRCAT and Electron beam welding was carried out at Indian industry. These cavities further served during commissioning trials for various cavity processing infrastructure being developed at RRCAT and are also a potential candidate for Niobium thin film deposition R and D. Based on the above experience, few single cell cavities were developed in fine grain niobium. The critical technology of forming and machining of niobium and the intermediate RF qualification were developed at RRCAT. The EB welding of bulk niobium cavities was carried out in collaboration with IUAC, New Delhi at their facility. As a next logical step efforts are now on for development of multicell cavities. The prototype dumbbells and end group made of aluminium, comprising of RF and HOM couplers ports have also been developed, with their LB welding done at Indian industry. In this paper we shall present the development efforts towards manufacturing of 1.3 GHz single cell cavities and their initial processing and qualification. (author)

  6. Power Systems Development Facility

    International Nuclear Information System (INIS)

    1993-06-01

    The objective of the PSDF would be to provide a modular facility which would support the development of advanced, pilot-scale, coal-based power systems and hot gas clean-up components. These pilot-scale components would be designed to be large enough so that the results can be related and projected to commercial systems. The facility would use a modular approach to enhance the flexibility and capability for testing; consequently, overall capital and operating costs when compared with stand-alone facilities would be reduced by sharing resources common to different modules. The facility would identify and resolve technical barrier, as well as-provide a structure for long-term testing and performance assessment. It is also intended that the facility would evaluate the operational and performance characteristics of the advanced power systems with both bituminous and subbituminous coals. Five technology-based experimental modules are proposed for the PSDF: (1) an advanced gasifier module, (2) a fuel cell test module, (3) a PFBC module, (4) a combustion gas turbine module, and (5) a module comprised of five hot gas cleanup particulate control devices. The final module, the PCD, would capture coal-derived ash and particles from both the PFBC and advanced gasifier gas streams to provide for overall particulate emission control, as well as to protect the combustion turbine and the fuel cell

  7. Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2009-01-31

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, has routinely demonstrated gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This final report summarizes the results of the technology development work conducted at the PSDF through January 31, 2009. Twenty-one major gasification test campaigns were completed, for a total of more than 11,000 hours of gasification operation. This operational experience has led to significant advancements in gasification technologies.

  8. MACCS2 development and verification efforts

    International Nuclear Information System (INIS)

    Young, M.; Chanin, D.

    1997-01-01

    MACCS2 represents a major enhancement of the capabilities of its predecessor MACCS, the MELCOR Accident Consequence Code System. MACCS, released in 1987, was developed to estimate the potential impacts to the surrounding public of severe accidents at nuclear power plants. The principal phenomena considered in MACCS/MACCS2 are atmospheric transport and deposition under time-variant meteorology, short-term and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs. MACCS2 was developed as a general-purpose analytical tool applicable to diverse reactor and nonreactor facilities. The MACCS2 package includes three primary enhancements: (1) a more flexible emergency response model, (2) an expanded library of radionuclides, and (3) a semidynamic food-chain model. In addition, errors that had been identified in MACCS version1.5.11.1 were corrected, including an error that prevented the code from providing intermediate-phase results. MACCS2 version 1.10 beta test was released to the beta-test group in May, 1995. In addition, the University of New Mexico (UNM) has completed an independent verification study of the code package. Since the beta-test release of MACCS2 version 1.10, a number of minor errors have been identified and corrected, and a number of enhancements have been added to the code package. The code enhancements added since the beta-test release of version 1.10 include: (1) an option to allow the user to input the σ y and σ z plume expansion parameters in a table-lookup form for incremental downwind distances, (2) an option to define different initial dimensions for up to four segments of a release, (3) an enhancement to the COMIDA2 food-chain model preprocessor to allow the user to supply externally calculated tables of tritium food-chain dose per unit deposition on farmland to support analyses of tritium releases, and (4) the capability to calculate direction-dependent doses

  9. Technology Development Facility (TDF)

    International Nuclear Information System (INIS)

    Doggett, J.N.

    1982-01-01

    We have been studying small, driven, magnetic-mirror-based fusion reactors for the Technology Development Facility (TDF), that will test fusion reactor materials, components, and subsystems. Magnetic mirror systems are particularly interesting for this application because of their inherent steady-state operation, potentially high neutron wall loading, and relatively small size. Our design is a tandem mirror device first described by Fowler and Logan, based on the physics of the TMX experiments at Lawrence Livermore National Laboratory (LLNL). The device produces 20 MW of fusion power with a first-wall, uncollided 14-MeV neutron flux of 1.4 MW/m 2 on an area of approximately 8 m 2 , while consuming approximately 250 MW of electrical power. The work was done by a combined industrial-laboratory-university group

  10. National Ignition Facility frequency converter development

    International Nuclear Information System (INIS)

    Barker, C.E.; Auerbach, J.M.; Adams, C.H.

    1996-01-01

    A preliminary error budget for the third harmonic converter for the National Ignition Facility (NIF) laser driver has been developed using a root-sum-square-accumulation of error sources. Such a budget sets an upper bound on the allowable magnitude of the various effects that reduce conversion efficiency. Development efforts on crystal mounting technology and crystal quality studies are discussed

  11. Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    None

    2003-07-01

    This report discusses Test Campaign TC12 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (SW) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). While operating as a gasifier, either air or oxygen can be used as the oxidant. Test run TC12 began on May 16, 2003, with the startup of the main air compressor and the lighting of the gasifier start-up burner. The Transport Gasifier operated until May 24, 2003, when a scheduled outage occurred to allow maintenance crews to install the fuel cell test unit and modify the gas clean-up system. On June 18, 2003, the test run resumed when operations relit the start-up burner, and testing continued until the scheduled end of the run on July 14, 2003. TC12 had a total of 733 hours using Powder River Basin (PRB) subbituminous coal. Over the course of the entire test run, gasifier temperatures varied between 1,675 and 1,850 F at pressures from 130 to 210 psig.

  12. Facility planning and site development

    International Nuclear Information System (INIS)

    Reisman, R.C.; Handmaker, H.

    1986-01-01

    Planning for a magnetic resonance imaging (MRI) facility should provide for the efficient operation of current and future MRI devices and must also take into consideration a broad range of general planning principles. Control of budgeted facility costs and construction schedules is of increasing importance due to the magnitude of expense of MRI facility development as well as the need to protect institutional or entrepreneurial investment. In a competitive environment facility costs may be the determining factor in a project's success

  13. POWER SYSTEMS DEVELOPMENT FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Unknown

    2002-11-01

    This report discusses test campaign GCT4 of the Kellogg Brown & Root, Inc. (KBR) transport reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The transport reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using one of two possible particulate control devices (PCDs). The transport reactor was operated as a pressurized gasifier during GCT4. GCT4 was planned as a 250-hour test run to continue characterization of the transport reactor using a blend of several Powder River Basin (PRB) coals and Bucyrus limestone from Ohio. The primary test objectives were: Operational Stability--Characterize reactor loop and PCD operations with short-term tests by varying coal-feed rate, air/coal ratio, riser velocity, solids-circulation rate, system pressure, and air distribution. Secondary objectives included the following: Reactor Operations--Study the devolatilization and tar cracking effects from transient conditions during transition from start-up burner to coal. Evaluate the effect of process operations on heat release, heat transfer, and accelerated fuel particle heat-up rates. Study the effect of changes in reactor conditions on transient temperature profiles, pressure balance, and product gas composition. Effects of Reactor Conditions on Synthesis Gas Composition--Evaluate the effect of air distribution, steam/coal ratio, solids-circulation rate, and reactor temperature on CO/CO{sub 2} ratio, synthesis gas Lower Heating Value (LHV), carbon conversion, and cold and hot gas efficiencies. Research Triangle Institute (RTI) Direct Sulfur Recovery Process (DSRP) Testing--Provide syngas in support of the DSRP commissioning. Loop Seal Operations--Optimize loop seal operations and investigate increases to previously achieved maximum solids-circulation rate.

  14. EVA Training and Development Facilities

    Science.gov (United States)

    Cupples, Scott

    2016-01-01

    Overview: Vast majority of US EVA (ExtraVehicular Activity) training and EVA hardware development occurs at JSC; EVA training facilities used to develop and refine procedures and improve skills; EVA hardware development facilities test hardware to evaluate performance and certify requirement compliance; Environmental chambers enable testing of hardware from as large as suits to as small as individual components in thermal vacuum conditions.

  15. Recent Ultrasonic Guided Wave Inspection Development Efforts

    International Nuclear Information System (INIS)

    Rose, Joseph L.; Tittmann, Bernhard R.

    2001-01-01

    The recognition of such natural wave guides as plates, rods, hollow cylinders, multi-layer structures or simply an interface between two materials combined with an increased understanding of the physics and wave mechanics of guided wave propagation has led to a significant increase in the number of guided wave inspection applications being developed each year. Of primary attention Is the ability to inspect partially hidden structures, hard to access areas, and treated or insulated structures. An introduction to some physical consideration of guided waves followed by some sample problem descriptions in pipe, ice detection, fouling detection in the foods industry, aircraft, tar coated structures and acoustic microscopy is presented in this paper. A sample problem in Boundary Element Modeling is also presented to illustrate the move in guided wave analysis beyond detection and location analysis to quantification

  16. Organizing the HIV vaccine development effort.

    Science.gov (United States)

    Voronin, Yegor; Snow, William

    2013-09-01

    To describe and compare the diverse organizational structures and funding mechanisms applied to advance HIV preventive vaccine research and development and to help explain and inform evolving infrastructures and collaborative funding models. On the basis of models that have been tried, improved or abandoned over three decades, the field seems to have settled into a relatively stable set of diverse initiatives, each with its own organizational signature. At the same time, this set of organizations is forging cross-organizational collaborations, which promise to acquire newly emergent beneficial properties. Strong motivation to expedite HIV vaccine R&D has driven a diversity of customized and inventive organizational approaches, largely government and foundation funded. Although no one approach has proven a panacea, the field has evolved into a constellation of often overlapping organizations that complement or reinforce one another. The Global HIV Vaccine Enterprise, a responsive, rapidly evolving loose infrastructure, is an innovative collaboration to catalyze that evolution.

  17. Pollution control and environmental monitoring efforts at DOE's Coal-Fired Flow Facility

    International Nuclear Information System (INIS)

    Attig, R.C.; Crawford, L.W.; Lynch, T.P.; Sheth, A.C.

    1991-01-01

    Proof-of-Concept (POC) scale demonstration of such technology is currently being carried out at the US Department of Energy's (DOE's) Coal-Fired Flow Facility (CFFF), located at The University of Tennessee Space Institute (UTSI) in Tullahoma, Tennessee and at the Component Development and Integration Facility in Butte, Montana. The CFFF is dedicated to the evaluation of downstream (steam cycle) components and technology that may be considered for a full-scale MHD system. The objectives of the CFFF testing include the demonstration of various pollution control devices and techniques at a scale sufficient for future scale-up. The CFFF offers a unique test environment in which emissions control techniques can be developed and evaluated through emissions and environmental monitoring. Results thus far have demonstrated the ability of sulfur oxide (SO x ), nitrogen oxide (NO x ) and particulate emissions well below the New Source Performance Standards (NSPS). Regeneration of the potassium sulfate to produce sulfur-free compounds also has been demonstrated. The experimental program at the CFFF is now aimed at determining the optimum conditions for future commercial scale designs. Because of increased interests in Air Toxics, measurements of nitrous oxide (N 2 O), a potential greenhouse gas, priority pollutants (inorganic as well as organics), and chlorine-containing species (Cl 2 and HCl) are also included in our ongoing efforts. Environmental monitoring activities are being pursued to develop an environmental impact assessment data base. These include the use of three ambient air sites to determine the impacts of gaseous and particulate emissions, five lake water sites to determine impacts due to process water discharges and seven sites to collect terrestrial data on possible soil contamination and tree growth. In this paper, we will summarize the status of our ongoing environmental program. 16 refs., 15 figs., 3 tabs

  18. Development Efforts Of Oil Companies As Perceived By Rural ...

    African Journals Online (AJOL)

    ... that the host communities are highly satisfied with companies' efforts (projects and services) to them. Based on these findings, recommendations were made. Key words: Oil producing communities; oil exploration/production; company's development efforts; Journal of Agriculture and Social Research Vol.4(1) 2004: 60-71 ...

  19. AMRDEC's HWIL Synthetic Environment Development Efforts for LADAR Sensors

    National Research Council Canada - National Science Library

    Kim, Hajin J; Cornell, Michael C; Naumann, Charles B

    2004-01-01

    .... With the emerging sensor/electronics technology LADAR sensors are becoming more viable option as an integral part of weapon systems, and AMCOM has been expending efforts to develop the capabilities...

  20. Preliminary design for a maglev development facility

    Energy Technology Data Exchange (ETDEWEB)

    Coffey, H.T.; He, J.L.; Chang, S.L.; Bouillard, J.X.; Chen, S.S.; Cai, Y.; Hoppie, L.O.; Lottes, S.A.; Rote, D.M. (Argonne National Lab., IL (United States)); Zhang, Z.Y. (Polytechnic Univ., Brooklyn, NY (United States)); Myers, G.; Cvercko, A. (Sterling Engineering, Westchester, IL (United States)); Williams, J.R. (Alfred Benesch and Co., Chicago, IL (United States))

    1992-04-01

    A preliminary design was made of a national user facility for evaluating magnetic-levitation (maglev) technologies in sizes intermediate between laboratory experiments and full-scale systems. A technical advisory committee was established and a conference was held to obtain advice on the potential requirements of operational systems and how the facility might best be configured to test these requirements. The effort included studies of multiple concepts for levitating, guiding, and propelling maglev vehicles, as well as the controls, communications, and data-acquisition and -reduction equipment that would be required in operating the facility. Preliminary designs for versatile, dual 2-MVA power supplies capable of powering attractive or repulsive systems were developed. Facility site requirements were identified. Test vehicles would be about 7.4 m (25 ft) long, would weigh form 3 to 7 metric tons, and would operate at speeds up to 67 m/s (150 mph) on a 3.3-km (2.05-mi) elevated guideway. The facility would utilize modular vehicles and guideways, permitting the substitution of levitation, propulsion, and guideway components of different designs and materials for evaluation. The vehicle would provide a test cell in which individual suspension or propulsion components or subsystems could be tested under realistic conditions. The system would allow economical evaluation of integrated systems under varying weather conditions and in realistic geometries.

  1. 48 CFR 35.009 - Subcontracting research and development effort.

    Science.gov (United States)

    2010-10-01

    ... ACQUISITION REGULATION SPECIAL CATEGORIES OF CONTRACTING RESEARCH AND DEVELOPMENT CONTRACTING 35.009 Subcontracting research and development effort. Since the selection of R&D contractors is substantially based on... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Subcontracting research...

  2. Effect of Community Engagement Interventions on Patient Safety and Risk Reduction Efforts in Primary Health Facilities: Evidence from Ghana.

    Directory of Open Access Journals (Sweden)

    Robert Kaba Alhassan

    Full Text Available Patient safety and quality care remain major challenges to Ghana's healthcare system. Like many health systems in Africa, this is largely because demand for healthcare is outstripping available human and material resource capacity of healthcare facilities and new investment is insufficient. In the light of these demand and supply constraints, systematic community engagement (SCE in healthcare quality assessment can be a feasible and cost effective option to augment existing quality improvement interventions. SCE entails structured use of existing community groups to assess healthcare quality in health facilities. Identified quality gaps are discussed with healthcare providers, improvements identified and rewards provided if the quality gaps are closed.This paper evaluates whether or not SCE, through the assessment of health service quality, improves patient safety and risk reduction efforts by staff in healthcare facilities.A randomized control trail was conducted in 64 primary healthcare facilities in the Greater Accra and Western regions of Ghana. Patient risk assessments were conducted in 32 randomly assigned intervention and control facilities. Multivariate multiple regression test was used to determine effect of the SCE interventions on staff efforts towards reducing patient risk. Spearman correlation test was used to ascertain associations between types of community groups engaged and risk assessment scores of healthcare facilities.Clinic staff efforts towards increasing patient safety and reducing risk improved significantly in intervention facilities especially in the areas of leadership/accountability (Coef. = 10.4, p<0.05 and staff competencies (Coef. = 7.1, p<0.05. Improvement in service utilization and health resources could not be attributed to the interventions because these were outside the control of the study and might have been influenced by institutional or national level developments between the baseline and follow-up period

  3. Developing standardized facility contingency plans

    International Nuclear Information System (INIS)

    Davidson, D.A.

    1993-01-01

    Texaco consists of several operating departments that are, in effect, independent companies. Each of these departments is responsible for complying with all environmental laws and regulations. This includes the preparation by each facility to respond to an oil spill at that location. For larger spills, however, management of the response will rest with corporate regional response teams. Personnel from all departments make up the regional teams. In 1990, Congress passed the Oil Pollution Act. In 1991, the US Coast Guard began developing oil spill response contingency plan regulations, which they are still working on. Meanwhile, four of the five west coast states have also passed laws requiring contingency plans. (Only Hawaii has chosen to wait and see what the federal regulations will entail). Three of the states have already adopted regulations. Given these laws and regulations, along with its corporate structure, Texaco addressed the need to standardize local facility plans as well as its response organization. This paper discusses how, by working together, the Texaco corporate international oil spill response staff and the Texaco western region on-scene commander developed: A standard contingency plan format crossing corporate boundaries and meeting federal and state requirements. A response organization applicable to any size facility or spill. A strategy to sell the standard contingency plan and response organization to the operating units

  4. Efforts towards the development of recombinant Vaccines against ...

    African Journals Online (AJOL)

    Hemorrhagic septicemia is caused by gram-negative bacterium of Pasteurella multocida (P. multocida) strains. Most of the current vaccines against P. multocida have shortcomings. Presently, there is increasing efforts towards construction of recombinant clone for vaccine development against P. multocida. In this review an ...

  5. Efforts Towards The Development Of Recombinant Vaccines Against

    African Journals Online (AJOL)

    ABSTRACT. Hemorrhagic septicemia is caused by gram-negative bacterium of Pasteurella multocida (P. multocida) strains. Most of the current vaccines against P. multocida have shortcomings. Presently, there is increasing efforts towards construction of recombinant clone for vaccine development against P. multocida.

  6. Detector development and test facility

    International Nuclear Information System (INIS)

    Reeder, D.D.

    1993-01-01

    Following the ideas presented in the proposal to the DoE, we have begun to acquire the equipment needed to design, develop construct and test the electronic and mechanical features of detectors used in High Energy Physics Experiments. A guiding principle for the effort is to achieve integrated electronic and mechanical designs which meet the demanding specifications of the modern hadron collider environment yet minimize costs. This requires state of the art simulation of signal processing as well as detailed calculations of heat transfer and finite element analysis of structural integrity

  7. A successful effort to involve stakeholders in a facility siting decision using LIPS with stakeholder involvement

    International Nuclear Information System (INIS)

    Merkhofer, L.; Conway, R.; Anderson, B.

    1995-01-01

    Local public opposition to federal bureaucratic decisions has resulted in public agencies rethinking the role of stakeholders in decision making. Efforts to include stakeholders directly in the decision-making process are on the increase. Unfortunately, many attempts to involve members of the public in decisions involving complex technical issues have failed. A key problem has been defining a meaningful role for the public in the process of arriving at a technical decision. This paper describes a successful effort by Sandia National Laboratories (SNL) in New Mexico to involve stakeholders in an important technical decision associated with its Environmental Restoration (ER) Project. The decision was where to locate a Corrective Action Management Unit (CAMU), a facility intended to consolidate and store wastes generated from the cleanup of hazardous waste sites. A formal priority setting process known as the Laboratory Integration Prioritization System (LIPS) was adapted to provide an approach for involving the public. Although rarely applied to stakeholder participation, the LIPS process proved surprisingly effective. It produced a consensus over a selected site and enhanced public trust and understanding of Project activities

  8. A multilateral effort to develop DNA vaccines against falciparum malaria.

    Science.gov (United States)

    Kumar, Sanjai; Epstein, Judith E; Richie, Thomas L; Nkrumah, Francis K; Soisson, Lorraine; Carucci, Daniel J; Hoffman, Stephen L

    2002-03-01

    Scientists from several organizations worldwide are working together to develop a multistage, multigene DNA-based vaccine against Plasmodium falciparum malaria. This collaborative vaccine development effort is named Multi-Stage DNA-based Malaria Vaccine Operation. An advisory board of international experts in vaccinology, malariology and field trials provides the scientific oversight to support the operation. This article discusses the rationale for the approach, underlying concepts and the pre-clinical development process, and provides a brief outline of the plans for the clinical testing of a multistage, multiantigen malaria vaccine based on DNA plasmid immunization technology.

  9. Examining human resources' efforts to develop a culturally competent workforce.

    Science.gov (United States)

    Whitman, Marilyn V; Valpuesta, Domingo

    2010-01-01

    The increasing diversification of the nation's population poses significant challenges in providing care that meets the needs of culturally diverse patients. Human resource management plays a vital role in developing a more culturally competent workforce. This exploratory study examines current efforts by human resource directors (HRDs) in Alabama's general hospitals to recruit more diverse candidates, train staff, and make language access resources available. A questionnaire was developed based on the Office of Minority Health's Culturally and Linguistically Appropriate Services standards. The HRDs of the 101 Alabama general hospitals served as the study's target population. A sample of 61 responses, or 60.4% of the population, was obtained. The findings indicate that most HRDs are focusing their efforts on recruiting racially/ethnically diverse candidates and training clerical and nursing staff to care for culturally and linguistically diverse patients. Less effort is being focused on recruiting candidates who speak a different language, and only 44.3% have a trained interpreter on the staff. The HRDs who indicated that they work closely with organizations that provide support to diverse groups were more likely to recruit diverse employees and have racially/ethnically and linguistically diverse individuals in leadership positions. It is crucial that health care organizations take the necessary steps to diversify their workforce to broaden access, improve the quality and equity of care, and capture a greater market share.

  10. Nondestructive assay system development for a plutonium scrap recovery facility

    International Nuclear Information System (INIS)

    Hsue, S.T.; Baker, M.P.

    1984-01-01

    A plutonium scrap recovery facility is being constructed at the Savannah River Plant (SRP). The safeguards groups of the Los Alamos National Laboratory have been working since the early design stage of the facility with SRP and other national laboratories to develop a state-of-the-art assay system for this new facility. Not only will the most current assay techniques be incorporated into the system, but also the various nondestructive assay (NDA) instruments are to be integrated with an Instrument Control Computer (ICC). This undertaking is both challenging and ambitious; an entire assay system of this type has never been done before in a working facility. This paper will describe, in particular, the effort of the Los Alamos Safeguards Assay Group in this endeavor. Our effort in this project can be roughly divided into three phases: NDA development, system integration, and integral testing. 6 references

  11. Estimation of total Effort and Effort Elapsed in Each Step of Software Development Using Optimal Bayesian Belief Network

    Directory of Open Access Journals (Sweden)

    Fatemeh Zare Baghiabad

    2017-09-01

    Full Text Available Accuracy in estimating the needed effort for software development caused software effort estimation to be a challenging issue. Beside estimation of total effort, determining the effort elapsed in each software development step is very important because any mistakes in enterprise resource planning can lead to project failure. In this paper, a Bayesian belief network was proposed based on effective components and software development process. In this model, the feedback loops are considered between development steps provided that the return rates are different for each project. Different return rates help us determine the percentages of the elapsed effort in each software development step, distinctively. Moreover, the error measurement resulted from optimized effort estimation and the optimal coefficients to modify the model are sought. The results of the comparison between the proposed model and other models showed that the model has the capability to highly accurately estimate the total effort (with the marginal error of about 0.114 and to estimate the effort elapsed in each software development step.

  12. Training development in Juzbado's Fuel Cycle Facility

    International Nuclear Information System (INIS)

    Perez, A.; Cunado, E.; Ortiz, D.

    2003-01-01

    In Juzbado's fuel cycle facility, because of the special activities developed, training is a very important issues. Training has been evolved, due to changes on the standards applicable each moment, and also due to the technological resources available. Both aspects have resulted in an evolution of the documents referred to training, such as training programs procedures, Radiation Protection Manual as well as the teaching methods. In the report we are going to present, we will show more precisely the changes that take place, referring to the different training methods used, present training sanitations, and the improvements already planned in training subjects as well as tools used, accomplishing with the legislation and improving in our effort of a better assimilation of the necessary knowledge. (Author)

  13. Overview of MACCS and MACCS2 development efforts

    International Nuclear Information System (INIS)

    Young, M.

    1996-01-01

    The MELCOR Accident Consequence Code System (MACCS), publicly distributed since 1987, was developed to estimate the potential impacts to the surrounding public of severe accidents at nuclear power plants. The principal phenomena considered in MACCS are atmospheric transport and deposition under time-variant meteorology, short-term and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs of mitigative actions. At this time, no other publicly available code in the US offers all these capabilities. MACCS2 represents a major enhancement of the capabilities of its predecessor MACCS. MACCS2 was developed as a general-purpose analytical tool applicable to diverse reactor and nonreactor Department of Energy (DOE) facilities. The MACCS2 package includes three primary enhancements: (1) a more flexible emergency response model, (2) an expanded library of radionuclides, and (3) a semidynamic food-chain model. The new code features allow detailed evaluations of risks to workers at nearby facilities on large DOE reservations and allow the user to assess the potential impacts of over 700 radionuclides that cannot be considered with MACCS

  14. Software Configuration Management For Multiple Releases: Influence On Development Effort

    Directory of Open Access Journals (Sweden)

    Sławomir P. Maludziński

    2007-01-01

    Full Text Available Software Configuration Management (SCM evolves together with the discipline of softwareengineering. Teams working on software products become larger and are geographically distributedat multiple sites. Collaboration between such groups requires well evaluated SCMplans and strategies to easy cooperation and decrease software development cost by reducingtime spent on SCM activities – branching and merging, that is effort utilized on creation ofrevisions (’serial’ versions and variants (’parallel’ versions. This paper suggests that SCMpractices should be combined with modular design and code refactoring to reduce cost relatedto maintenance of the same code line. Teams which produce several variants of thesame code line at the same time should use approaches like components, modularization, orplug-ins over code alternations maintained on version branches. Findings described in thispaper were taken by teams in charge of development of radio communication systems inMotorola GEMS divisions. Each team collaborating on similar projects used different SCMstrategies to develop parts of this system.

  15. Joint development effort Thermonuclear Fusion. Programme budgeting 1984

    International Nuclear Information System (INIS)

    1985-01-01

    The joint KfK and IPP project for the development of thermonuclear fusion device is established as the centerpiece of Federal German efforts in this field. It is meant to enhance the German contribution to the European programme and thus foster the chances of a joint European large-scale experiment to be started in the Federal Republic of Germany. IPP's tasks in the project are to study the physical principles and aspects, whereas KfK is responsible for the technological aspects. Work at IPP is focused on divertor experiments with the ASDEX series in order to go deeper into the problems that could not be solved by the JET experiments, namely those of the plasma boundary and control of impurities. Stellarator experiments are made in order to study the potentials of this toroidal confinement concept for steady-state operation. The IPP which always has been working in the plasma physics field devotes all activities to the joint effort. KfK has established a special project group for this purpose, PKF. The budgeting programme presented therefore covers the IPP entire working schedule, and that of PKF of the KfK. (orig./GG) [de

  16. Aum Shinrikyo’s Nuclear and Chemical Weapons Development Efforts

    Directory of Open Access Journals (Sweden)

    Andrea A. Nehorayoff

    2016-03-01

    Full Text Available This article details the terrorist activities of the Japanese cult, Aum Shinrikyo, from the perspective of its complex engineering efforts aimed at producing nuclear and chemical weapons. The experience of this millenarian organization illustrates that even violent non-state actors with considerable wealth and resources at their disposal face numerous obstacles to realizing their destructive aspirations. Specifically, Aum’s attempts at complex engineering were stymied by a combination of unchecked fantastical thinking, self-imposed ideological constraints, and a capricious leadership. The chapter highlights each of these mechanisms, as well as the specific ways in which they constrained the decision-making process and the implementation of the complex engineering tasks associated with their unconventional weapons development.

  17. Effort assessment in the development of information systems projects

    Directory of Open Access Journals (Sweden)

    Živadinović Jovan

    2015-01-01

    Full Text Available There is a great lack of methods and techniques in the software development process itself, as well as the lack of the appropriate tools that would make it more efficient. The significance of the problem is repeatedly emphasized by the need to ensure a high quality of software and software-based systems. The main objective of this work is to develop and systematize the original formal procedure for assessing the development of information systems in the early stages of the software life cycle, through metrics of the data model. We calculate the metrics of data model by using data that can be read off from a base data model, which is represented with an Entity-Relationship (ER diagram that is defined with four basic concepts: entities, relationships, attributes of entities or relationships and values. The idea is to present the complexity of the process with a function of a number of these concepts and a number of attributes for entity types. Assessment techniques represent the basis for planning and successful performance of software projects. Statistical method was used in this paper and these assessment processes go under the category of empirical parametric methods, although they have some characteristics of the expert estimation method. A developed assessment process represents a step in the efforts to reach suitable measures which we would use to assess the size and complexity of the data model and also to estimate the amount of costs and resources necessary for the development of information systems. Likewise, certain metrics are developed. By being familiar with the data model, we can use these metrics to quantify characteristics of an information system as a whole in the logic design phase. Suggested metrics were tested on specific models and the results are shown here.

  18. On the efforts (man-day) concerned with inspection in uranium fuel fabrication facility

    International Nuclear Information System (INIS)

    Watanabe, T.; Tanaka, T.; Seki, Y.

    1990-01-01

    Taking notice of inspection efforts (man·day) of STA·IAEA and those of MNF concerned with them, their change and various factors affecting the change have been studied. Namely, first, main topics concerning inspection in our Tokai plant are mentioned and secondly the relation between the inspection efforts and such factors as PIV period, number of items, number of DA sampling and NDA measurements, and so forth is studied. According to our study, though efforts of STA·IAEA and MNF required for both routine FLOW inspection and PIT have been nearly unchanged each year, our efforts for PIV have been increasing gradually. The factors relating to this increase of our efforts are the PIV period, inspection efforts of STA·IAEA for PIV and the number of DA sampling and NDA measurements. Finally, a suggestion on the future inspection system has been mentioned and then some items for improvement under the current inspection system have been exemplified. (author)

  19. The Effects of Response Effort on Safe Performance by Therapists at an Autism Treatment Facility

    Science.gov (United States)

    Casella, Sarah E.; Wilder, David A.; Neidert, Pamela; Rey, Catalina; Compton, Megan; Chong, Ivy

    2010-01-01

    The effects of response effort on safe behaviors (i.e., glove wearing, hand sanitizing, and electrical outlet replacement) exhibited by therapists at an autism treatment center were examined. Participants were exposed to 2 or 3 levels of effort (i.e., high, medium, low) for each dependent variable. Results showed increased safe performance during…

  20. Republic of Korea. Closure concept development for LILW disposal facility in Republic of Korea

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear Environment Technology Institute (NETEC) of Korea Electric Power Corporation (KEPCO) is developing near surface disposal concepts for both a rock cavern type disposal facility, and a vault type facility; two types of facility are being considered to provide more options for LILW repository siting. The conceptual design for the vault type facility will be completed in 1999. As a part of conceptual design effort, a preliminary concept for the disposal facility closure has been identified

  1. Main principles of development stationary training facilities

    International Nuclear Information System (INIS)

    Tsiptsyura, R.D.

    1986-01-01

    The designation of stationary training facilities is shown and the main requirements for them are formulated. When considering the above-mentioned requirements, special attention was paid to obligatory correspondence between training experience and practical skill of an operator. It is shown, that the switchboard block is the major unit of the training facility, which should develop skills and habits of an operator

  2. Efforts to Develop a 300°C Solder

    Energy Technology Data Exchange (ETDEWEB)

    Norann, Randy A [Perma Works LLC

    2015-01-25

    This paper covers the efforts made to find a 300°C electrical solder solution for geothermal well monitoring and logging tools by Perma Works LLC. This paper covers: why a high temperature solder is needed, what makes for a good solder, testing flux, testing conductive epoxy and testing intermetallic bonds. Future areas of research are suggested.

  3. Space facilities: Meeting future needs for research, development, and operations

    Science.gov (United States)

    The National Facilities Study (NFS) represents an interagency effort to develop a comprehensive and integrated long-term plan for world-class aeronautical and space facilities that meet current and projected needs for commercial and government aerospace research and development and space operations. At the request of NASA and the DOD, the National Research Council's Committee on Space Facilities has reviewed the space related findings of the NFS. The inventory of more than 2800 facilities will be an important resource, especially if it continues to be updated and maintained as the NFS report recommends. The data in the inventory provide the basis for a much better understanding of the resources available in the national facilities infrastructure, as well as extensive information on which to base rational decisions about current and future facilities needs. The working groups have used the inventory data and other information to make a set of recommendations that include estimates of cast savings and steps for implementation. While it is natural that the NFS focused on cost reduction and consolidations, such a study is most useful to future planning if it gives equal weight to guiding the direction of future facilities needed to satisfy legitimate national aspirations. Even in the context of cost reduction through facilities closures and consolidations, the study is timid about recognizing and proposing program changes and realignments of roles and missions to capture what could be significant savings and increased effectiveness. The recommendations of the Committee on Space Facilities are driven by the clear need to be more realistic and precise both in recognizing current incentives and disincentives in the aerospace industry and in forecasting future conditions for U.S. space activities.

  4. Development of cancer therapy facility of HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Jun, Byung Jin; Hwang, S. Y.; Kim, M. J. and others

    2000-04-01

    Facilities of the research and clinical treatments of neutron capture therapy using HANARO are developed, and they are ready to install. They are BNCT irradiation facility and prompt gamma neutron activatiion analysis facility. Since every horizontal neutron facility of HANARO is long and narrow tangential beam tube, it is analysed that sufficient epithermal neutrons for the BNCT cannot be obtained but sufficient thermal neutrons can be obtained by a filter composed of silicon and bismuth single crystals. Since the thermal neutron penetaration increases significantly when the crystals are cooled, a filter cooled by liquid nitrogen is developed. So as to avoid interference with the reactor operation, a water shutter is developed. The irradiation room is designed for the temporary surgical operation as well. Handling tools to remove activated beam port plug and to install water shutter and filter are developed. The basic structure of the irradiation room is already installed and most of other parts are ready to install. Since no free beam port is available for the prompt gamma neutron activation analysis, a method obtaining almost pure thermal neutrons by the vertical diffraction of extra beam for the polarized neutron spectrometer is developed. This method is confirmed by analysis and experiments to give high enough neutron beam. Equipment and devices are provided to install this facility.

  5. Development of cancer therapy facility of HANARO

    International Nuclear Information System (INIS)

    Jun, Byung Jin; Hwang, S. Y.; Kim, M. J. and others

    2000-04-01

    Facilities of the research and clinical treatments of neutron capture therapy using HANARO are developed, and they are ready to install. They are BNCT irradiation facility and prompt gamma neutron activatiion analysis facility. Since every horizontal neutron facility of HANARO is long and narrow tangential beam tube, it is analysed that sufficient epithermal neutrons for the BNCT cannot be obtained but sufficient thermal neutrons can be obtained by a filter composed of silicon and bismuth single crystals. Since the thermal neutron penetaration increases significantly when the crystals are cooled, a filter cooled by liquid nitrogen is developed. So as to avoid interference with the reactor operation, a water shutter is developed. The irradiation room is designed for the temporary surgical operation as well. Handling tools to remove activated beam port plug and to install water shutter and filter are developed. The basic structure of the irradiation room is already installed and most of other parts are ready to install. Since no free beam port is available for the prompt gamma neutron activation analysis, a method obtaining almost pure thermal neutrons by the vertical diffraction of extra beam for the polarized neutron spectrometer is developed. This method is confirmed by analysis and experiments to give high enough neutron beam. Equipment and devices are provided to install this facility

  6. Thermionic system evaluation test (TSET) facility construction: A United States and Russian effort

    International Nuclear Information System (INIS)

    Wold, S.K.

    1993-01-01

    The Thermionic System Evaluation Test (TSET) is a ground test of an unfueled Russian TOPAZ-II in-core thermionic space reactor powered by electric heaters. The facility that will be used for testing of the TOPAZ-II systems is located at the New Mexico Engineering Research Institute (NMERI) complex in Albuquerque, NM. The reassembly of the Russian test equipment is the responsibility of International Scientific Products (ISP), a San Jose, CA, company and Inertek, a Russian corporation, with support provided by engineers and technicians from Phillips Laboratory (PL), Sandia National Laboratories (SNL), Los Alamos National Laboratory (LANL), and the University of New Mexico (UNM). This test is the first test to be performed under the New Mexico Strategic Alliance agreement. This alliance consists of the PL, SNL, LANL, and UNM. The testing is being funded by the Strategic Defense Initiative Organization (SDIO) with the PL responsible for project execution

  7. A collaborative effort of medical and educational facilities for radiation safety training of nurses

    International Nuclear Information System (INIS)

    Matsuda, Naoki; Yoshida, Masahiro; Takao, Hideaki

    2005-01-01

    The proper understanding of radiation safety by nursing staffs in hospitals are essential not only for radiation protection of themselves against occupational radiation exposure but for quality nursing for patients who receive medical radiation exposure. The education program on radiation in nursing schools in Japan is, however, rather limited, and is insufficient for nurses to acquire basic knowledge of radiation safety and protection. Therefore, the radiation safety training of working nurses is quite important. A hospital-based training needs assignment of radiation technologists and radiologists as instructors, which may result in temporary shortage of these staffs for patients' services. Additionally, the equipments and facilities for radiation training in a hospital might not be satisfactory. In order to provide an effective education regarding radiation for working nurses, the radiation safety training course has been conducted for nurse of the university hospital by the collaboration of medical and educational staffs in Nagasaki University. This course was given for 6 hours in Radioisotope Research Center, a research and education facility for radiation workers using radioisotopes. The curriculum of this course included basics of radiation, effects of radiation on human health, procedures in clinical settings for radiation protection and practical training by using survey meters, which were mainly based on the radiation safety training for beginners according to the Japanese law concerning radiation safety with a modification to focus on medical radiation exposure. This course has been given to approximately 25 nurses in a time, and held 13 times in May 2000 through October 2003 for 317 nurse overall. The pre-instruction questionnaire revealed that 60% of nurses felt fears about radiation diagnosis or therapy, which reduced to less than 15% in the post-instruction surveillance. The course also motivated nurses to give an answer to patients' questions about

  8. Upper Stage Flight Experiment (USFE) Integral Structure Development Effort

    National Research Council Canada - National Science Library

    Guerrero, Jim; Hamilton, Brent; Burton, Randy; Crockett, Dave; Taylor, Zach

    2004-01-01

    .... AFRL/VS is developing a wide range of tank concepts that include linerless cryogenic tankage, self-healing cryogenic tankage, hydrogen peroxide compatible tankage, volumetrically efficient toroidal (donut shaped...

  9. Development of a Medical Cyclotron Production Facility

    Science.gov (United States)

    Allen, Danny R.

    2003-08-01

    Development of a Cyclotron manufacturing facility begins with a business plan. Geographics, the size and activity of the medical community, the growth potential of the modality being served, and other business connections are all considered. This business used the customer base established by NuTech, Inc., an independent centralized nuclear pharmacy founded by Danny Allen. With two pharmacies in operation in Tyler and College Station and a customer base of 47 hospitals and clinics the existing delivery system and pharmacist staff is used for the cyclotron facility. We then added cyclotron products to contracts with these customers to guarantee a supply. We partnered with a company in the process of developing PET imaging centers. We then built an independent imaging center attached to the cyclotron facility to allow for the use of short-lived isotopes.

  10. Development of a Medical Cyclotron Production Facility

    International Nuclear Information System (INIS)

    Allen, Danny R.

    2003-01-01

    Development of a Cyclotron manufacturing facility begins with a business plan. Geographics, the size and activity of the medical community, the growth potential of the modality being served, and other business connections are all considered. This business used the customer base established by NuTech, Inc., an independent centralized nuclear pharmacy founded by Danny Allen. With two pharmacies in operation in Tyler and College Station and a customer base of 47 hospitals and clinics the existing delivery system and pharmacist staff is used for the cyclotron facility. We then added cyclotron products to contracts with these customers to guarantee a supply. We partnered with a company in the process of developing PET imaging centers. We then built an independent imaging center attached to the cyclotron facility to allow for the use of short-lived isotopes

  11. DeBeNe Test Facilities for Fast Breeder Development

    International Nuclear Information System (INIS)

    Storz, R.

    1980-10-01

    This report gives an overview and a short description of the test facilities constructed and operated within the collaboration for fast breeder development in Germany, Belgium and the Netherlands. The facilities are grouped into Sodium Loops (Large Facilities and Laboratory Loops), Special Equipment including Hot Cells and Reprocessing, Test Facilities without Sodium, Zero Power Facilities and In-pile Loops including Irradiation Facilities

  12. Cryogenic detection of particles: Development effort in the United States

    International Nuclear Information System (INIS)

    Sadoulet, B.

    1987-05-01

    The development of cryogenic detectors of particles, with emphasis on large mass devices, has been reviewed. Most groups are still tooling up and exploring basic properties of sensors. The main discussion themes are summarized and some of the early experimental results are described

  13. Worldwide collaborative efforts in plasma control software development

    International Nuclear Information System (INIS)

    Penaflor, B.G.; Ferron, J.R.; Walker, M.L.; Humphreys, D.A.; Leuer, J.A.; Piglowski, D.A.; Johnson, R.D.; Xiao, B.J.; Hahn, S.H.; Gates, D.A.

    2008-01-01

    This presentation will describe the DIII-D collaborations with various tokamak experiments throughout the world which have adapted custom versions of the DIII-D plasma control system (PCS) software for their own use. Originally developed by General Atomics for use on the DIII-D tokamak, the PCS has been successfully installed and used for the NSTX experiment in Princeton, the MAST experiment in Culham UK, the EAST experiment in China, and the Pegasus experiment in the University of Wisconsin. In addition to these sites, a version of the PCS is currently being developed for use by the KSTAR tokamak in Korea. A well-defined and robust PCS software infrastructure has been developed to provide a common foundation for implementing the real-time data acquisition and feedback control codes. The PCS infrastructure provides a flexible framework that has allowed the PCS to be easily adapted to fulfill the unique needs of each site. The software has also demonstrated great flexibility in allowing for different computing, data acquisition and real-time networking hardware to be used. A description of the current PCS software architecture will be given along with experiences in developing and supporting the various PCS installations throughout the world

  14. Decontamination Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Oh, Won Zin; Jung, Chong Hun; Choi, Wang Kyu; Won, Hui Jun; Kim, Gye Nam

    2004-02-01

    Technology development of surface decontamination in the uranium conversion facility before decommissioning, technology development of component decontamination in the uranium conversion facility after decommissioning, uranium sludge treatment technology development, radioactive waste soil decontamination technology development at the aim of the temporary storage soil of KAERI, Optimum fixation methodology derivation on the soil and uranium waste, and safety assessment methodology development of self disposal of the soil and uranium waste after decontamination have been performed in this study. The unique decontamination technology applicable to the component of the nuclear facility at room temperature was developed. Low concentration chemical decontamination technology which is very powerful so as to decrease the radioactivity of specimen surface under the self disposal level was developed. The component decontamination technology applicable to the nuclear facility after decommissioning by neutral salt electro-polishing was also developed. The volume of the sludge waste could be decreased over 80% by the sludge waste separation method by water. The electrosorption method on selective removal of U(VI) to 1 ppm of unrestricted release level using the uranium-containing lagoon sludge waste was tested and identified. Soil decontamination process and equipment which can reduce the soil volume over 90% were developed. A pilot size of soil decontamination equipment which will be used to development of real scale soil decontamination equipment was designed, fabricated and demonstrated. Optimized fixation methodology on soil and uranium sludge was derived from tests and evaluation of the results. Safety scenario and safety evaluation model were development on soil and uranium sludge aiming at self disposal after decontamination

  15. Analysis of international efforts in energy research and development

    International Nuclear Information System (INIS)

    Rezaiyan, A.J.; Gill, R.T.

    1995-09-01

    Research and experimental development comprise innovative and creative work undertaken systematically to increase the stock of knowledge of science, engineering, and society. This knowledge reserve is used to improve living conditions and standards, including economic growth. Research and development (R ampersand D) expenditures are useful measures of the scale and direction of technological innovation within a country, industry, or scientific field. Administrators concerned with economic growth and performance rely on R ampersand D statistics as one possible type of indicator of technological change. R ampersand D statistics are an essential tool in many government programs and evaluations (OECD 1993). The objective of the analysis was to identify and evaluate R ampersand D funding sources, levels, and trends in the energy sectors of selected industrialized countries (Australia, Belgium, Canada, Denmark, Finland, France, Germany, Italy, Japan, Netherlands, Norway, Sweden, Switzerland, United Kingdom, United States) and the European Union (EU). Fossil fuel technologies, particularly fuel cells and advanced gas turbines, were the focus of the analysis, whose results are presented in this report

  16. Establishing molecular microbiology facilities in developing countries

    Directory of Open Access Journals (Sweden)

    Salman S. Ahmed

    2015-11-01

    Full Text Available Summary: Microbiology laboratories play an important role in epidemiology and infection control programs. Within microbiology laboratories, molecular microbiology techniques have revolutionized the identification and surveillance of infectious diseases. The combination of excellent sensitivity, specificity, low contamination levels and speed has made molecular techniques appealing methods for the diagnosis of many infectious diseases. In a well-equipped microbiology laboratory, the facility designated for molecular techniques remains indiscrete. However, in most developing countries, poor infrastructure and laboratory mismanagement have precipitated hazardous consequences. The establishment of a molecular microbiology facility within a microbiology laboratory remains fragmented. A high-quality laboratory should include both conventional microbiology methods and molecular microbiology techniques for exceptional performance. Furthermore, it should include appropriate laboratory administration, a well-designed facility, laboratory procedure standardization, a waste management system, a code of practice, equipment installation and laboratory personnel training. This manuscript lays out fundamental issues that need to be addressed when establishing a molecular microbiology facility in developing countries. Keywords: Developing country, Molecular technique, Molecular microbiology laboratory

  17. Low Temperature Double-layer Capacitors with Improved Energy Density: An Overview of Recent Development Efforts

    Science.gov (United States)

    Brandon, Erik J.; West, William C.; Smart, Marshall C.; Yushin, Gleb; Korenblit, Yair; Kajdos, Adam; Kvit, Alexander; Jagiello, Jacek

    2012-01-01

    Electrochemical double-layer capacitors are finding increased use in a wide range of energy storage applications, particularly where high pulse power capabilities are required. Double-layer capacitors store charge at a liquid/solid interface, making them ideal for low temperature power applications, due to the facile kinetic processes associated with the rearrangement of the electrochemical double-layer at these temperatures. Potential low temperature applications include hybrid and electric vehicles, operations in polar regions, high altitude aircraft and aerospace avionics, and distributed environmental and structural health monitoring. State-of-the-art capacitors can typically operate to -40 C, with a subsequent degradation in power performance below room temperature. However, recent efforts focused on advanced electrolyte and electrode systems can enable operation to temperatures as low as -70 C, with capacities similar to room temperature values accompanied by reasonably low equivalent series resistances. This presentation will provide an overview of recent development efforts to extend and improve the wide temperature performance of these devices.

  18. Detection of suboptimal effort with symbol span: development of a new embedded index.

    Science.gov (United States)

    Young, J Christopher; Caron, Joshua E; Baughman, Brandon C; Sawyer, R John

    2012-03-01

    Developing embedded indicators of suboptimal effort on objective neurocognitive testing is essential for detecting increasingly sophisticated forms of symptom feigning. The current study explored whether Symbol Span, a novel Wechsler Memory Scale-fourth edition measure of supraspan visual attention, could be used to discriminate adequate effort from suboptimal effort. Archival data were collected from 136 veterans classified into Poor Effort (n = 42) and Good Effort (n = 94) groups based on symptom validity test (SVT) performance. The Poor Effort group had significantly lower raw scores (p Span test. A raw score cutoff of Span can effectively differentiate veterans with multiple failures on established free-standing and embedded SVTs.

  19. Research and development efforts in the implementation of nuclear power programme in Indonesia

    International Nuclear Information System (INIS)

    Suhaemi, T.

    1986-04-01

    Research and development efforts in the implementation of nuclear power programme in Indonesia are presented. According to Indonesia Law, the National Atomic Energy Agency (BATAN) is an official body which is reponsible for all aspects of nuclear development. In implementing the nuclear power, BATAN together with the State Electricity Corporation (PLN) have pioneered the introduction of nuclear power plant in Indonesia by carrying out various activities, studies, seminars, workshops and report writings. A nuclear power planning study was carried out jointly with the International Atomic Energy Agency. The feasibility studies were also carried out by NIRA, an Italian consultant firm in cooperation with BATAN and PLN. To improve research and development, BATAN has established 5 research nuclear centres which function as centres of basic and applied research, isotope and radiation application, standardization and calibration and uranium exploration. Nowadays BATAN is constructing a sophisticated and multidisciplinary complex at Serpong near Jakarta. It is hoped that the participation of the national industry can be synchronized to the construction of the first nuclear power in Indonesia. To endorse the movement towards the industrial and technological future, the National Centre for Research, Science and Technology (known as PUSPITEK) has been established. There will be 12 different laboratories providing facilities for research and development of all aspects of technology. For training manpower, BATAN has established the Education and Training Centre (PUSDIKLAT). BATAN has also collaborated with universities, such as Gadjahmada University in Yogyakarta, in establishing Nuclear Engineering Division in the School of Engineering. 6 refs, 3 figs

  20. Development of Diagnostic Technology for Substation Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kweon, D.J.; Yoon, J.Y. [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1998-09-01

    This report contains the conceptual design of predictive diagnostic system for KEPCO 765kV substation apparatus which will be operated in 2001. Various kinds of techniques in the world for power transformer and GIS monitoring were examined, then the integrated diagnosis system configuration which will be most effective in our future substation was suggested. In addition, the development of the optimum life management for substation facilities. development of a system to measure the ESDD of substation insulator surfaces at a distance and application study of the degradation sensor(PCS) were described also. (author) 55 refs., 27 figs., 68 tabs.

  1. Diagnostic development and support of MHD test facilities

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The Diagnostic Instrumentation and Analysis Laboratory (DIAL) at Mississippi State University (MSU) is developing diagnostic instruments for MHD power train data acquisition and for support of MHD component development test facilities. Microprocessor-controlled optical instruments, initially developed for Heat Recovery/Seed Recovery support, are being refined, and new systems to measure temperatures and gas-seed-slag stream characteristics are being developed. To further data acquisition and analysis capabilities, the diagnostic systems are being interfaced with DIAL's computers. Technical support for the diagnostic needs of the national MHD research effort is being provided. DIAL personnel will also cooperate with government agencies and private industries to improve the transformation of research and development results into processes, products and services applicable to their needs. 25 figs., 6 tabs.

  2. Diagnostic development and support of MHD (magnetohydrodynamics) test facilities

    Energy Technology Data Exchange (ETDEWEB)

    1989-07-01

    Mississippi State University (MSU) is developing diagnostic instruments for Magnetohydrodynamics (MHD) power train data acquisition and for support of MHD component development test facilities. Microprocessor-controlled optical instruments, initially developed for HRSR support, are being refined, and new systems to measure temperatures and gas-seed-slag stream characteristics are being developed. To further data acquisition and analysis capabilities, the diagnostic systems are being interfaced with MHD Energy Center computers. Technical support for the diagnostic needs of the national MHD research effort is being provided. MSU personnel will also cooperate with government agencies and private industries to improve the transformation of research and development results into processes, products and services applicable to their needs.

  3. Diagnostic development and support of MHD test facilities

    International Nuclear Information System (INIS)

    Shepard, W.S.; Cook, R.L.

    1990-01-01

    The Diagnostic Instrumentation and Analysis Laboratory (DIAL) at Mississippi State University (MSU) is developing diagnostic instruments for MHD power train data acquisition and for support of MHD component development test facilities. Microprocessor-controlled optical instruments, initially developed for Heat Recovery/ Seed Recovery support, are being refined, and new systems to measure temperatures and gas-seed-slag stream characteristics are being developed. To further data acquisition and analysis capabilities, the diagnostic systems are being interfaced with DIAL's computers. Technical support for the diagnostic needs of the national MHD research effort is being provided. DIAL personnel will also cooperate with government agencies and private industries to improve the transformation of research and development results into processes, products and services applicable to their needs

  4. The One Plan Project: A cooperative effort of the National Response Team and the Region 6 Regional Response Team to simplify facility emergency response planning

    International Nuclear Information System (INIS)

    Staves, J.; McCormick, K.

    1997-01-01

    The National Response Team (NRT) in coordination with the Region 6 Response Team (RRT) have developed a facility contingency plan format which would integrate all existing regulatory requirements for contingency planning. This format was developed by a multi-agency team, chaired by the USEPA Region 6, in conjunction with various industry, labor, and public interest groups. The impetus for this project came through the USEPA Office of Chemical Emergency Preparedness and Prevention (CEPPO). The current national oil and hazardous material emergency preparedness and response system is an amalgam of federal, state, local, and industrial programs which are often poorly coordinated. In a cooperative effort with the NRT, the CEPPO conducted a Presidential Review of federal agency authorities and coordination responsibilities regarding release prevention, mitigation, and response. Review recommendations led to a Pilot Project in USEPA Region 6. The Region 6 Pilot Project targeted end users in the intensely industrialized Houston Ship Channel (HSC) area, which is comprised of petroleum and petrochemical companies

  5. Conceptual development of a test facility for spent fuel management

    Energy Technology Data Exchange (ETDEWEB)

    Park, S.W.; Lee, H.H.; Lee, J.Y.; Lee, J.S.; Ro, S.G. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    Spent fuel management is an important issue for nuclear power program, requiring careful planning and implementation. With the wait-and-see policy on spent fuel management in Korea, research efforts are directed at KAERI to develop advanced technologies for safer and more efficient management of the accumulating spent fuels. In support of these research perspectives, a test facility of pilot scale is being developed with provisions for integral demonstration of a multitude of technical functions required for spent fuel management. The facility, baptized SMART (Spent fuel MAnagement technology Research and Test facility), is to be capable of handling full size assembly of spent PWR fuel (as well as CANDU fuel) with a maximum capacity of 10 MTU/y (about 24 assemblies of PWR type). Major functions of the facility are consolidation of spent PWR fuel assembly into a half-volume package and optionally transformation of the fuel rod into a fuel of CANDU type (called DUPIC). Objectives of these functions are to demonstrate volume reduction of spent fuel (for either longer-term dry storage or direct disposal ) in the former case and direct refabrication of the spent PWR fuel into CANDU-type DUPIC fuel for reuse in CANDU reactors in the latter case, respectively. In addition to these major functions, there are other associated technologies to be demonstrated : such as waste treatment, remote maintenance, safeguards, etc. As the facility is to demonstrate not only the functional processes but also the safety and efficiency of the test operations, engineering criteria equivalent to industrial standards are incorporated in the design concept. The hot cell structure enclosing the radioactive materials is configured in such way to maximize costs within the given functional and operational requirements. (author). 3 tabs., 4 figs.

  6. Conceptual development of a test facility for spent fuel management

    International Nuclear Information System (INIS)

    Park, S.W.; Lee, H.H.; Lee, J.Y.; Lee, J.S.; Ro, S.G.

    1997-01-01

    Spent fuel management is an important issue for nuclear power program, requiring careful planning and implementation. With the wait-and-see policy on spent fuel management in Korea, research efforts are directed at KAERI to develop advanced technologies for safer and more efficient management of the accumulating spent fuels. In support of these research perspectives, a test facility of pilot scale is being developed with provisions for integral demonstration of a multitude of technical functions required for spent fuel management. The facility, baptized SMART (Spent fuel MAnagement technology Research and Test facility), is to be capable of handling full size assembly of spent PWR fuel (as well as CANDU fuel) with a maximum capacity of 10 MTU/y (about 24 assemblies of PWR type). Major functions of the facility are consolidation of spent PWR fuel assembly into a half-volume package and optionally transformation of the fuel rod into a fuel of CANDU type (called DUPIC). Objectives of these functions are to demonstrate volume reduction of spent fuel (for either longer-term dry storage or direct disposal ) in the former case and direct refabrication of the spent PWR fuel into CANDU-type DUPIC fuel for reuse in CANDU reactors in the latter case, respectively. In addition to these major functions, there are other associated technologies to be demonstrated : such as waste treatment, remote maintenance, safeguards, etc. As the facility is to demonstrate not only the functional processes but also the safety and efficiency of the test operations, engineering criteria equivalent to industrial standards are incorporated in the design concept. The hot cell structure enclosing the radioactive materials is configured in such way to maximize costs within the given functional and operational requirements. (author). 3 tabs., 4 figs

  7. Personal Professional Development Efforts of Science and Technology Teachers in Their Fields

    Science.gov (United States)

    Bilgin, Aysegul; Balbag, Mustafa Zafer

    2018-01-01

    The aim of this study is to examine the personal professional development efforts of science and technology teachers in their fields with regard to some variables. These variables were determined as gender, year of seniority and sufficiency level of the laboratory equipment. Moreover, the relation between the actual efforts exerted by science and…

  8. Large sample NAA facility and methodology development

    International Nuclear Information System (INIS)

    Roth, C.; Gugiu, D.; Barbos, D.; Datcu, A.; Aioanei, L.; Dobrea, D.; Taroiu, I. E.; Bucsa, A.; Ghinescu, A.

    2013-01-01

    A Large Sample Neutron Activation Analysis (LSNAA) facility has been developed at the TRIGA- Annular Core Pulsed Reactor (ACPR) operated by the Institute for Nuclear Research in Pitesti, Romania. The central irradiation cavity of the ACPR core can accommodate a large irradiation device. The ACPR neutron flux characteristics are well known and spectrum adjustment techniques have been successfully applied to enhance the thermal component of the neutron flux in the central irradiation cavity. An analysis methodology was developed by using the MCNP code in order to estimate counting efficiency and correction factors for the major perturbing phenomena. Test experiments, comparison with classical instrumental neutron activation analysis (INAA) methods and international inter-comparison exercise have been performed to validate the new methodology. (authors)

  9. Sports Facilities Development and Urban Generation

    OpenAIRE

    Maassoumeh Barghchi; Dasimah B.   Omar; Mohd S.   Aman

    2009-01-01

    Problem statement: One major issue on sports facilities construction is the question of their funding and justification for investment. Due to, requirement of huge money for construction, constant maintenance costs and ancillary needs, which are almost certainly with substantial public investment, therefore, sports facilities have been considered. Further, sports facilities construction boom have been started for more than two decades. Approach: Recent sports facilities construction was not p...

  10. Progress in developing new commercial LLRW disposal facilities and DOE assistance

    International Nuclear Information System (INIS)

    Tait, T.D.; Hinschberger, S.T.

    1988-01-01

    This paper reports state and regional progress in developing new commercial low-level radioactive waste disposal facilities. Specifically the paper addresses DOE determination of state and regional compliance with the 1988 milestone requirements of the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). In addition, the paper summarizes the assistance provided by the Department of Energy (DOE) to the states and regions in their efforts to develop new disposal facilities as mandated in the LLRWPAA

  11. Development of circular filters for active facilities

    International Nuclear Information System (INIS)

    Pratt, R.P.

    1986-01-01

    An assessment of problems associated with remote handling, changing and disposal of filters suggested that significant improvements to filtration systems could be made if circular geometries were adopted in place of conventional systems. Improved systems have been developed and are now available for a range of applications and air flow rates. Where primary filters are installed within the active cell or cave, circular filters incorporating a lip seal have been developed which enable the filters to be sealed into the facility without recourse to clamping. For smaller cells, a range of push-through filter change systems have been developed, the principal feature being that the filter is passed into the housing from the clean side, but transferred from the housing directly into the cell for subsequent disposal. For plant room applications, circular bag change canister systems have been developed which ease the sealing and bag change operation. Such systems have a rated air flow of up to 3000 m 3 /h whilst still allowing ultimate disposal via the 200 litre waste drum route without prior volume reduction of the filter inserts. (author)

  12. Development of the Jyvaeskylae microbeam facility

    Energy Technology Data Exchange (ETDEWEB)

    Norarat, Rattanaporn, E-mail: rattanaporn.norarat@phys.jyu.fi [Department of Physics, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 Jyvaeskylae (Finland); Sajavaara, Timo; Laitinen, Mikko; Heikkinen, Pauli; Ranttila, Kimmo; Ylikorkala, Kari; Haenninen, Vaeinoe; Rossi, Mikko; Jones, Pete [Department of Physics, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 Jyvaeskylae (Finland); Marjomaeki, Varpu; Gilbert, Leona [Department of Environmental and Biological Sciences, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 Jyvaeskylae (Finland); Whitlow, Harry J. [Department of Physics, University of Jyvaeskylae, P.O. Box 35 (YFL), FIN-40014 Jyvaeskylae (Finland)

    2012-02-01

    Research highlights: Black-Right-Pointing-Pointer A MeV ion microbeam for biomedical materials research is being developed. Black-Right-Pointing-Pointer High accuracy scanning using electrostatic post-focus deflection. Black-Right-Pointing-Pointer Imaging and direct lithographic image writing using time-stamping methods. Black-Right-Pointing-Pointer New scanning modes and fluorescence detectors permit low ion-fluence cell imaging. Black-Right-Pointing-Pointer Thermal compensated beam-line support design for high positional accuracy. - Abstract: A new microbeam facility is being constructed at the 1.7 MV Pelletron Accelerator in Jyvaeskylae. The facility is designed for easy upgrading and incorporates a number of innovative features. Initially, it is based on a Heidelberg doublet with a design capability of a 3 Multiplication-Sign 5 {mu}m beamspot at PIXE intensities and later upgraded to nanobeam performance. A thermal-expansion compensated rigid frame mounted on a mechanically isolated floor section is used to support the ion optical components. A compact-post focusing electrostatic deflector is used for high linearity beam scanning. This together with a novel time-stamped data collection (TDC) allows dynamic effects in IBIC, fluorescence bleaching to be studied as well as facilitating multi-resolution image support for low-fluence imaging of cells. The target chamber is fitted with a novel low-cost large working distance optical microscope, extremely compact large solid angle photon detectors as well as conventional secondary electron, PIXE and Scanning Transmission Ion Microscopy (STIM) detectors.

  13. [Glass Development Laser (GDL) Facility upgrade.] LLE Review. Quarterly report, October-December 1984. Volume 21

    International Nuclear Information System (INIS)

    Kim, H.

    1984-01-01

    This volume of the LLE Review contains articles on the upgrade of the GDL (Glass Development) system, theoretical advances in the laser fusion effort, improved target fabrication capabilities, x-ray laser research, developments in the picosecond optics research of the LLE advanced technology program, and on the National Laser Users Facility activities for October-December 1984. 56 refs., 31 figs., 3 tabs

  14. Development of a state radioactive materials storage facility

    International Nuclear Information System (INIS)

    Schmidt, P.S.

    1995-01-01

    The paper outlines the site selection and facility development processes of the state of Wisconsin for a radioactive materials facility. The facility was developed for the temporary storage of wastes from abandoned sites. Due to negative public reaction, the military site selected for the facility was removed from consideration. The primary lesson learned during the 3-year campaign was that any project involving radioactive materials is a potential political issue

  15. Sustainable Facility Development: Perceived Benefits and Challenges

    Science.gov (United States)

    Stinnett, Brad; Gibson, Fred

    2016-01-01

    Purpose: The purpose of this paper is to assess the perceived benefits and challenges of implementing sustainable initiatives in collegiate recreational sports facilities. Additionally, this paper intends to contribute to the evolving field of facility sustainability in higher education. Design/methodology/approach The design included qualitative…

  16. Conceptual design of a 10-MJ driver for a high gain target development facility

    International Nuclear Information System (INIS)

    Olson, R.E.

    1987-01-01

    Commercial application of inertial confinement fusion (ICF) will require inexpensive, high gain (>80) fusion targets. It is thought that the development of such targets will require a 5 to 10 year search effort utilizing a dedicated nuclear research facility with a driver capable of providing a 10 MJ, 300 to 1000 TW pulse of on-target energy. The Terget Development Facility (TDF) is a light ion driven concept for such a facility. A TDF driver based upon extrapolations from present-day pulsed power technology is described in the present paper

  17. Safety analysis of DUPIC fuel development facility

    International Nuclear Information System (INIS)

    Lee, H. H.; Park, J. J.; Shin, J. M.; Yang, M. S.; Baek, S. Y.; Ahn, J. Y.

    2001-01-01

    Various experimental facilities are necessary in order to perform experimental verification for development of DUPIC fuel fabrication technology. In special, since highly radioactive material such as spent PWR fuel is used for this experiment, DUPIC fuel fabrication has to be performed in hot cell by remote handling. Therefore, it should be provided with proper engineering requirement and safety. M6 hot cell of IMEF which is to used for DUPIC fuel fabrication experiment was constructed as an α-γ hot cell for material examination of small amount of high-burnup fuel. The characteristics and amount of spent fuel for DUPIC fuel fabrication experiment will be different from the original design criteria. Therefore, the increased amount of spent fuel and different characteristics of experiment result in not only change of shielding and enviornmental evaluation results but new requirement of nuclear criticality evaluation. Therefore, this study includes evaluation of shielding, environmental effect and nuclear criticality in case that IMEF M6 hot cell is used for DUPIC fuel fabrication

  18. Further development of NEPTUN photon tagging facility

    Energy Technology Data Exchange (ETDEWEB)

    Symochko, Dmytro; Arnould, Michaela; Aumann, Thomas; Baumann, Martin; Pietralla, Norbert; Scheit, Heiko; Semmler, Diego; Walz, Christopher [Institut fuer Kernphysik, Darmstadt Univ. (Germany)

    2016-07-01

    The low-energy photon tagging facility NEPTUN at the superconducting Darmstadt linear accelerator (SDALINAC) has been constructed with the aim to study the photoabsorption cross section of the nuclei in the energy regions of Pygmy Dipole and Giant Dipole Resonances. Recently it went through the series of commissioning runs, which proved the concept and the ability of NEPTUN to tag the discreet nuclear states. Also, based on the results of the commissioning, major upgrade was developed to optimize the setup. Upgraded tagger will be able to operate with 60 MeV electron beam and will have extended focal plane with energy bite of more than 10 MeV. After completion of upgrade it will be possible to perform total dipole response measurement in the energy region 5-35 MeV for one target using only 2-3 settings of the spectrometer. Presentation will focus on the analysis results of commissioning runs and details of the proposed upgrade plan.

  19. Personal Professional Development Efforts Scale for Science and Technology Teachers Regarding Their Fields

    Science.gov (United States)

    Bilgin, Aysegül; Balbag, Mustafa Zafer

    2016-01-01

    This study has developed "Personal Professional Development Efforts Scale for Science and Technology Teachers Regarding Their Fields". Exploratory factor analysis of the scale has been conducted based on the data collected from 200 science and technology teachers across Turkey. The scale has been observed through varimax rotation method,…

  20. Personal Professional Development Efforts Scale for Middle School Mathematics Teachers: An Adaptation Study

    Science.gov (United States)

    Balbag, M. Zafer; Yenilmez, Kürsat; Turgut, Melih

    2017-01-01

    This study aimed at adapting the personal professional development efforts scale developed for science and technology teachers to be applied for middle school mathematics teachers. For this purpose, first of all, the items of the original scale were adjusted for the middle school mathematics teachers by a team of experts. Data obtained by the new…

  1. 40 CFR 256.42 - Recommendations for assuring facility development.

    Science.gov (United States)

    2010-07-01

    ... facilities and practices to be developed by responsible State and substate agencies or by the private sector... sector initiatives in order to meet the identified facility needs. (e) In any area having fewer than 2... establish procedures for choosing which facilities will get priority for technical or financial assistance...

  2. Decontamination Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Choi, W. K.; Jung, C. H.; Oh, W. Z.

    2007-06-01

    The originative CO 2 pellet blasting equipment was developed by improving additional components such as feed screw, idle roller and air-lock feeder to clear up the problems of freezing and discontinuity of blasting and by adopting pneumatically operated vacuum suction head and vacuum cup to prevent recontamination by collecting contaminant particulates simultaneously with the decontamination. The optimum decontamination process was established according to the kind of materials such as metal, concrete and plastic and the type of contaminants such as particulate, fixed chemical compound and oil. An excellent decontamination performances were verified by means of the lab-scale hot test with radioactive specimen and the technology demonstration in IMEF hot cell. The PFC dry decontamination equipment applicable to the surface contaminated with high radioactive particulate was developed. This equipment consists of the unit processes such as spray, collection, filtration and dry distillation designed originatively applicable to inside of dry hot cell. Through the demonstration of PFC spray decontamination process in IMEF hot cell, we secured on-site applicability and the decontamination efficiency more than 90 %. We investigated the characteristics of dismantled metal waste melting and the radionuclide(Co, Cs, U) distribution into ingot and slag by melting decontamination experiments using electric arc melter. We obtained the decontamination factors greater than 100 for Cs and of 10∼100 for uranium. The pilot scale(200 kg/batch) demonstration for melting decontamination was carried out successfully using high temperature melting facility at KAERI. The volume reduction factor of 1/7 and the economical feasibility of the melting decontamination were verified.

  3. Geoscience Workforce Development at UNAVCO: Leveraging the NSF GAGE Facility

    Science.gov (United States)

    Morris, A. R.; Charlevoix, D. J.; Miller, M.

    2013-12-01

    Global economic development demands that the United States remain competitive in the STEM fields, and developing a forward-looking and well-trained geoscience workforce is imperative. According to the Bureau of Labor Statistics, the geosciences will experience a growth of 19% by 2016. Fifty percent of the current geoscience workforce is within 10-15 years of retirement, and as a result, the U.S. is facing a gap between the supply of prepared geoscientists and the demand for well-trained labor. Barring aggressive intervention, the imbalance in the geoscience workforce will continue to grow, leaving the increased demand unmet. UNAVCO, Inc. is well situated to prepare undergraduate students for placement in geoscience technical positions and advanced graduate study. UNAVCO is a university-governed consortium facilitating research and education in the geosciences and in addition UNAVCO manages the NSF Geodesy Advancing Geosciences and EarthScope (GAGE) facility. The GAGE facility supports many facets of geoscience research including instrumentation and infrastructure, data analysis, cyberinfrastructure, and broader impacts. UNAVCO supports the Research Experiences in the Solid Earth Sciences for Students (RESESS), an NSF-funded multiyear geoscience research internship, community support, and professional development program. The primary goal of the RESESS program is to increase the number of historically underrepresented students entering graduate school in the geosciences. RESESS has met with high success in the first 9 years of the program, as more than 75% of RESESS alumni are currently in Master's and PhD programs across the U.S. Building upon the successes of RESESS, UNAVCO is launching a comprehensive workforce development program that will network underrepresented groups in the geosciences to research and opportunities throughout the geosciences. This presentation will focus on the successes of the RESESS program and plans to expand on this success with broader

  4. Aerospace Plane Technology: Research and Development Efforts in Japan and Australia

    Science.gov (United States)

    1991-10-01

    However, only with the develop- Aerospace Planes ment of better test facility instruments and more trained personnel, together with the renovation and...necessary. Such a rocket booster (the H-IID) would be one of the largest launchers in the world after the Soviet Energia booster and U.S. Titan IV launch

  5. DOE research and development and field facilities

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    This report describes the roles of DOE's headquarters, field offices, major multiprogram laboratories, Energy Technology and Mining Operations Centers, and other government-owned, contractor-operated facilities which are located in all regions of the United States. It gives brief descriptions of resources, activities, and capabilities of each field facility (sections III through V). These represent a cumulative capital investment of $12 billion and involve a work force of approximately 12,000 government (field) employees and approximately 100,000 contractor employees.

  6. Chile and Its Efforts to Present High-Level Technologies to the Developed World

    Science.gov (United States)

    Young, Nathan

    2007-01-01

    Chile is rich in natural resources. Like many other resource-dependent nations, it has never made technology transfer a subject of intense focus. This article sheds light on the technological state of Chile today and its efforts to promote development, increase innovation and move towards a knowledge-based economy. The paper summarizes current…

  7. Development of automatic facilities for ZEPHYR

    International Nuclear Information System (INIS)

    Eder, O.; Lackner, E.; Pohl, F.; Schilling, H.B.

    1982-04-01

    This concept of remotely controlled facilities for repair and maintenance tasks inside the ZEPHYR vacuum vessel uses a supporting structure to insert various types of mobile automatic devices are guided by an egg-shaped disc which is part of the supporting structure. Considerations of adapting the guiding disc to the vessel contour are included. (orig.)

  8. Upgrades of Hanford Engineering Development Laboratory hot cell facilities

    International Nuclear Information System (INIS)

    Daubert, R.L.; DesChane, D.J.

    1987-01-01

    The Hanford Engineering Development Laboratory operates the 327 Postirradiation Testing Laboratory (PITL) and the 324 Shielded Materials Facility (SMF). These hot cell facilities provide diverse capabilities for the postirradiation examination and testing of irradiated reactor fuels and materials. The primary function of these facilities is to determine failure mechanisms and effects of irradiation on physical and mechanical properties of reactor components. The purpose of this paper is to review major equipment and facility upgrades that enhance customer satisfaction and broaden the engineering capabilities for more diversified programs. These facility and system upgrades are providing higher quality remote nondestructive and destructive examination services with increased productivity, operator comfort, and customer satisfaction

  9. Prototype development of radio frequency cavity and quadrupole for ADSS - initial efforts by mechanical design and prototype development section

    International Nuclear Information System (INIS)

    Kumar, Manish; Kamble, Sunil; Choughule, L.S.; Kumar, Sunil; Patankar, S.R.; Phalke, V.M.; Dharmik, D.A.; Singh, Tejinder; Ram, Y.; Chaudhari, A.T.; Pathak, Kavindra; Prasad, N.K.; Marathe, V.V.; Matkar, A.W.

    2007-01-01

    Mechanical Design and Prototype Development Section has participated in the efforts for development of RF cavity and Quadrupole for ADSS. Recently prototype Super conducting RF cavity, Radio Frequency Quadrupole (RFQ), Radio Frequency Quadrupole (RFQ) Simulation Chamber and related experimental setups were developed, fabricated and delivered for the characterisation of various relevant parameters. Under the program for development of Super conducting RF Cavity for high-energy section of LINAC of ADS first prototype RF Cavity of ETP copper was developed by machining and brazing process. The prototype cavity having elliptical and circular profile is the heart of this setup. The cavity is made up of two symmetrical cups joined together by welding or brazing. Various methods are being tried out by MD and PDS for the fabrication of cups and joining them together. Manufacturing of cup by machining and joining them by conventional brazing technique to make the cavity was the first step in this direction. Another method of manufacturing and joining viz forming of cup by deep drawing and joining them by EB welding is in progress. RFQ is a versatile and efficient system for accelerating ion beams especially at low energy. It works in quadrupole mode, which is at 350M Hz. RFQ Focuses, Bunches and Accelerates the beam simultaneously. The bunching is done in this RFQ, which results in more than 95% transmission where as in the normal buncher the transmission is less than 40%. The actual RFQ, which is designed for the PURNIMA facility, will be fabricated from OFHC copper that will accelerate a deuteron (D+) ion beam from 50keV to 400keV over its 1.37meter length. For the validation of manufacturing process and characterisation of various parameters at low frequency a 500mm long prototype RFQ in Aluminium with an accuracy of ± 25microns and surface finish of 1.6 micron has been fabricated by MD and PDS. A simplified simulation chamber to facilitate the development of RFQ for

  10. DARPA-funded efforts in the development of novel brain-computer interface technologies.

    Science.gov (United States)

    Miranda, Robbin A; Casebeer, William D; Hein, Amy M; Judy, Jack W; Krotkov, Eric P; Laabs, Tracy L; Manzo, Justin E; Pankratz, Kent G; Pratt, Gill A; Sanchez, Justin C; Weber, Douglas J; Wheeler, Tracey L; Ling, Geoffrey S F

    2015-04-15

    The Defense Advanced Research Projects Agency (DARPA) has funded innovative scientific research and technology developments in the field of brain-computer interfaces (BCI) since the 1970s. This review highlights some of DARPA's major advances in the field of BCI, particularly those made in recent years. Two broad categories of DARPA programs are presented with respect to the ultimate goals of supporting the nation's warfighters: (1) BCI efforts aimed at restoring neural and/or behavioral function, and (2) BCI efforts aimed at improving human training and performance. The programs discussed are synergistic and complementary to one another, and, moreover, promote interdisciplinary collaborations among researchers, engineers, and clinicians. Finally, this review includes a summary of some of the remaining challenges for the field of BCI, as well as the goals of new DARPA efforts in this domain. Copyright © 2014 The Authors. Published by Elsevier B.V. All rights reserved.

  11. What Drives Biodiversity Conservation Effort in the Developing World? An analysis for Sub-Saharan Africa

    OpenAIRE

    Ariane Manuela Amin

    2012-01-01

    Biodiversity conservation in low-income economies is a vital issue and hence needs to be addressed for development and poverty eradication. A variety of empirical works exist on the subject, but the focus is often limited on the search for possible causes of biodiversity erosion. Research on the "driving forces" that influence biodiversity conservation effort is still largely missing, especially for developing countries. In this study, we seek to address this gap. We test, using different mod...

  12. Report of the committee on a commercially developed space facility

    Science.gov (United States)

    Shea, Joseph F.; Stever, H. Guyford; Cutter, W. Bowman, III; Demisch, Wolfgang H.; Fink, Daniel J.; Flax, Alexander H.; Gatos, Harry C.; Glicksman, Martin E.; Lanzerotti, Louis J.; Logsdon, John M., III

    1989-01-01

    Major facilities that could support significant microgravity research and applications activity are discussed. The ground-based facilities include drop towers, aircraft flying parabolic trajectories, and sounding rockets. Facilities that are intrinsically tied to the Space Shuttle range from Get-Away-Special canisters to Spacelab long modules. There are also orbital facilities which include recoverable capsules launched on expendable launch vehicles, free-flying spacecraft, and space stations. Some of these existing, planned, and proposed facilities are non-U.S. in origin, but potentially available to U.S. investigators. In addition, some are governmentally developed and operated whereas others are planned to be privately developed and/or operated. Tables are provided to show the facility, developer, duration, estimated gravity level, crew interaction, flight frequency, year available, power to payload, payload volume, and maximum payload mass. The potential of direct and indirect benefits of manufacturing in space are presented.

  13. 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

  14. Effect of Community Engagement Interventions on Patient Safety and Risk Reduction Efforts in Primary Health Facilities: Evidence from Ghana

    NARCIS (Netherlands)

    Alhassan, Robert Kaba; Nketiah-Amponsah, Edward; Spieker, Nicole; Arhinful, Daniel Kojo; Ogink, Alice; van Ostenberg, Paul; Rinke de Wit, Tobias F.

    2015-01-01

    Background Patient safety and quality care remain major challenges to Ghana's healthcare system. Like many health systems in Africa, this is largely because demand for healthcare is outstripping available human and material resource capacity of healthcare facilities and new investment is

  15. Development of ISA procedure for uranium fuel fabrication and enrichment facilities

    International Nuclear Information System (INIS)

    Yamate, Kazuki; Arakawa, Tomoyuki; Yamashita, Masahiro; Sasaki, Noriaki; Hirano, Mitsumasa

    2011-01-01

    The integrated safety analysis (ISA) procedure has been developed to apply risk-informed regulation to uranium fuel fabrication and enrichment facilities. The major development efforts are as follows: (a) preparing the risk level matrix as an index for items-relied-on-for-safety (IROFS) identification, (b) defining requirements of IROFS, and (c) determining methods of IROFS importance based on the results of risk- and scenario-based analyses. For the risk level matrix, the consequence and likelihood categories have been defined by taking into account the Japanese regulatory laws, rules, and safety standards. The trial analyses using the developed procedure have been performed for several representative processes of the reference uranium fuel fabrication and enrichment facilities. This paper presents the results of the ISA for the sintering process of the reference fabrication facility. The results of the trial analyses have demonstrated the applicability of the procedure to the risk-informed regulation of these facilities. (author)

  16. A review of recent developments in radiometric calibration facilities

    International Nuclear Information System (INIS)

    Corner, B.

    1984-01-01

    Two new developments concerning radiometric calibration facilities are described in this presentation. The first is the result of the international programme for the monitoring and cross-reference of existing calibration facilities, sponsored by the International Atomic Energy Agency. The second development that is discussed concerns the accuracy of the stripping ratios derived at Pelindaba and has important implications for in situ assaying

  17. Bloodstream infection rates in outpatient hemodialysis facilities participating in a collaborative prevention effort: a quality improvement report.

    Science.gov (United States)

    Patel, Priti R; Yi, Sarah H; Booth, Stephanie; Bren, Virginia; Downham, Gemma; Hess, Sally; Kelley, Karen; Lincoln, Mary; Morrissette, Kathy; Lindberg, Curt; Jernigan, John A; Kallen, Alexander J

    2013-08-01

    Bloodstream infections (BSIs) cause substantial morbidity in hemodialysis patients. In 2009, the US Centers for Disease Control and Prevention (CDC) sponsored a collaborative project to prevent BSIs in outpatient hemodialysis facilities. We sought to assess the impact of a set of interventions on BSI and access-related BSI rates in participating facilities using data reported to the CDC's National Healthcare Safety Network (NHSN). Quality improvement project. Patients in 17 outpatient hemodialysis facilities that volunteered to participate. Facilities reported monthly event and denominator data to NHSN, received guidance from the CDC, and implemented an evidence-based intervention package that included chlorhexidine use for catheter exit-site care, staff training and competency assessments focused on catheter care and aseptic technique, hand hygiene and vascular access care audits, and feedback of infection and adherence rates to staff. Crude and modeled BSI and access-related BSI rates. Up to 12 months of preintervention (January 2009 through December 2009) and 15 months of intervention period (January 2010 through March 2011) data from participating centers were analyzed. Segmented regression analysis was used to assess changes in BSI and access-related BSI rates during the preintervention and intervention periods. Most (65%) participating facilities were hospital based. Pooled mean BSI and access-related BSI rates were 1.09 and 0.73 events per 100 patient-months during the preintervention period and 0.89 and 0.42 events per 100 patient-months during the intervention period, respectively. Modeled rates decreased 32% (P = 0.01) for BSIs and 54% (P facilities were not representative of all outpatient hemodialysis centers nationally. There was no control arm to this quality improvement project. Facilities participating in a collaborative successfully decreased their BSI and access-related BSI rates. The decreased rates appeared to be maintained in the intervention

  18. The challenge of logistics facilities development

    Science.gov (United States)

    Davis, James R.

    1987-01-01

    The paper discusses the experiences of a group of engineers and logisticians at John F. Kennedy Space center in the design, construction and activation of a consolidated logistics facility for support of Space Transportation System ground operations and maintenance. The planning, methodology and processes are covered, with emphasis placed on unique aspects and lessons learned. The project utilized a progressive design, baseline and build concept for each phase of construction, with the Government exercising funding and configuration oversight.

  19. How Effective Have Thirty Years of Internationally Driven Conservation and Development Efforts Been in Madagascar?

    Science.gov (United States)

    Wilmé, Lucienne; Mercier, Jean-Roger; Camara, Christian; Lowry, Porter P.

    2016-01-01

    Conservation and development are intricately linked. The international donor community has long provided aid to tropical countries in an effort to alleviate poverty and conserve biodiversity. While hundreds of millions of $ have been invested in over 500 environmental-based projects in Madagascar during the period covered by a series of National Environmental Action Plans (1993–2008) and the protected areas network has expanded threefold, deforestation remains unchecked and none of the eight Millennium Development Goals (MDGs) established for 2000–2015 were likely be met. Efforts to achieve sustainable development had failed to reduce poverty or deliver progress toward any of the MDGs. Cross-sectorial policy adjustments are needed that (i) enable and catalyze Madagascar’s capacities rather than deepening dependency on external actors such as the World Bank, the International Monetary Fund and donor countries, and that (ii) deliver improvements to the livelihoods and wellbeing of the country’s rural poor. PMID:27532499

  20. How Effective Have Thirty Years of Internationally Driven Conservation and Development Efforts Been in Madagascar?

    Science.gov (United States)

    Waeber, Patrick O; Wilmé, Lucienne; Mercier, Jean-Roger; Camara, Christian; Lowry, Porter P

    2016-01-01

    Conservation and development are intricately linked. The international donor community has long provided aid to tropical countries in an effort to alleviate poverty and conserve biodiversity. While hundreds of millions of $ have been invested in over 500 environmental-based projects in Madagascar during the period covered by a series of National Environmental Action Plans (1993-2008) and the protected areas network has expanded threefold, deforestation remains unchecked and none of the eight Millennium Development Goals (MDGs) established for 2000-2015 were likely be met. Efforts to achieve sustainable development had failed to reduce poverty or deliver progress toward any of the MDGs. Cross-sectorial policy adjustments are needed that (i) enable and catalyze Madagascar's capacities rather than deepening dependency on external actors such as the World Bank, the International Monetary Fund and donor countries, and that (ii) deliver improvements to the livelihoods and wellbeing of the country's rural poor.

  1. The development of nuclear power and the research effort in the Community

    International Nuclear Information System (INIS)

    Davies, D.H.

    1986-01-01

    The development of nuclear power in the European Community up to the present time is reviewed in the light of the 1973 oil crisis. The European Community nuclear energy policy and strategy are described, as well as the future objectives for the development of nuclear power in Europe. The research effort in the Community, concerning energy resources, and including nuclear fission energy, is outlined. Research and development (R and D) work in the field of radioactive waste management is reviewed. Also some achievements of the twelve year Plan of Action, and of the multiannual R and D programmes are presented. (U.K.)

  2. Waste reduction efforts through the evaluation and procurement of a digital camera system for the Alpha-Gamma Hot Cell Facility at Argonne National Laboratory-East

    International Nuclear Information System (INIS)

    Bray, T. S.; Cohen, A. B.; Tsai, H.; Kettman, W. C.; Trychta, K.

    1999-01-01

    The Alpha-Gamma Hot Cell Facility (AGHCF) at Argonne National Laboratory-East is a research facility where sample examinations involve traditional photography. The AGHCF documents samples with photographs (both Polaroid self-developing and negative film). Wastes generated include developing chemicals. The AGHCF evaluated, procured, and installed a digital camera system for the Leitz metallograph to significantly reduce labor, supplies, and wastes associated with traditional photography with a return on investment of less than two years

  3. Achievement goal profiles and developments in effort and achievement in upper elementary school.

    Science.gov (United States)

    Hornstra, Lisette; Majoor, Marieke; Peetsma, Thea

    2017-12-01

    The multiple goal perspective posits that certain combinations of achievement goals are more favourable than others in terms of educational outcomes. This study aimed to examine longitudinally whether students' achievement goal profiles and transitions between profiles are associated with developments in self-reported and teacher-rated effort and academic achievement in upper elementary school. Participants were 722 fifth-grade students and their teachers in fifth and sixth grade (N = 68). Students reported on their achievement goals and effort in language and mathematics three times in grade 5 to grade 6. Teachers rated students' general school effort. Achievement scores were obtained from school records. Goal profiles were derived with latent profile and transition analyses. Longitudinal multilevel analyses were conducted. Theoretically favourable goal profiles (high mastery and performance-approach goals, low on performance-avoidance goals), as well as transitions from less to more theoretically favourable goal profiles, were associated with higher levels and more growth in effort for language and mathematics and with stronger language achievement gains. Overall, these results provide support for the multiple goal perspective and show the sustained benefits of favourable goal profiles beyond effects of cognitive ability and background characteristics. © 2017 The Authors. British Journal of Education Psychology published by John Wiley & Sons Ltd on behalf of British Psychological Society.

  4. Development of radiation safety monitoring system at gamma greenhouse gamma facility

    International Nuclear Information System (INIS)

    Hairul Nizam Idris; Azimawati Ahmad, Ahmad Zaki Hussain; Ahmad Fairuz Mohd Nasir

    2009-01-01

    This paper is discussing about installation of radiation safety monitoring system at Gamma Greenhouse Gamma facility, Agrotechnology and Bioscience Division (BAB). This facility actually is an outdoor type irradiation facility, which first in Nuclear Malaysia and the only one in Malaysia. Source Cs-137 (801 Curie) was use as radiation source and it located at the centre of 30 metres diameter size of open irradiation area. The radiation measurement and monitoring system to be equipped in this facility were required the proper equipment and devices, specially purpose for application at outside of building. Research review, literature study and discussion with the equipment manufacturers was being carried out, in effort to identify the best system should be developed. Factors such as tropical climate, environment surrounding and security were considered during selecting the proper system. Since this facility involving with panoramic radiation type, several critical and strategic locations have been fixed with radiation detectors, up to the distance at 200 meter from the radiation source. Apart from that, this developed system also was built for capable to provide the online real-time reading (using internet). In general, it can be summarized that the radiation safety monitoring system for outdoor type irradiation facility was found much different and complex compared to the system for indoor type facility. Keyword: radiation monitoring, radiation safety, Gamma Greenhouse, outdoor irradiation facility, panoramic radiation. (Author)

  5. Development of simplified decommissioning cost estimation code for nuclear facilities

    International Nuclear Information System (INIS)

    Tachibana, Mitsuo; Shiraishi, Kunio; Ishigami, Tsutomu

    2010-01-01

    The simplified decommissioning cost estimation code for nuclear facilities (DECOST code) was developed in consideration of features and structures of nuclear facilities and similarity of dismantling methods. The DECOST code could calculate 8 evaluation items of decommissioning cost. Actual dismantling in the Japan Atomic Energy Agency (JAEA) was evaluated; unit conversion factors used to calculate the manpower of dismantling activities were evaluated. Consequently, unit conversion factors of general components could be classified into three kinds. Weights of components and structures of the facility were necessary for calculation of manpower. Methods for evaluating weights of components and structures of the facility were studied. Consequently, the weight of components in the facility was proportional to the weight of structures of the facility. The weight of structures of the facility was proportional to the total area of floors in the facility. Decommissioning costs of 7 nuclear facilities in the JAEA were calculated by using the DECOST code. To verify the calculated results, the calculated manpower was compared with the manpower gained from actual dismantling. Consequently, the calculated manpower and actual manpower were almost equal. The outline of the DECOST code, evaluation results of unit conversion factors, the evaluation method of the weights of components and structures of the facility are described in this report. (author)

  6. Development of fusion first-wall radiation damage facilities

    International Nuclear Information System (INIS)

    McElroy, R.J.; Atkins, T.

    1986-11-01

    The report describes work performed on the development of fusion-reactor first-wall simulation facilities on the Variable Energy Cyclotron, at Harwell, United Kingdom. Two irradiation facilities have been constructed: i) a device for helium and hydrogen filling up to 1000 ppm for post-irradiation mechanical properties studies, and ii) a helium implantation and damage facility for simultaneous injection of helium and radiation damage into a specimen under stress. These facilities are now fully commissioned and are available for investigations of first-wall radiation damage and for intercorrelation of fission- and fusion -reactor materials behaviour. (U.K.)

  7. A development of multiphase flow facility

    International Nuclear Information System (INIS)

    Ismail Mustapha; Jaafar Abdullah

    2004-01-01

    Multiphase liquid flow facility shall be enabling to transport of oil/gas/water in pipelines. In horizontal pipelines, the different flow patterns that could be observed. The flow pattern will depend mainly on the gas and liquid velocities, and gas liquid ratio. For very high liquid velocities and low gas liquid ratios, the dispersed bubble flow is observed. For low flow rates of liquid and gas, a smooth or wavy stratified flow is expected. For intermediate liquid velocities, rolling waves of liquids are formed. The rolling waves increase to the point of forming a plug flow and a slug flow. For very high gas velocities, the annular flow is observed Also include a tillable test section allowing for testing at any angle between 0 0 degree from horizontal, lowering the measurement uncertainties and increased capabilities with respect to flow rates and gas fractions. (Author)

  8. Developing a LLW disposal facility in California

    International Nuclear Information System (INIS)

    Romano, S.A.; Gaynor, R.K.; Hanrahan, T.P.

    1988-01-01

    US Ecology has been designated by the State of California to site and operate a low-level radioactive waste disposal facility. The firm identified three sites for detailed characterization work in February, 1987. Ecological and archaeological studies and related environmental assessments were undertaken to obtain land use permits from the Bureau of Land Management, which holds title to the sites. Geophysics investigations, exploratory borings, well drilling and weather station installation followed. Local Committees were established for each site to assist US Ecology in evaluating socio-economic impacts, and Native Americans were consulted regarding cultural resources. The project's Citizens Advisory Committee assisted in evaluating the three candidate sites. US Ecology systematically integrated citizen involvement into the technical studies leading to selection of the two site finalists. This approach furthered two objectives. Community leaders and the public received accurate information on the nature of low-level radioactive waste and the environmental conditions appropriate for its disposal

  9. Development of the decommissioning techniques for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Tanimoto, Ken-ichi; Sugaya, Toshikatsu; Hara, Mitsuo; Kikuchi, Yutaka; Tobita, Hiroo; Enokido, Yuji

    1992-01-01

    Being developed the basement techniques such as measurement, decontamination, dismantling, remote handling and data base. For the elevating and systematizing the basement techniques, thinking over the application, forward to the facility decommissionings in the future, including the technique of waste treatment in WDF and the achievement using the dismantling and recycling technique in renewaling the research facilities. (author)

  10. Development of Barnwell as a multinational demonstration facility

    International Nuclear Information System (INIS)

    Colby, L.J. Jr.

    1977-01-01

    The author takes an existing private business venture (Barnwell) with its assets of facilities, personnel, technology and domestic business commitments (past, present, and future) and develops a role for it which will be compatible with the advancement of multinational reprocessing facilities under international control

  11. Impact of product development efforts on product introduction and product customization abilities

    DEFF Research Database (Denmark)

    Chaudhuri, Atanu; Dawar, Saloni

    2014-01-01

    This paper investigates the impact of efforts in new product development-manufacturing integration (NPDMI) on new product introduction (NPI) and product customization (PC) abilities and the moderating effects of product design complexity and importance of new product development order winners...... (NPIOW) on the above relationships. The results from the data on 136 Indian manufacturing plants show that NPDMI, product design complexity and NPIOW all have significant positive impact on NPI and PC abilities. Importance of NPIOW has a positive moderating effect on the relationship between NPDMI and PC...... ability change but product design complexity demonstrate no such effect on the above relationships....

  12. Treatment facilities, human resource development, and future prospect of particle beam therapy

    International Nuclear Information System (INIS)

    Tamaki, Tomoaki; Nakano, Takashi

    2015-01-01

    The number of particle beam therapy facilities is increasing globally. Among the countries practicing particle beam therapy, Japan is one of the leading countries in the field with four operating carbon-ion therapy facilities and ten operating proton therapy facilities. With the increasing number of particle beam therapy facilities, the human resource development is becoming extremely important, and there has been many such efforts including the Gunma University Program for Cultivating Global Leaders in Heavy Ion Therapeutics and Engineering, which aimed to educate and train the radiation oncologists, medical physicists, accelerator engineers, and radiation biologists to become global leaders in the field of particle beam therapy. In the future, the benefit and effectiveness of particle beam therapy should be discussed and elucidated objectively in a framework of comprehensive cancer care. (author)

  13. Recent developments in the effort to cure HIV infection: going beyond N = 1

    Science.gov (United States)

    Siliciano, Janet D.; Siliciano, Robert F.

    2016-01-01

    Combination antiretroviral therapy (ART) can suppress plasma HIV to undetectable levels, allowing HIV-infected individuals who are treated early a nearly normal life span. Despite the clear ability of ART to prevent morbidity and mortality, it is not curative. Even in individuals who have full suppression of viral replication on ART, there are resting memory CD4+ T cells that harbor stably integrated HIV genomes, which are capable of producing infectious virus upon T cell activation. This latent viral reservoir is considered the primary obstacle to the development of an HIV cure, and recent efforts in multiple areas of HIV research have been brought to bear on the development of strategies to eradicate or develop a functional cure for HIV. Reviews in this series detail progress in our understanding of the molecular and cellular mechanisms of viral latency, efforts to accurately assess the size and composition of the latent reservoir, the characterization and development of HIV-targeted broadly neutralizing antibodies and cytolytic T lymphocytes, and animal models for the study HIV latency and therapeutic strategies. PMID:26829622

  14. Summary Report of Summer 2009 NGSI Human Capital Development Efforts at Lawrence Livermore National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Dougan, A; Dreicer, M; Essner, J; Gaffney, A; Reed, J; Williams, R

    2009-11-16

    In 2009, Lawrence Livermore National Laboratory (LLNL) engaged in several activities to support NA-24's Next Generation Safeguards Initiative (NGSI). This report outlines LLNL's efforts to support Human Capital Development (HCD), one of five key components of NGSI managed by Dunbar Lockwood in the Office of International Regimes and Agreements (NA-243). There were five main LLNL summer safeguards HCD efforts sponsored by NGSI: (1) A joint Monterey Institute of International Studies/Center for Nonproliferation Studies-LLNL International Safeguards Policy and Information Analysis Course; (2) A Summer Safeguards Policy Internship Program at LLNL; (3) A Training in Environmental Sample Analysis for IAEA Safeguards Internship; (4) Safeguards Technology Internships; and (5) A joint LLNL-INL Summer Safeguards Lecture Series. In this report, we provide an overview of these five initiatives, an analysis of lessons learned, an update on the NGSI FY09 post-doc, and an update on students who participated in previous NGSI-sponsored LLNL safeguards HCD efforts.

  15. [Development of a questionnaire for measuring effort-reward imbalance in household and family work].

    Science.gov (United States)

    Sperlich, Stefanie; Arnhold-Kerri, Sonja; Engelke, Sonja; Noeres, Dorothee; Collatz, Jürgen; Geyer, Siegfried

    2009-05-01

    Siegrists concept of effort-reward imbalance (ERI) had been shown to be associated with a broad range of health impairments, in particular cardiovascular diseases and depression. The original questionnaire was designed to assess ERI in the field of occupational work. This paper reports on a newly developed questionnaire for the assessment of ERI in household and family work. Analogous to the original version, it is divided into two components: (i) dysbalance of effort and reward (extrinsic component), and (ii) over-commitment (intrinsic components). The questionnaire was tested with data drawn from a clinical sample of mothers (n = 567) in rehabilitation clinics. Factor analyses have reproduced the two main dimensions "effort" and "reward". Relevant aspects of reward at home were (i) meaningfulness, (ii) social gratification, (iii) appreciation from the spouse, and (iv) affection for the child. Finally a 19-item questionnaire for assessing ERI in household and family work (ERI-M) and a four-item measure for measuring parental over-commitment (Over-M) are available. The psychometric properties of both instruments are good to satisfactory.

  16. Summary Report of Summer 2009 NGSI Human Capital Development Efforts at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Dougan, A.; Dreicer, M.; Essner, J.; Gaffney, A.; Reed, J.; Williams, R.

    2009-01-01

    In 2009, Lawrence Livermore National Laboratory (LLNL) engaged in several activities to support NA-24's Next Generation Safeguards Initiative (NGSI). This report outlines LLNL's efforts to support Human Capital Development (HCD), one of five key components of NGSI managed by Dunbar Lockwood in the Office of International Regimes and Agreements (NA-243). There were five main LLNL summer safeguards HCD efforts sponsored by NGSI: (1) A joint Monterey Institute of International Studies/Center for Nonproliferation Studies-LLNL International Safeguards Policy and Information Analysis Course; (2) A Summer Safeguards Policy Internship Program at LLNL; (3) A Training in Environmental Sample Analysis for IAEA Safeguards Internship; (4) Safeguards Technology Internships; and (5) A joint LLNL-INL Summer Safeguards Lecture Series. In this report, we provide an overview of these five initiatives, an analysis of lessons learned, an update on the NGSI FY09 post-doc, and an update on students who participated in previous NGSI-sponsored LLNL safeguards HCD efforts.

  17. A Proposal to Develop a Biotechnology Information Facility

    National Research Council Canada - National Science Library

    Spalding, John

    2002-01-01

    The objective of this grant was to develop facilities and information resources that support current research in biotechnology and to meet the goal of strengthening the biological science programs at HBCUs/Mls...

  18. Development of the radioisotope production facility for the HANARO

    International Nuclear Information System (INIS)

    Lee, Ji Bok; Wu, J. S.; Baik, S. T.

    1998-06-01

    Hot cell and related facilities were developed in the RI production building of the HANARO. 1. development of concrete H/C and related components 2. development of lead H/C and related components 3. development of the hydraulic transfer system 4. development of radiation monitoring system 5. development of purification system for Co-60 storage pool 6. development of the fire fighting system for H/C 7. development of the experimental equipment. (author). 15 figs

  19. Cryogenic Fluid Storage Technology Development: Recent and Planned Efforts at NASA

    Science.gov (United States)

    Moran, Matthew E.

    2009-01-01

    Recent technology development work conducted at NASA in the area of Cryogenic Fluid Management (CFM) storage is highlighted, including summary results, key impacts, and ongoing efforts. Thermodynamic vent system (TVS) ground test results are shown for hydrogen, methane, and oxygen. Joule-Thomson (J-T) device tests related to clogging in hydrogen are summarized, along with the absence of clogging in oxygen and methane tests. Confirmation of analytical relations and bonding techniques for broad area cooling (BAC) concepts based on tube-to-tank tests are presented. Results of two-phase lumped-parameter computational fluid dynamic (CFD) models are highlighted, including validation of the model with hydrogen self pressurization test data. These models were used to simulate Altair representative methane and oxygen tanks subjected to 210 days of lunar surface storage. Engineering analysis tools being developed to support system level trades and vehicle propulsion system designs are also cited. Finally, prioritized technology development risks identified for Constellation cryogenic propulsion systems are presented, and future efforts to address those risks are discussed.

  20. Holifield Radioactive Ion Beam Facility Development and Status

    CERN Document Server

    Tatum, Alan

    2005-01-01

    The Holifield Radioactive Ion Beam Facility (HRIBF) is a national user facility dedicated to nuclear structure, reactions, and nuclear astrophysics research with radioactive ion beams (RIBs) using the isotope separator on-line (ISOL) technique. An integrated strategic plan for physics, experimental systems, and RIB production facilities have been developed and implementation of the plan is under way. Specific research objectives are defined for studying the nature of nucleonic matter, the origin of elements, solar physics, and synthesis of heavy elements. Experimental systems upgrade plans include new detector arrays and beam lines, and expansion and upgrade of existing devices. A multifaceted facility expansion plan includes a $4.75M High Power Target Laboratory (HPTL), presently under construction, to provide a facility for testing new target materials, target geometries, ion sources, and beam preparation techniques. Additional planned upgrades include a second RIB production system (IRIS2), an external axi...

  1. Accelerator-driven subcritical facility:Conceptual design development

    Science.gov (United States)

    Gohar, Yousry; Bolshinsky, Igor; Naberezhnev, Dmitry; Duo, Jose; Belch, Henry; Bailey, James

    2006-06-01

    A conceptual design development of an accelerator-driven subcritical facility has been carried out in the preparation of a joint activity with Kharkov Institute of Physics and Technology of Ukraine. The main functions of the facility are the medical isotope production and the support of the Ukraine nuclear industry. An electron accelerator is considered to drive the subcritical assembly. The neutron source intensity and spectrum have been studied. The energy deposition, spatial neutron generation, neutron utilization fraction, and target dimensions have been quantified to define the main target performance parameters, and to select the target material and beam parameters. Different target conceptual designs have been developed based the engineering requirements including heat transfer, thermal hydraulics, structure, and material issues. The subcritical assembly is designed to obtain the highest possible neutron flux level with a Keff of 0.98. Different fuel materials, uranium enrichments, and reflector materials are considered in the design process. The possibility of using low enrichment uranium without penalizing the facility performance is carefully evaluated. The mechanical design of the facility has been developed to maximize its utility and minimize the time for replacing the target and the fuel assemblies. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements, upgrades, and new missions. In addition, it has large design margins to accommodate different operating conditions and parameters. In this paper, the conceptual design and the design analyses of the facility will be presented.

  2. A brief history of the global effort to develop a preventive HIV vaccine.

    Science.gov (United States)

    Esparza, José

    2013-08-02

    Soon after HIV was discovered as the cause of AIDS in 1983-1984, there was an expectation that a preventive vaccine would be rapidly developed. In trying to achieve that goal, three successive scientific paradigms have been explored: induction of neutralizing antibodies, induction of cell mediated immunity, and exploration of combination approaches and novel concepts. Although major progress has been made in understanding the scientific basis for HIV vaccine development, efficacy trials have been critical in moving the field forward. In 2009, the field was reinvigorated with the modest results obtained from the RV144 trial conducted in Thailand. Here, we review those vaccine development efforts, with an emphasis on events that occurred during the earlier years. The goal is to provide younger generations of scientists with information and inspiration to continue the search for an HIV vaccine. Copyright © 2013 The Author. Published by Elsevier Ltd.. All rights reserved.

  3. Efforts onto nuclear research and development such as new reactor and so forth

    International Nuclear Information System (INIS)

    Onishi, Tuneji

    2000-01-01

    The Japan Atomic Power Co. which is one of specified business company on nuclear power generation, has carried out construction and operation of power plants with different types of reactor such as boiling light water reactor (BWR), pressurized light water rector (PWR), and so forth. And, by actively using technical powers and experiences accumulated before then, additional construction of a new power unit, and researches and developments on a simplified light water reactor, a future type rector, and a high breeder proof reactor have been made some efforts. Here were introduced some outlines on development of an improved type PWR, development of a new type reactor for example, deep embedded plant), future type reactor (for example, revolutionary middle and small type reactor, simplified PWR, and simplified BWR), a fast breeder reactor, and a reactor building suitable for a ship shell structure. (G.K.)

  4. National RF Test Facility as a multipurpose development tool

    International Nuclear Information System (INIS)

    McManamy, T.J.; Becraft, W.R.; Berry, L.A.

    1983-01-01

    Additions and modifications to the National RF Test Facility design have been made that (1) focus its use for technology development for future large systems in the ion cyclotron range of frequencies (ICRF), (2) expand its applicability to technology development in the electron cyclotron range of frequencies (ECRF) at 60 GHz, (3) provide a facility for ELMO Bumpy Torus (EBT) 60-GHz ring physics studies, and (4) permit engineering studies of steady-state plasma systems, including superconducting magnet performance, vacuum vessel heat flux removal, and microwave protection. The facility will continue to function as a test bed for generic technology developments for ICRF and the lower hybrid range of frequencies (LHRF). The upgraded facility is also suitable for mirror halo physics experiments

  5. Trend of development of robots for nuclear facilities

    International Nuclear Information System (INIS)

    Maki, Hideo; Sasaki, Masayoshi

    1984-01-01

    Robot technology becomes more and more important in the field of atomic energy industries. Hitachi Ltd. has energetically engaged in the development of the robot technology for nuclear facilities, recognizing these situations. The course of the development of robot technology and the robots for nuclear facilities is described. As the practical examples of the robots for nuclear facilities, there have been automatic fuel exchangers, the remotely operated automatic exchangers for control rod driving mechanism, automatic and semi-automatic ultrasonic flaw detectors and so on. As the robots for nuclear facilities under development, control rod driving mechanism disassembling and cleaning system, the volume reduction device for spent fuel channel boxes and control rods and others are reported. (Kako, I.)

  6. Development of the Holifield Radioactive Ion Beam Facility

    International Nuclear Information System (INIS)

    Tatum, B.A.

    1997-01-01

    The Holifield Radioactive Ion Beam Facility (HRIBF) construction project has been completed and the first radioactive ion beam has been successfully accelerated. The project, which began in 1992, has involved numerous facility modifications. The Oak Ridge Isochronous Cyclotron has been converted from an energy booster for heavy ion beams to a light ion accelerator with internal ion source. A target-ion source and mass analysis system have been commissioned as key components of the facility's radioactive ion beam injector to the 25MV tandem electrostatic accelerator. Beam transport lines have been completed, and new diagnostics for very low intensity beams have been developed. Work continues on a unified control system. Development of research quality radioactive beams for the nuclear structure and nuclear astrophysics communities continues. This paper details facility development to date

  7. Decommissioning Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kang, Y. A.; Kim, G. H.

    2007-06-01

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely

  8. Decommissioning Technology Development for Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. W.; Kang, Y. A.; Kim, G. H. (and others)

    2007-06-15

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely.

  9. Facilities for Research and Development of Medical Radioisotopes

    International Nuclear Information System (INIS)

    Shin, Byung Chul; Choung, Won Myung; Park, Jin Ho

    2003-03-01

    This study is carried out by KAERI(Korea Atomic Energy Research Institute) to construct the basic facilities for development and production of medical radioisotope. For the characteristics of radiopharmaceuticals, the facilities should be complied with the radiation shield and GMP(Good Manufacturing Practice) guideline. The KAERI, which has carried out the research and development of the radiopharmaceuticals, made a design of these facilities and built them in the HANARO Center and opened the technique and facilities to the public to give a foundation for research and development of the radiopharmaceuticals. In the facilities, radiation shielding utilities and GMP instruments were set up and their operating manuals were documented. Every utilities and instruments were performed the test to confirm their efficiency and the approval for use of the facilities will be achieved from MOST(Ministry of Science and Technology). It is expected to be applied in development of therapeutic radioisotope such as Re-188 generator and Ho-166, as well as Tc-99m generator and Sr-89 chloride for medical use. And it also looks forward to the contribution to the related industry through the development of product in high demand and value

  10. Sizing and melting development activities using noncontaminated metal at the Waste Experimental Reduction Facility

    International Nuclear Information System (INIS)

    Larsen, M.M.; Logan, J.A.

    1984-05-01

    EG and G Idaho, Inc., has established the Waste Experimental Reduction Facility (WERF) at the Idaho National Engineering Laboratory (INEL) to develop the capability to reduce the volume that low-level beta/gamma wastes occupy at the disposal site. The work effort at WERF includes a waste sizing development activity (WSDA), a waste melting development activity (WMDA), and a waste incineration development activity (WIDA). This report describes work and developments to date in the WSDA and WMDA with noncontaminated metallic waste in preparation for operations at WERF involving beta/gamma-contaminated metal

  11. Forge: a short pulse x-ray diagnostic development facility

    International Nuclear Information System (INIS)

    Stradling, G.L.; Hurry, T.R.; Denbow, E.R.; Selph, M.M.; Ameduri, F.P.

    1985-01-01

    A new short pulse x-ray calibration facility has been brought on line at Los Alamos. This facility is being used for the development, testing and calibration of fast x-ray diagnostic systems. The x-ray source consists of a moderate size, sub-nanosecond laser focused at high intensity on an appropriate target material to generate short pulses of x-ray emission from the resulting plasma. Dynamic performance parameters of fast x-ray diagnostic instruments, such as x-ray streak cameras, can be conveniently measured using this facility

  12. Participation in multilateral effort to develop high performance integrated CPC evacuated collectors

    Science.gov (United States)

    Winston, R.; Ogallagher, J. J.

    1992-05-01

    The University of Chicago Solar Energy Group has had a continuing program and commitment to develop an advanced evacuated solar collector integrating nonimaging concentration into its design. During the period from 1985-1987, some of our efforts were directed toward designing and prototyping a manufacturable version of an Integrated Compound Parabolic Concentrator (ICPC) evacuated collector tube as part of an international cooperative effort involving six organizations in four different countries. This 'multilateral' project made considerable progress towards a commercially practical collector. One of two basic designs considered employed a heat pipe and an internal metal reflector CPC. We fabricated and tested two large diameter (125 mm) borosilicate glass collector tubes to explore this concept. The other design also used a large diameter (125 mm) glass tube but with a specially configured internal shaped mirror CPC coupled to a U-tube absorber. Performance projections in a variety of systems applications using the computer design tools developed by the International Energy Agency (IEA) task on evacuated collectors were used to optimize the optical and thermal design. The long-term goal of this work continues to be the development of a high efficiency, low cost solar collector to supply solar thermal energy at temperatures up to 250 C. Some experience and perspectives based on our work are presented and reviewed. Despite substantial progress, the stability of research support and the market for commercial solar thermal collectors were such that the project could not be continued. A cooperative path involving university, government, and industrial collaboration remains the most attractive near term option for developing a commercial ICPC.

  13. Industry's efforts toward technology development related to aging management of PWR plants

    International Nuclear Information System (INIS)

    Tanaka, Hideo

    2010-01-01

    The term, 'aging plants', which refers to nuclear power plants operating more than 30 years, has become popular among local residents around nuclear power plants as well as among the media. The term 'aging' was first used in the title of the document issued by Agency of Natural Resources and Energy in 1996, 'The Basic Concept of Aging Management'. In addressing aging degradation, it was a matter of question which measure of time (date, month or year) should be used as a unit to consider an events. Although the aging plant was defined as a plant operating more than 30 years, the mode and timing of aging degradation depend on the environment and service conditions under which a component has been operating. Previous efforts made by related parties have contributed to the prevention of potential aging events which may challenge the reactor safety. Owing to such efforts, causes of some events attributable to defective design have been clarified and preventive maintenance measures, including the replacement and mitigation, have been taken accordingly. As a result, the number of events resulting from such aging phenomena has been reduced. On other other hand, the events caused by aging phenomena attributable to manufacturing processes (welding, surface treatment, etc.), which hardly emerge, are slightly increasing. There have been many cases that a shorter weld line due to lack of penetration in the narrow gap has been led to fatigue cracking. More recently, incidents of stress corrosion cracking due to work hardening and local tensile stresses on the surface have been observed. It should be noted that an effort to analyze not only the phenomena but also the mechanisms of the above events to clarify the root causes can improve the quality of preventive maintenance by means of rolling-out the analytical results to relevant plants. This paper introduces valuable experiences with the application of the results of technology development regarding to aging degradation of

  14. Development of cloud-operating platform for detention facility design

    Science.gov (United States)

    Tun Lee, Kwan; Hung, Meng-Chiu; Tseng, Wei-Fan; Chan, Yi-Ping

    2017-04-01

    In the past 20 years, the population of Taiwan has accumulated in urban areas. The land development has changed the hydrological environment and resulted in the increase of surface runoff and shortened the time to peak discharge. The change of runoff characteristics increases the flood risk and reduces resilient ability of the city during flood. Considering that engineering measures may not be easy to implement in populated cities, detention facilities set on building basements have been proposed to compromise the increase of surface runoff resulting from development activities. In this study, a web-based operational platform has been developed to integrate the GIS technologies, hydrological analyses, as well as relevant regulations for the design of detention facilities. The design procedure embedded in the system includes a prior selection of type and size of the detention facility, integrated hydrological analysis for the developing site, and inspection of relevant regulations. After login the platform, designers can access the system database to retrieve road maps, land use coverages, and storm sewer information. Once the type, size, inlet, and outlet of the detention facility are assigned, the system can acquire the rainfall intensity-duration-frequency information from adjacent rain gauges to perform hydrological analyses for the developing site. The increase of the runoff volume due to the development and the reduction of the outflow peak through the construction of the detention facility can be estimated. The outflow peak at the target site is then checked with relevant regulations to confirm the suitability of the detention facility design. The proposed web-based platform can provide a concise layout of the detention facility and the drainageway of the developing site on a graphical interface. The design information can also be delivered directly through a web link to authorities for inspecting to simplify the complex administrative procedures.

  15. 78 FR 43889 - Synergizing Efforts in Standards Development for Cellular Therapies and Regenerative Medicine...

    Science.gov (United States)

    2013-07-22

    ... regenerative medicine products have generated a great deal of interest. These efforts include standards... is done to coordinate the various existing efforts. In the public workshop, FDA hopes to bring...

  16. Investigating the Nature of Relationship between Software Size and Development Effort

    OpenAIRE

    Bajwa, Sohaib-Shahid

    2008-01-01

    Software effort estimation still remains a challenging and debatable research area. Most of the software effort estimation models take software size as the base input. Among the others, Constructive Cost Model (COCOMO II) is a widely known effort estimation model. It uses Source Lines of Code (SLOC) as the software size to estimate effort. However, many problems arise while using SLOC as a size measure due to its late availability in the software life cycle. Therefore, a lot of research has b...

  17. Research and development efforts relative to superconducting materials. Final report. [Nb/sub 3/Sn tapes

    Energy Technology Data Exchange (ETDEWEB)

    Adam, E; Beishcher, P; Marancik, W; Lucariello, R; Young, M

    1976-04-01

    Three processes for the production of low-loss superconducting tapes of Nb/sub 3/Sn were investigated. They are the rolled-bronze process, the electron beam (EB) bronze deposition process, and the high-rate sputtering process. Shortly after the start of the investigation, effort on the last two processes was suspended because the process-development time that would be needed to arrive at a suitable transmission-line tape appeared most likely to be the shortest with the rolled-bronze process. Long lengths of Nb/sub 3/Sn tapes were prepared by the rolled-bronze process from extruded and rolled bronze-clad niobium billets. Tapes were stabilized by removing the bronze layer after reaction and then coating the exposed Nb/sub 3/Sn with high-purity copper by EB evaporation. Several meters of high quality Nb/sub 3/Sn tapes were produced by the rolled-bronze process. Even when the tapes were stabilized with copper, the losses were as low as 1.8 ..mu..W/cm/sup 2/ at 4.2 K and a surface current density of 500 rms A/cm. Despite early curtailment of the effort on the EB bronze-deposition process, short samples of Nb/sub 3/Sn tapes were produced.

  18. The European efforts in development of new high temperature rotor materials - COST536

    Energy Technology Data Exchange (ETDEWEB)

    Kern, T.U. [Siemens Energy, Muehlheim (Germany); Mayer, K.H. [Alstom Power, Nuernberg (Germany); Donth, B. [Saarschmiede, Voelklingen (Germany); Zeiler, G. [Boehler Schmiedetechnik, Kapfenberg (Austria); Di Gianfrancesco, A. [CSM, Roma (Italy)

    2010-07-01

    Despite the ongoing efforts to increase the amount of available alternative energy sources, fossil fuels such as lignite and hard coal will remain important for the energy mix and sustainability of energy supply. Fossil-fuelled Steam Power Plants (SSP's) or Combined Cycle power plants (CCPP's) will also continue to supply a significant portion of our energy needs. Within the frame of European COST536, a new project was installed with the aim of Alloy development for Critical Components of Environmentally friendly Power planTs (ACCEPT) aiming for material solutions for steam conditions up to 650 C. Martensitic materials should be used for thick-walled components to maintain high operational flexibility of such large plants. Rotors, casings, bolts, tubes, pipes, and water walls, are the critical components under current investigation. The class of the 9-12%Cr steels offers the highest potential to meet the required property levels for critical components such as rotor forgings. Therefore a significant effort to increase the application temperature of these steels was and is the focus of studies within Europe. Although there are 600 C materials already being successfully utilised in a number of advanced European power plants, further improvement in creep strength is being achieved by the addition of Boron and a well balanced Co content. Full-size prototype components are now being tested. New ideas to improve the behaviour and increase the application temperatures are under investigation. Results are reported here. (orig.)

  19. Stop the Bleeding: the Development of a Tool to Streamline NASA Earth Science Metadata Curation Efforts

    Science.gov (United States)

    le Roux, J.; Baker, A.; Caltagirone, S.; Bugbee, K.

    2017-12-01

    The Common Metadata Repository (CMR) is a high-performance, high-quality repository for Earth science metadata records, and serves as the primary way to search NASA's growing 17.5 petabytes of Earth science data holdings. Released in 2015, CMR has the capability to support several different metadata standards already being utilized by NASA's combined network of Earth science data providers, or Distributed Active Archive Centers (DAACs). The Analysis and Review of CMR (ARC) Team located at Marshall Space Flight Center is working to improve the quality of records already in CMR with the goal of making records optimal for search and discovery. This effort entails a combination of automated and manual review, where each NASA record in CMR is checked for completeness, accuracy, and consistency. This effort is highly collaborative in nature, requiring communication and transparency of findings amongst NASA personnel, DAACs, the CMR team and other metadata curation teams. Through the evolution of this project it has become apparent that there is a need to document and report findings, as well as track metadata improvements in a more efficient manner. The ARC team has collaborated with Element 84 in order to develop a metadata curation tool to meet these needs. In this presentation, we will provide an overview of this metadata curation tool and its current capabilities. Challenges and future plans for the tool will also be discussed.

  20. Upgrade and Development of Nuclear Data Production Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-04-15

    It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: (1) upgrade the electron linac, (2) collimators inside the TOF beam pipe, (3) the development and installation of an automatic sample changer, (4) the extension of the TOF beam line, and (5) the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students

  1. Upgrade and development of nuclear data production test facility

    Energy Technology Data Exchange (ETDEWEB)

    Namkung, Won; Ko, I. S.; Cho, M. H.; Lee, Y. S.; Kang, H. S. [Pohang Univ. of Science and Technology, Pohang (Korea, Republic of); Kim, G. N. [Kyungpook National Univ., Daegu (Korea, Republic of); Koh, S. K. [Univ. of Ulsan, Ulsan (Korea, Republic of); Ro, T. I. [Donga Univ., Busan (Korea, Republic of); Choi, G. U. [Korea Research Institute of Standards and Science, Daejeon (Korea, Republic of)

    2005-04-15

    It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: upgrade the electron linac, collimators inside the TOF beam pipe, the development and installation of an automatic sample changer, the extension of the TOF beam line, and the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students.

  2. Detecting Development Pattern of Urban Business Facilities Using Reviews Data

    Directory of Open Access Journals (Sweden)

    JIANG Botao

    2015-09-01

    Full Text Available This paper reveals and utilizes the growing power of online customer reviews in the space and time context. The location of commercial facilities and online customer reviews offered by Dianping.com provide an important data source for the study of spatial and temporal dynamics of urban commercial facilities. The constraints of road network are taken into account towards computing the density of urban commercial facilities and associated online customer reviews, as well as their spatial distribution, temporal trend, and the coupling relationship between facility number and stratification level. This paper maps the spatial distribution of commercial facilities onto the nearby road network, reflecting the influences of the locations, number and satisfaction levels of other commercial facilities across various street types. Because more and more customers tend to make a final shopping decision by sorting through search results by ratings and feedback, the research conducted in this paper can provide the proof for quantitative evaluation of urban planning on commercial facility development.

  3. Developing a model lifeline protection program for DOE facilities

    International Nuclear Information System (INIS)

    Lowing, A.N.

    1996-01-01

    A National Lifeline Standard Development Program is currently being conducted by FEMA and NIST. The Department of Energy is following these developments and supplementing them to meet Life-Safety and mission requirements for all DOE facilities as part of the Natural Phenomena Hazards Mitigation Plan. The task will be overseen by a DOE management team with technical guidance provided by a Steering Group of management and operating contractor representatives. The DOE will participate in the federal program by conducting a workshop on lifeline protection issues, developing an overall plan, organizing a Steering Group, and conducting a pilot study at a DOE facility

  4. Development of a facility using robotics for testing automation of inertial instruments

    Science.gov (United States)

    Greig, Joy Y.; Lamont, Gary B.; Biezad, Daniel J.; Lewantowicz, Zdsislaw H.; Greig, Joy Y.

    1987-01-01

    The Integrated Robotics System Simulation (ROBSIM) was used to evaluate the performance of the PUMA 560 arm as applied to testing of inertial sensors. Results of this effort were used in the design and development of a feasibility test environment using a PUMA 560 arm. The implemented facility demonstrated the ability to perform conventional static inertial instrument tests (rotation and tumble). The facility included an efficient data acquisitions capability along with a precision test servomechanism function resulting in various data presentations which are included in the paper. Analysis of inertial instrument testing accuracy, repeatability and noise characteristics are provided for the PUMA 560 as well as for other possible commercial arm configurations. Another integral aspect of the effort was an in-depth economic analysis and comparison of robot arm testing versus use of contemporary precision test equipment.

  5. Development of anti-biofouling methods for gate facilities

    International Nuclear Information System (INIS)

    Fukuoka, Mari; Akamine, Kenichi; Iai, Yuuichi; Takatoo, Norihiro; Fukushima, Noriaki

    2016-01-01

    In the maintenance and management of gate facilities, a large sum of money and labor are required to remove and clean organisms that attach themselves to the facilities. That is why we developed two anti-biofouling systems, one that uses a weak electric current and another that uses ultrasonic waves. We carried out basic examinations and actual environment examinations to verify the effects of these methods. As a result, it has been confirmed that these methods effectively anti-foul the parts they are applied to, and that they can be used on gate facilities. In the future, we will evaluate their adaptability to aqueducts, such as those used in thermal and nuclear power plants, and marine structures, such as floating breakwaters, in addition to gate facilities. (author)

  6. Neutronic analyses and tools development efforts in the European DEMO programme

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, U., E-mail: ulrich.fischer@kit.edu [Association KIT-Euratom, Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Bachmann, C. [European Fusion Development Agreement (EFDA), Garching (Germany); Bienkowska, B. [Association IPPLM-Euratom, IPPLM Warsaw/INP Krakow (Poland); Catalan, J.P. [Universidad Nacional de Educación a Distancia (UNED), Madrid (Spain); Drozdowicz, K.; Dworak, D. [Association IPPLM-Euratom, IPPLM Warsaw/INP Krakow (Poland); Leichtle, D. [Association KIT-Euratom, Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Fusion for Energy (F4E), Barcelona (Spain); Lengar, I. [MESCS-JSI, Ljubljana (Slovenia); Jaboulay, J.-C. [CEA, DEN, Saclay, DM2S, SERMA, F-91191 Gif-sur-Yvette (France); Lu, L. [Association KIT-Euratom, Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Moro, F. [Associazione ENEA-Euratom, ENEA Fusion Division, Frascati (Italy); Mota, F. [Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT), Madrid (Spain); Sanz, J. [Universidad Nacional de Educación a Distancia (UNED), Madrid (Spain); Szieberth, M. [Budapest University of Technology and Economics (BME), Budapest (Hungary); Palermo, I. [Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT), Madrid (Spain); Pampin, R. [Fusion for Energy (F4E), Barcelona (Spain); Porton, M. [Euratom/CCFE Fusion Association, Culham Science Centre for Fusion Energy (CCFE), Culham (United Kingdom); Pereslavtsev, P. [Association KIT-Euratom, Karlsruhe Institute of Technology (KIT), Karlsruhe (Germany); Ogando, F. [Universidad Nacional de Educación a Distancia (UNED), Madrid (Spain); Rovni, I. [Budapest University of Technology and Economics (BME), Budapest (Hungary); and others

    2014-10-15

    Highlights: •Evaluation of neutronic tools for application to DEMO nuclear analyses. •Generation of a DEMO model for nuclear analyses based on MC calculations. •Nuclear analyses of the DEMO reactor equipped with a HCLL-type blanket. -- Abstract: The European Fusion Development Agreement (EFDA) recently launched a programme on Power Plant Physics and Technology (PPPT) with the aim to develop a conceptual design of a fusion demonstration reactor (DEMO) addressing key technology and physics issues. A dedicated part of the PPPT programme is devoted to the neutronics which, among others, has to define and verify requirements and boundary conditions for the DEMO systems. The quality of the provided data depends on the capabilities and the reliability of the computational tools. Accordingly, the PPPT activities in the area of neutronics include both DEMO nuclear analyses and development efforts on neutronic tools including their verification and validation. This paper reports on first neutronics studies performed for DEMO, and on the evaluation and further development of neutronic tools.

  7. Neutronic analyses and tools development efforts in the European DEMO programme

    International Nuclear Information System (INIS)

    Fischer, U.; Bachmann, C.; Bienkowska, B.; Catalan, J.P.; Drozdowicz, K.; Dworak, D.; Leichtle, D.; Lengar, I.; Jaboulay, J.-C.; Lu, L.; Moro, F.; Mota, F.; Sanz, J.; Szieberth, M.; Palermo, I.; Pampin, R.; Porton, M.; Pereslavtsev, P.; Ogando, F.; Rovni, I.

    2014-01-01

    Highlights: •Evaluation of neutronic tools for application to DEMO nuclear analyses. •Generation of a DEMO model for nuclear analyses based on MC calculations. •Nuclear analyses of the DEMO reactor equipped with a HCLL-type blanket. -- Abstract: The European Fusion Development Agreement (EFDA) recently launched a programme on Power Plant Physics and Technology (PPPT) with the aim to develop a conceptual design of a fusion demonstration reactor (DEMO) addressing key technology and physics issues. A dedicated part of the PPPT programme is devoted to the neutronics which, among others, has to define and verify requirements and boundary conditions for the DEMO systems. The quality of the provided data depends on the capabilities and the reliability of the computational tools. Accordingly, the PPPT activities in the area of neutronics include both DEMO nuclear analyses and development efforts on neutronic tools including their verification and validation. This paper reports on first neutronics studies performed for DEMO, and on the evaluation and further development of neutronic tools

  8. Reliability database development and plant performance improvement effort at Korea Hydro and Nuclear Power Co

    International Nuclear Information System (INIS)

    Oh, S. J.; Hwang, S. W.; Na, J. H.; Lim, H. S.

    2008-01-01

    Nuclear utilities in recent years have focused on improved plant performance and equipment reliability. In U.S., there is a movement toward process integration. Examples are INPO AP-913 equipment reliability program and the standard nuclear performance model developed by NEI. Synergistic effect from an integrated approach can be far greater than as compared to individual effects from each program. In Korea, PSA for all Korean NPPs (Nuclear Power Plants) has been completed. Plant performance monitoring and improvement is an important goal for KHNP (Korea Hydro and Nuclear Power Company) and a risk monitoring system called RIMS has been developed for all nuclear plants. KHNP is in the process of voluntarily implementing maintenance rule program similar to that in U.S. In the future, KHNP would like to expand the effort to equipment reliability program and to achieve highest equipment reliability and improved plant performance. For improving equipment reliability, the current trend is moving toward preventive/predictive maintenance from corrective maintenance. With the emphasis on preventive maintenance, the failure cause and operation history and environment are important. Hence, the development of accurate reliability database is necessary. Furthermore, the database should be updated regularly and maintained as a living program to reflect the current status of equipment reliability. This paper examines the development of reliability database system and its application of maintenance optimization or Risk Informed Application (RIA). (authors)

  9. Considerations in the development and implementation of a maintenance robot for nuclear power facilities

    International Nuclear Information System (INIS)

    Rohrabacher, A.; Carlton, R.; Gelhaus, F.

    1987-01-01

    The Nuclear Power Division of the Electric Power Research Institute (EPRI) began its automated nuclear plant maintenance research (research project 2232) in 1982 with surveys of domestic and Japanese ongoing and potential uses of robotic systems in nuclear power facilities. After studying these potential research areas, EPRI initiated a three-pronged effort. All surveys concluded that a mobile system for general environmental, visual, and auto surveillance would be beneficial, and EPRI contracted for the development and evaluation of the Surveyor robot. Work also began to catalog existing systems and to quantify the methodology that a utility could use to optimally complete the plant-mission, robot-system selection process. The conceptualizing phase of the effort defined the necessary physical attributes for the machine to perform a variety of maintenance tasks. Characteristics such as mobility, strength, conditions of service, materials of construction, tool functional requirements, facility interfaces, and operator interface were defined to the extent practical. Substantial versatility is required for the variability of the targeted maintenance tasks and for the variability of facility layouts and designs found throughout the nuclear industry. A key contribution to this development effort comes from the project's Utility Advisors Group. The contract's host utility provides membership to lead this group, and that company will train in the use of the machine for 6 months prior to utilizing it in their power plant for 2 yr

  10. Efforts to develop a cultured sponge cell line: revisiting an intractable problem.

    Science.gov (United States)

    Grasela, James J; Pomponi, Shirley A; Rinkevich, Buki; Grima, Jennifer

    2012-01-01

    Residents of the marine environment, sponges (Porifera) have the ability to produce organic compounds known as secondary metabolites, which are not directly involved in the normal growth, development, or reproduction of an organism. Because of their sessile nature, the production of these bioactive compounds has been interpreted as a functional adaptation to serve in an important survival role as a means to counter various environmental stress factors such as predation, overgrowth by fouling organisms, or competition for limited space. Regardless of the reasons for this adaptation, a variety of isolated compounds have already proven to demonstrate remarkable anticancer, fungicidal, and antibiotic properties. A major obstacle to the isolation and production of novel compounds from sponges is the lack of a large, reliable source of sponge material. Sponge collection from the sea would be environmentally detrimental to the already stressed and sparse sponge populations. Sponge production in an aquaculture setting might appear to be an ideal alternative but would also be cost-ineffective and sponge growth is extremely slow. A third approach involves the development of a sponge cell culture system capable of producing the necessary cell numbers to harvest for research purposes as well as for the eventual commercial-scale production of promising bioactive compounds. Unfortunately, little progress has been made in this direction other than the establishment of temporary cultures containing aggregates and fragments of cells. One impediment toward successful sponge cell culture might be ascribed to a lack of published knowledge of failed methodologies, and thus, time and effort is wasted on continued reinvention of the same methods and procedures. Consequently, we have undertaken here to chart some of our unsuccessful research efforts, our methodology, and results to provide the sponge research community with knowledge to assist them to better avoid taking the same failed

  11. Development of a fault test experimental facility model using Matlab

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Iraci Martinez; Moraes, Davi Almeida, E-mail: martinez@ipen.br, E-mail: dmoraes@dk8.com.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The Fault Test Experimental Facility was developed to simulate a PWR nuclear power plant and is instrumented with temperature, level and pressure sensors. The Fault Test Experimental Facility can be operated to generate normal and fault data, and these failures can be added initially small, and their magnitude being increasing gradually. This work presents the Fault Test Experimental Facility model developed using the Matlab GUIDE (Graphical User Interface Development Environment) toolbox that consists of a set of functions designed to create interfaces in an easy and fast way. The system model is based on the mass and energy inventory balance equations. Physical as well as operational aspects are taken into consideration. The interface layout looks like a process flowchart and the user can set the input variables. Besides the normal operation conditions, there is the possibility to choose a faulty variable from a list. The program also allows the user to set the noise level for the input variables. Using the model, data were generated for different operational conditions, both under normal and fault conditions with different noise levels added to the input variables. Data generated by the model will be compared with Fault Test Experimental Facility data. The Fault Test Experimental Facility theoretical model results will be used for the development of a Monitoring and Fault Detection System. (author)

  12. Development of a fault test experimental facility model using Matlab

    International Nuclear Information System (INIS)

    Pereira, Iraci Martinez; Moraes, Davi Almeida

    2015-01-01

    The Fault Test Experimental Facility was developed to simulate a PWR nuclear power plant and is instrumented with temperature, level and pressure sensors. The Fault Test Experimental Facility can be operated to generate normal and fault data, and these failures can be added initially small, and their magnitude being increasing gradually. This work presents the Fault Test Experimental Facility model developed using the Matlab GUIDE (Graphical User Interface Development Environment) toolbox that consists of a set of functions designed to create interfaces in an easy and fast way. The system model is based on the mass and energy inventory balance equations. Physical as well as operational aspects are taken into consideration. The interface layout looks like a process flowchart and the user can set the input variables. Besides the normal operation conditions, there is the possibility to choose a faulty variable from a list. The program also allows the user to set the noise level for the input variables. Using the model, data were generated for different operational conditions, both under normal and fault conditions with different noise levels added to the input variables. Data generated by the model will be compared with Fault Test Experimental Facility data. The Fault Test Experimental Facility theoretical model results will be used for the development of a Monitoring and Fault Detection System. (author)

  13. Development efforts on helium vessel for 5 cell - 650 MHz SRF cavity at RRCAT

    International Nuclear Information System (INIS)

    Kumar, Abhay; Kumar, Pankaj; Sandha, R.S.; Dutta, Subhajit; Soni, Rakesh; Dwivedi, Jishnu; Thakurta, A.C.; Bhatnagar, V.K.; Mundra, G.

    2011-01-01

    The work focuses on the development of helium vessel which houses a 5 cell - 650 MHz SRF niobium cavity and serves as a helium bath to maintain the cavity at 2 K. The vessel has provision for changing the axial length of the cavity for tuning purpose by using a tuning mechanism and a large bellow. Titanium has been chosen as a material of construction of the vessel due to its coefficient of thermal expansion being close to that of niobium. Efforts have been initiated to understand the functional requirements, design requirements, acceptance criteria for design and analysis, non-destructive examination requirements, inspection and testing requirements, manufacturing technology of the titanium vessel and its integration with the SRF cavity. The welding assumes a special significance as titanium is highly reactive and ductility of the weld joint is lost in the presence of air and other impurities. A trial vessel has been conceptualised having typical sizes and geometries. The manufacturing features of vessel are based on ASME B and PV Code, Section VIII Division-1 and manufacturing of this vessel has been started at an Indian industry. Quality assurance plan for this work is developed. The paper describes the work done at RRCAT on the functional and integration requirements, overall design requirements, design methodology to achieve code conformance, manufacturing technology and QAP being used in the development of helium vessel. (author)

  14. Development of the flow control irradiation facility for JOYO

    International Nuclear Information System (INIS)

    Soroi, Masatoshi; Miyakawa, Shun-ichi

    1998-05-01

    This report describes the present situation and problems with the development of the flow control irradiation facility (FLORA). The purpose of FLORA is to run the cladding breach (RTCB) irradiation test under loss of flow conditions in the experimental fast reactor 'JOYO'. FLORA is a facility like FPTF (Fuel Performance Test Facility) plus BFTF (Breached Fuel Test Facility) in EBR-II, USA. The technical feature of FLORA is its annular linear induction pump (A-LIP), which was developed in response to a need identified through the experiences in the mechanical flow control of FPTF. We have already designed the basic system facility of FLORA for the JOYO MK-II core. However, to put FLORA to practical use in the future, we have to confirm the stability of the JOYO MK-III core condition, solve problems and improve the design. We are going to freeze and review the FLORA project, taking into consideration the fuel development situation and the research project of JOYO MK-III core. (J.P.N.)

  15. Development of Experimental Facilities for Advanced Spent Fuel Management Technology

    Energy Technology Data Exchange (ETDEWEB)

    You, G. S.; Jung, W. M.; Ku, J. H. [and others

    2004-07-01

    The advanced spent fuel management process(ACP), proposed to reduce the overall volume of the PWR spent fuel and improve safety and economy of the long-term storage of spent fuel, is under research and development. This technology convert spent fuels into pure metal-base uranium with removing the highly heat generating materials(Cs, Sr) efficiently and reducing of the decay heat, volume, and radioactivity from spent fuel by 1/4. In the next phase(2004{approx}2006), the demonstration of this technology will be carried out for verification of the ACP in a laboratory scale. For this demonstration, the hot cell facilities of {alpha}-{gamma} type and auxiliary facilities are required essentially for safe handling of high radioactive materials. As the hot cell facilities for demonstration of the ACP, a existing hot cell of {beta}-{gamma} type will be refurbished to minimize construction expenditures of hot cell facility. In this study, the design requirements are established, and the process detail work flow was analysed for the optimum arrangement to ensure effective process operation in hot cell. And also, the basic and detail design of hot cell facility and process, and safety analysis was performed to secure conservative safety of hot cell facility and process.

  16. Feasibility of energy justice: Exploring national and local efforts for energy development in Nepal

    International Nuclear Information System (INIS)

    Islar, Mine; Brogaard, Sara; Lemberg-Pedersen, Martin

    2017-01-01

    The energy justice framework serves as an important decision-making tool in order to understand how different principles of justice can inform energy systems and policies. The realization of the urgency of providing modern energy technology and services particularly to rural areas has prompted both the Nepalese government and development institutions to focus on community-run renewable energy facilities. It is argued that off-grid and micro-scale energy development offers an alternative path to fossil-fuel use and top-down resource management as they democratize the grid and increase marginalized communities' access to renewable energy, education and health care. However, Nepal's energy development is also heavily influenced by demands from the fast-growing economies of neighboring countries such as China and India. As a result, this article evaluates the Nepalese national energy policies by applying the key aspects of the energy justice framework and showing the feasibility constraints due to geopolitical and biophysical factors to the implementation of energy just policies in this developing country context. The empirical evidence is derived from interviews during a one-month fieldwork in the Lalitpur and Katmandu districts of Nepal, site-visits, discourse analysis of expert statements, government policies and newspaper articles as well literature review on peer-review articles. - Highlights: • Energy justice framework can be used as a decision-making tool. • Energy transitions need to be understood from multiple perspectives. • Justice principles may face geopolitical, biophysical and ethical feasibility constraints. • The implementation of energy justice principles requires attention to the problem of agency.

  17. EURATOM safeguards efforts in the development of spent fuel verification methods by non-destructive assay

    Energy Technology Data Exchange (ETDEWEB)

    Matloch, L.; Vaccaro, S.; Couland, M.; De Baere, P.; Schwalbach, P. [Euratom, Communaute europeenne de l' energie atomique - CEEA (European Commission (EC))

    2015-07-01

    The back end of the nuclear fuel cycle continues to develop. The European Commission, particularly the Nuclear Safeguards Directorate of the Directorate General for Energy, implements Euratom safeguards and needs to adapt to this situation. The verification methods for spent nuclear fuel, which EURATOM inspectors can use, require continuous improvement. Whereas the Euratom on-site laboratories provide accurate verification results for fuel undergoing reprocessing, the situation is different for spent fuel which is destined for final storage. In particular, new needs arise from the increasing number of cask loadings for interim dry storage and the advanced plans for the construction of encapsulation plants and geological repositories. Various scenarios present verification challenges. In this context, EURATOM Safeguards, often in cooperation with other stakeholders, is committed to further improvement of NDA methods for spent fuel verification. In this effort EURATOM plays various roles, ranging from definition of inspection needs to direct participation in development of measurement systems, including support of research in the framework of international agreements and via the EC Support Program to the IAEA. This paper presents recent progress in selected NDA methods. These methods have been conceived to satisfy different spent fuel verification needs, ranging from attribute testing to pin-level partial defect verification. (authors)

  18. Development of Mix Design Method in Efforts to Increase Concrete Performance Using Portland Pozzolana Cement (PPC)

    Science.gov (United States)

    Krisnamurti; Soehardjono, A.; Zacoeb, A.; Wibowo, A.

    2018-01-01

    Earthquake disaster can cause infrastructure damage. Prevention of human casualties from disasters should do. Prevention efforts can do through improving the mechanical performance of building materials. To achieve high-performance concrete (HPC), usually used Ordinary Portland Cement (OPC). However, the most widely circulating cement types today are Portland Pozzolana Cement (PPC) or Portland Composite Cement (PCC). Therefore, the proportion of materials used in the HPC mix design needs to adjust to achieve the expected performance. This study aims to develop a concrete mix design method using PPC to fulfil the criteria of HPC. The study refers to the code/regulation of concrete mixtures that use OPC based on the results of laboratory testing. This research uses PPC material, gravel from Malang area, Lumajang sand, water, silica fume and superplasticizer of a polycarboxylate copolymer. The analyzed information includes the investigation results of aggregate properties, concrete mixed composition, water-binder ratio variation, specimen dimension, compressive strength and elasticity modulus of the specimen. The test results show that the concrete compressive strength achieves value between 25 MPa to 55 MPa. The mix design method that has developed can simplify the process of concrete mix design using PPC to achieve the certain desired performance of concrete.

  19. Implementation of a protein profiling platform developed as an academic-pharmaceutical industry collaborative effort.

    Science.gov (United States)

    Végvári, Akos; Magnusson, Mattias; Wallman, Lars; Ekström, Simon; Bolmsjö, Gunnar; Nilsson, Johan; Miliotis, Tasso; Ostling, Jörgen; Kjellström, Sven; Ottervald, Jan; Franzén, Bo; Hultberg, Hans; Marko-Varga, György; Laurell, Thomas

    2008-06-01

    As much attention has devoted to the proteome research during the last few years, biomarker discovery has become an increasingly hot area, potentially enabling the development of new assays for diagnosis and prognosis of severe diseases. This is the field of research interest where efforts originating from both academic and industrial groups should jointly work on solutions. In this paper, we would like to demonstrate the fruitful combination of both research domains where the scientific crossroads sprout fresh ideas from the basic research domain and how these are refined and tethered to industrial standards. We will present an approach that is based on novel microfluidic devices, utilizing their benefits in processing small-volume samples. Our biomarker discovery strategy, built around this platform, involves optimized samples processing (based on SPE and sample enrichment) and fast MALDI-MS readout. The identification of novel biomarkers at low-abundance level has been achieved by the utilization of a miniaturized sample handling platform, which offers clean-up and enrichment of proteins in one step. Complete automation has been realized in the form of a unique robotic instrumentation that is able to extract and transfer 96 samples onto standard MALDI target plates with high throughput. The developed platform was operated with a 60 sample turnaround per hour allowing sensitivities in femtomol regions of medium- and low-abundant target proteins from clinical studies on samples of multiple sclerosis and gastroesophageal reflux disease. Several proteins have been identified as new biomarkers from cerebrospinal fluid and esophagus epithelial cells.

  20. Recent developments in the target facilities at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Greene, J.P.; Thomas, G.E.

    1989-01-01

    A description is given of recent developments in the target facility at Argonne National Laboratory (ANL). Highlights include equipment upgrades which enable us to provide enhanced capabilities for support of the Argonne Heavy-Ion ATLAS Accelerator Project. Also, future plans and additional equipment acquisitions will be discussed. (orig.)

  1. Development of cables for nuclear fuel processing facilities

    International Nuclear Information System (INIS)

    Kamimura, Seiji; Seki, Ikuo; Yamamoto, Yasuaki; Matsuyama, Shigeki; Endo, Shigeru; Yagi, Toshiaki; Kawakami, Waichiro.

    1988-01-01

    Accompanying the development of nuclear power stations, the expansion and repletion of the facilities for nuclear fuel cycle such as fuel reprocessing facilities and waste treatment facilities are requested. In these facilities, there is the environment which is exposed to very high level radiation, and in this case, the cables withstanding 10 MGy radiation dose are required. As the cables meeting such requirement, the new cables having excellent flexibility and radiation resistance were developed. In this paper, the points of material development and the characteristics of cables are reported. Considering the radiation resistance and others, ethylene propylene rubber was selected as the base polymer of the insulator, and polyethylene chlorosulfonate was selected as the sheath material. In order to give excellent radiation resistance, as the anti-rad, energy transfer type aromatic oil that absorbs and dissipates radiation energy and radical trap type anti-oxidant of amine group that catches and stabilizes the radicals generated in the polymer were added. The bromine group burning retarding agent having excellent radiation resistance was applied. In this way, the cables withstanding high radiation dose up to 10 MGy were able to be developed. (K.I.)

  2. Recent developments in the target facilities at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Greene, J.P.; Thomas, G.E.

    1988-01-01

    A description is given of recent developments in the target facility at Argonne National Laboratory. Highlights include equipment upgrades which enables us to provide enhanced capabilities for support of the Argonne Heavy-Ion ATLAS Accelerator Project. Also future plans and additional equipment acquisitions will be discussed. 3 refs., 3 tabs

  3. Test Facilities and Experience on Space Nuclear System Developments at the Kurchatov Institute

    International Nuclear Information System (INIS)

    Ponomarev-Stepnoi, Nikolai N.; Garin, Vladimir P.; Glushkov, Evgeny S.; Kompaniets, George V.; Kukharkin, Nikolai E.; Madeev, Vicktor G.; Papin, Vladimir K.; Polyakov, Dmitry N.; Stepennov, Boris S.; Tchuniyaev, Yevgeny I.; Tikhonov, Lev Ya.; Uksusov, Yevgeny I.

    2004-01-01

    The complexity of space fission systems and rigidity of requirement on minimization of weight and dimension characteristics along with the wish to decrease expenditures on their development demand implementation of experimental works which results shall be used in designing, safety substantiation, and licensing procedures. Experimental facilities are intended to solve the following tasks: obtainment of benchmark data for computer code validations, substantiation of design solutions when computational efforts are too expensive, quality control in a production process, and 'iron' substantiation of criticality safety design solutions for licensing and public relations. The NARCISS and ISKRA critical facilities and unique ORM facility on shielding investigations at the operating OR nuclear research reactor were created in the Kurchatov Institute to solve the mentioned tasks. The range of activities performed at these facilities within the implementation of the previous Russian nuclear power system programs is briefly described in the paper. This experience shall be analyzed in terms of methodological approach to development of future space nuclear systems (this analysis is beyond this paper). Because of the availability of these facilities for experiments, the brief description of their critical assemblies and characteristics is given in this paper

  4. Power Systems Development Facility. Quarterly report, July--September 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a fimction of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and hot gas cleanup units: carbonizer/pressurized circulating fluidized bed gas source; hot gas cleanup units to mate to all gas streams; combustion gas turbine; and fuel cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the facility towards completion and integrating the balance-of-plant processes and particulate control devices (PCDS) into the structural and process designs. Substantial progress in construction activities was achieved during the quarter. Delivery and construction of the process structural steel is nearing completion. Nearly all equipment are set in its place and the FW equipment and the PCDs are being set in the structure.

  5. Accelerator development for a radioactive beam facility based on ATLAS

    International Nuclear Information System (INIS)

    Shepard, K. W.

    1998-01-01

    The existing superconducting linac ATLAS is in many respects an ideal secondary beam accelerator for an ISOL (Isotope separator on-line) type radioactive beam facility. Such a facility would require the addition of two major accelerator elements: a low charge state injector for the existing heavy ion linac, and a primary beam accelerator providing 220 MV of acceleration for protons and light ions. Development work for both of these elements, including the option of superconducting cavities for the primary beam accelerator is discussed

  6. Development of safeguards information treatment system at the facility level

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Doo; Song, Dae Yong; So, Dong Sup; Kwack, Eun Ho [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-04-01

    Safeguards Information Treatment System(SITS) at the facility level is required to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this report, the requirements and major functions of SITS were considered, and the error checking methods and the relationships of safeguards information were reviewed. SITS will be developed to cover the different accounting procedures and methods applied at the various facilities under IAEA safeguards. Also, the resolved result of the Y2K problem in the existing nuclear material accounting program was described. 3 tabs. (Author)

  7. Development of Facilities Master Plan and Laboratory Renovation Project

    Energy Technology Data Exchange (ETDEWEB)

    Fox, Andrea D

    2011-10-03

    Funding from this grant has allowed Morehouse School of Medicine to complete its first professionally developed, comprehensive campus master plan that is in alignment with the recently completed strategic plan. In addition to master planning activities, funds were used for programming and designing research renovations, and also to supplement other research facility upgrades by providing lighting and equipment. The activities funded by this grant will provide the catalyst for substantial improvement in the School's overall facilities for biomedical education and research, and will also provide much of the information needed to conduct a successful campaign to raise funds for proposed buildings and renovations.

  8. Accelerator development for a radioactive beam facility based on ATLAS.

    Energy Technology Data Exchange (ETDEWEB)

    Shepard, K. W.

    1998-01-08

    The existing superconducting linac ATLAS is in many respects an ideal secondary beam accelerator for an ISOL (Isotope separator on-line) type radioactive beam facility. Such a facility would require the addition of two major accelerator elements: a low charge state injector for the existing heavy ion linac, and a primary beam accelerator providing 220 MV of acceleration for protons and light ions. Development work for both of these elements, including the option of superconducting cavities for the primary beam accelerator is discussed.

  9. Overview 2004 of NASA Stirling-Convertor CFD-Model Development and Regenerator R&D Efforts

    Science.gov (United States)

    Tew, Roy C.; Dyson, Rodger W.; Wilson, Scott D.; Demko, Rikako

    2005-01-01

    This paper reports on accomplishments in 2004 in development of Stirling-convertor CFD model at NASA GRC and via a NASA grant, a Stirling regenerator-research effort being conducted via a NASA grant (a follow-on effort to an earlier DOE contract), and a regenerator-microfabrication contract for development of a "next-generation Stirling regenerator." Cleveland State University is the lead organization for all three grant/contractual efforts, with the University of Minnesota and Gedeor Associates as subcontractors. Also, the Stirling Technology Co. and Sunpower, Inc. are both involved in all three efforts, either as funded or unfunded participants. International Mezzo Technologies of Baton Rouge, LA is the regenerator fabricator for the regenerator-microfabrication contract. Results of the efforts in these three areas are summarized.

  10. Role of disposal in developing Federal Facility Compliance Act mixed waste treatment plans

    International Nuclear Information System (INIS)

    Case, J.T.; Rhoderick, J.

    1994-01-01

    The Federal Facilities Compliance Act (FFCA) was enacted on October 6, 1992. This act amends the Solid Waste Disposal Act, which was previously amended by the Resource Conservation and Recovery Act (RCRA). The FFCA set in place a process for managing the Department of Energy's (DOE) mixed low-level radioactive wastes (MLLW), wastes that contain both hazardous and low-level radioactive constituents, with full participation of the affected states. The FFCA provides the framework for the development of treatment capacity for DOE's mixed waste. Disposal of the treatment residues is not addressed by the FFCA. DOE has initiated efforts in concert with the states in the development of a disposal strategy for the treated mixed wastes. This paper outlines DOE efforts in development of a mixed waste disposal strategy which is integrated with the FFCA Site Treatment Planning process

  11. Test facility for the development of 150-keV, multi-megawatt neutral beam systems

    International Nuclear Information System (INIS)

    Haughian, W.; Baker, W.R.; Biagi, L.A.; Hopkins, D.B.

    1975-11-01

    The next generation of CTR experiments, such as the Tokamak Fusion Test Reactor (TFTR), will require neutral-beam injection systems that produce multi-megawatt, 120-keV deuterium-beam pulses of 0.5-second duration. Since present injection systems are operating in the 10- to 40-keV range, an intensive development effort is in progress to meet a 150-keV requirement. The vacuum system and power supplies that make up a test facility to be used in the development of these injectors are described

  12. Development of decommissioning, decontamination and reuse technology for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Moon, J. K.; Choi, B. S.

    2012-03-01

    In this project, the foundation of decommissioning technology through the development of core technologies applied to maintenance and decommissioning of nuclear facility was established. First of all, we developed the key technology such as safety assessment technology for decommissioning work needed at the preparatory stage of decommissioning of the highly contaminated facilities and simultaneous measurement technology of the high-level alpha/beta contamination applicable to the operation and decommissioning of the nuclear facilities. Second, we developed a remotely controlled laser ablation decontamination system which is useful for a removal of fixed contaminants and developed a chemical gel decontamination technology for a removal of non-fixed contaminants during the maintenance and decommissioning works of high radiation hot cells which have been used for a recycling or treatment of spent fuels. Third, we developed a volume reduction and self-disposal technology for dismantled concrete wastes. Also, the technology for volume reduction and stabilization of the peculiar wastes(HEPA filter and organic mixed wastes), which have been known to be very difficult to treat and manage, generated from the high radioactive facilities in operation, improvement and repair and under decommissioning was developed. Finally, this research project was developed a system for the reduction of radiotoxicity of several uranium mixtures generated in the front- and back-end nuclear fuel cycles with characteristics of highly enhanced proliferation-resistance and more environmental friendliness, which can make the uranium to be recovered or separated from the mixtures with a high purity level enough for the uranium to be reused and to be classified as C-class level for burial near the surface, and then which result in the much reduction in volume of the uranium mixture wastes

  13. Construction and engineering report for advanced nuclear fuel development facility

    International Nuclear Information System (INIS)

    Cho, S. W.; Park, J. S.; Kwon, S.J.; Lee, K. W.; Kim, I. J.; Yu, C. H.

    2003-09-01

    The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m 2 , basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc

  14. Development Of A Numerical Tow Tank With Wave Generation To Supplement Experimental Efforts

    Science.gov (United States)

    2017-12-01

    meters (24 inches), a maximum thrust of 1779.3 newtons ( 400 pounds), and a maximum linear speed of 0.4064 m/s (16.0 in/s). 17 3.3 Data Collection...has a small tow tank built in the 1970s. This 10.97 meter (36 foot) long facility is short by academic standards and has lacked wave generation...PAGE INTENTIONALLY LEFT BLANK 14 CHAPTER 3: Experimental Setup 3.1 Description of Experimental Facility The experimental tow tank is 10.97 meters (36.0

  15. Parenting and the Development of Effortful Control from Early Childhood to Early Adolescence: A Transactional Developmental Model

    Science.gov (United States)

    Capaldi, Deborah M.; Kerr, David C. R.; Bertrand, Maria; Pears, Katherine C.; Owen, Lee

    2016-01-01

    Poor effortful control is a key temperamental factor underlying behavioral problems. The bidirectional association of child effortful control with both positive parenting and negative discipline was examined from ages approximately 3 to 13–14 years, involving 5 time points, and using data from parents and children in the Oregon Youth Study-Three Generational Study (N = 318 children from 150 families). Based on a dynamic developmental systems approach, it was hypothesized that there would be concurrent associations between parenting and child effortful control and bidirectional effects across time from each aspect of parenting to effortful control and from effortful control to each aspect of parenting. It was also hypothesized that associations would be more robust in early childhood, from ages 3 to 7 years, and would diminish as indicated by significantly weaker effects at the older ages, 11–12 to 13–14 years. Longitudinal feedback or mediated effects were also tested. Findings supported (a) stability in each construct over multiple developmental periods; (b) concurrent associations, which were significantly weaker at the older ages; (c) bidirectional effects, consistent with the interpretation that at younger ages children’s effortful control influenced parenting, whereas at older child ages, parenting influenced effortful control; and (d) a transactional effect, such that maternal parenting in late childhood was a mechanism explaining children’s development of effortful control from midchildhood to early adolescence. PMID:27427809

  16. The Transrapid test facility between system development and system application

    Energy Technology Data Exchange (ETDEWEB)

    Baur, L [MVP GmbH, Muenchen (Germany)

    1996-12-31

    In the development of a new rail technology, such as the magnetic levitation, there is - in contrast to the further development of the railway technology - not the possibility to use existing routes for the technical verification of the system technology until the application. Instead of this there are two possibilities: Cost-effective preliminary development on test beds and small test facilities up to a development stage which justifies the (relatively serious) risk of realising a service route early and to conclude the system trials and verification there; cost-intensive construction of a large-scale test facility which permits an application-related verification of all important system functions and thus creates the technical pre-requisites for a low-risk system application; The presentation deals with the technical requirements of the system at the test facility the challenges and chances linked to its realisation and adjustment to the rapidly progressing state-of-the-art and which this way opens up for a minimisation of the technical application risk. (orig./HW)

  17. Thermal fuel research and development facilities in BNFL

    International Nuclear Information System (INIS)

    Roberts, V.A.; Vickers, J.

    1996-01-01

    BNFL is committed to providing high quality, cost effective nuclear fuel cycle services to customers on a National and International level. BNFL's services, products and expertise span the complete fuel cycle; from fuel manufacture through to fuel reprocessing, transport, waste management and decommissioning and the Company maintains its technical and commercial lead by investment in continued research and development (R and D). This paper discusses BNFL's involvement in R and D and gives an account of the current facilities available together with a description of the advanced R and D facilities constructed or planned at Springfields and Sellafield. It outlines the work being carried out to support the company fuel technology business, to (1) develop more cost effective routes to existing fuel products; (2) maximize the use of recycled uranium, plutonium and tails uranium and (3) support a successful MOX business

  18. Development of BNL Heat Transfer Facility 1: flashing experiments

    International Nuclear Information System (INIS)

    Leonhardt, W.J.; Klein, J.H.; Zimmer, G.A.; Abuaf, N.; Jones, O.C. Jr.

    1979-01-01

    A major area of interest to reactor safety technology is the prediction of actual vapor generation rates under conditions of thermal nonequilibrium as would be encountered during a loss-of-coolant accident (LOCA) in a light water reactor. In support of the development of advanced codes dealing with LOCA induced flashing, analytical models of the nonequilibrium vapor generation processes of interest have been formulated, and an experimental facility has been constructed to provide data to verify these models. This facility is known as BNL Heat Transfer Facility. The experimental facility consists of a flow loop, test section and the data acquisition and analysis system. The main portion of the flow loop is constructed from three inch nominal (7.6 cm) stainless steel pipe. High purity water is circulated through the loop using a centrifugal pump rated 1500 l/min at 600 kPa. Very close and stable control of all loop parameters is required since flashing is sensitive to very small changes in such parameters as flow rate, subcooling, and pressure

  19. Management and Development of the RT Research Facilities and Infrastructures

    International Nuclear Information System (INIS)

    Kim, Won Ho; Nho, Young Chang; Kim, Jae Sung

    2009-01-01

    The purpose of this project are to operate the core facilities of the research for the Radiation Technology in stable and to assist the research activities efficiently in the industry, academic, and research laboratory. By developing the infrastructure of the national radio technology industry, we can activate the researching area of the RT and the related industry, and obtain the primary and original technology. The key point in the study of the RT and the assistance of the industry, academic, and research laboratory for the RT area smoothly, is managing the various of unique radiation facilities in our country. The gamma Phytotron and Gene Bank are essential in the agribiology because these facilities are used to preserve and utilize the genes and to provide an experimental field for the environment and biotechnology. The Radiation Fusion Technology research supporting facilities are the core support facilities, and are used to develop the high-tech fusion areas. In addition, the most advanced analytical instruments, whose costs are very high, should be managed in stable and be utilized in supporting works, and the experimental animal supporting laboratory and Gamma Cell have to be maintained in high level and managed in stable also. The ARTI have been developed the 30MeV cyclotron during 2005∼2006, aimed to produce radioisotopes and to research the beam applications as a result of the project, 'Establishment of the Infrastructure for the Atomic Energy Research Expansion', collaborated with the Korea Institute of Radiological and Medical Sciences. In addition, the ARTI is in the progress of establishing cyclotron integrated complex as a core research facility, using a proton beam to produce radioisotopes and to support a various research areas. The measurement and evaluation of the irradiation dose, and irradiation supporting technology of the Good Irradiation Practice(GIP) are essential in various researching areas. One thing to remember is that the publicity

  20. Development of a water detritiation facility for JET

    International Nuclear Information System (INIS)

    Perevezentsev, A.N.; Bell, A.C.; Brennan, P.D.; Hemmerich, J.L.

    2002-01-01

    A water detritiation facility, based on a world-wide adopted combined electrolysis catalytic exchange (CECE) process, for the JET active gas handling plant is described. A research and development programme is presented. The programme includes the testing of structured inert packing with an incorporated hydrophobic catalyst for increased throughput of a liquid phase catalytic exchange (LPCE) column, a vapour phase catalytic exchange (VPCE) process for reduction of tritium inventory in the alkali electrolyser and a column of high effectiveness for alkali retention

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

    International Nuclear Information System (INIS)

    Mennicken, K.; Lohmann, P.

    2015-01-01

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

  2. [The challenges of sustainable development in healthcare facilities].

    Science.gov (United States)

    Mourgues, François; Muret, Jane; Pauchard, Jean-Claude

    2018-03-01

    Healthcare and medical-social facilities have a major responsibility within society, that of the quality of care, but also that of developing a system of sustainable and socially-responsible health. This system must meet the three pillars which constitute such an approach: economic, social and environmental sustainability. Innovation remains central to the sustainable evolution of practices and the first results are now visible. Copyright © 2018 Elsevier Masson SAS. All rights reserved.

  3. Currently developing opportunities in food irradiation and modern irradiation facilities

    International Nuclear Information System (INIS)

    Wanke, R.

    1997-01-01

    I. Factor currently influencing advancing opportunities for food irradiation include: heightened incidence and awareness of food borne illnesses and causes. Concerns about ensuring food safety in international as well as domestic trade. Regulatory actions regarding commonly used fumigants/pesticides e.g. Me Br. II. Modern irradiator design: the SteriGenics M ini Cell . A new design for new opportunities. Faster installation of facility. Operationally and space efficient. Provides local o nsite control . Red meat: a currently developing opportunity. (Author)

  4. Development of the pulsed muon facility at ISIS

    International Nuclear Information System (INIS)

    Eaton, G.H.; Scott, C.A.; Williams, W.G.

    1994-01-01

    The ISIS pulsed surface muon facility at RAL is presently undergoing a major expansion to provide three experimental ports with simultaneous single muon pulses at 50 Hz. This upgrade, funded by the European Community (EC), is described together with recent development results which are relevant to its future scientific programme. These new beam lines are expected to be available for experiments in June 1993. (orig.)

  5. Common Data Acquisition Systems (DAS) Software Development for Rocket Propulsion Test (RPT) Test Facilities

    Science.gov (United States)

    Hebert, Phillip W., Sr.; Davis, Dawn M.; Turowski, Mark P.; Holladay, Wendy T.; Hughes, Mark S.

    2012-01-01

    The advent of the commercial space launch industry and NASA's more recent resumption of operation of Stennis Space Center's large test facilities after thirty years of contractor control resulted in a need for a non-proprietary data acquisition systems (DAS) software to support government and commercial testing. The software is designed for modularity and adaptability to minimize the software development effort for current and future data systems. An additional benefit of the software's architecture is its ability to easily migrate to other testing facilities thus providing future commonality across Stennis. Adapting the software to other Rocket Propulsion Test (RPT) Centers such as MSFC, White Sands, and Plumbrook Station would provide additional commonality and help reduce testing costs for NASA. Ultimately, the software provides the government with unlimited rights and guarantees privacy of data to commercial entities. The project engaged all RPT Centers and NASA's Independent Verification & Validation facility to enhance product quality. The design consists of a translation layer which provides the transparency of the software application layers to underlying hardware regardless of test facility location and a flexible and easily accessible database. This presentation addresses system technical design, issues encountered, and the status of Stennis development and deployment.

  6. Neutron research and facility development at the Oak Ridge Electron Linear Accelerator 1970 to 1995

    International Nuclear Information System (INIS)

    Peelle, R.W.; Harvey, J.A.; Maienschein, F.C.; Weston, L.W.; Olsen, D.K.; Larson, D.C.; Macklin, R.L.

    1982-07-01

    This report reviews the accomplishments of the first decade of operation of the Oak Ridge Electron Linear Accelerator (ORELA) and discusses the plans for the facility in the coming decade. Motivations for scientific and applied research during the next decade are included. In addition, ORELA is compared with competing facilities, and prospects for ORELA's improvement and even replacement are reported. Development efforts for the next few years are outlined that are consistent with the anticipated research goals. Recommendations for hardware development include improving the electron injection system to give much larger short-pulse currents on a reliable basis, constructing an Electron Beam Injector Laboratory to help make this improvement possible, continuing a study of possibly replacing the electron accelerator with a proton machine, and replacing or upgrading the facility's data-acquistion and immediate-analysis computer systems. Increased operating time and more involvement of nuclear theorists are recommended, and an effective staff size for optimum use of this unique facility is discussed. A bibliography of all ORELA-related publications is included

  7. Development of an Extreme Environment Materials Research Facility at Princeton

    International Nuclear Information System (INIS)

    Cohen, A.B.; Gentile, C.A.; Tully, C.G.; Austin, R.; Calaprice, F.; McDonald, K.; Ascione, G.; Baker, G.; Davidson, R.; Dudek, L.; Grisham, L.; Kugel, H.; Pagdon, K.; Stevenson, T.; Woolley, R.; Zwicker, A.

    2010-01-01

    The need for a fundamental understanding of material response to a neutron and/or high heat flux environment can yield development of improved materials and operations with existing materials. Such understanding has numerous applications in fields such as nuclear power (for the current fleet and future fission and fusion reactors), aerospace, and other research fields (e.g., high-intensity proton accelerator facilities for high energy physics research). A proposal has been advanced to develop a facility for testing various materials under extreme heat and neutron exposure conditions at Princeton. The Extreme Environment Materials Research Facility comprises an environmentally controlled chamber (48 m 3 ) capable of high vacuum conditions, with extreme flux beams and probe beams accessing a central, large volume target. The facility will have the capability to expose large surface areas (1 m 2 ) to 14 MeV neutrons at a fluence in excess of 10 13 n/s. Depending on the operating mode. Additionally beam line power on the order of 15-75 MW/m 2 for durations of 1-15 seconds are planned. The multi-second duration of exposure can be repeated every 2-10 minutes for periods of 10-12 hours. The facility will be housed in the test cell that held the Tokamak Fusion Test Reactor (TFTR), which has the desired radiation and safety controls as well as the necessary loading and assembly infrastructure. The facility will allow testing of various materials to their physical limit of thermal endurance and allow for exploring the interplay between radiation-induced embrittlement, swelling and deformation of materials, and the fatigue and fracturing that occur in response to thermal shocks. The combination of high neutron energies and intense fluences will enable accelerated time scale studies. The results will make contributions for refining predictive failure modes (modeling) in extreme environments, as well as providing a technical platform for the development of new alloys, new

  8. Development of a 20 MeV Dielectric-Loaded Accelerator Test Facility

    International Nuclear Information System (INIS)

    Gold, Steven H.; Fliflet, Arne W.; Kinkead, Allen K.; Gai Wei; Power, John G.; Konecny, Richard; Jing Chunguang; Tantawi, Sami G.; Nantista, Christopher D.; Hu, Y.; Chen, H.; Tang, C.; Lin, Y.; Bruce, Ralph W.; Bruce, Robert L.; Lewis, David III

    2004-01-01

    This paper describes a joint project by the Naval Research Laboratory (NRL) and Argonne National Laboratory (ANL), in collaboration with the StanFord Linear Accelerator Center (SLAC), to develop a dielectric-loaded accelerator (DLA) test facility powered by a high-power 11.424-GHz magnicon amplifier. The magnicon can presently produce 25 MW of output power in a 250-ns pulse at 10 Hz, and efforts are in progress to increase this to 50 MW. The facility will include a 5 MeV electron injector being developed by the Accelerator Laboratory of Tsinghua University in Beijing, China. The DLA test structures are being developed by ANL, and some have undergone testing at NRL at gradients up to ∼8 MV/m. SLAC is developing a means to combine the two magnicon output arms, and to drive an injector and accelerator with separate control of the power ratio and relative phase. RWBruce Associates, Inc., working with NRL, is developing a means to join short ceramic sections into a continuous accelerator tube by ceramic brazing using an intense millimeter-wave beam. The installation and testing of the first dielectric-loaded test accelerator, including injector, DLA structure, and spectrometer, should take place within the next year. The facility will be used for testing DLA structures using a variety of materials and configurations, and also for testing other X-band accelerator concepts. The initial goal is to produce a compact 20 MeV dielectric-loaded test accelerator

  9. Learner Characteristic Based Learning Effort Curve Mode: The Core Mechanism on Developing Personalized Adaptive E-Learning Platform

    Science.gov (United States)

    Hsu, Pi-Shan

    2012-01-01

    This study aims to develop the core mechanism for realizing the development of personalized adaptive e-learning platform, which is based on the previous learning effort curve research and takes into account the learner characteristics of learning style and self-efficacy. 125 university students from Taiwan are classified into 16 groups according…

  10. Development of the power ramping facility at JMTR

    International Nuclear Information System (INIS)

    Nakata, Hirokatsu; Sezaki, Katsuji; Nakazaki, Chosaburo; Ishii, Tadahiko; Ito, Haruhiko; Abe, Hiroshi

    1985-03-01

    The LWR fuel power ramping facility have been being developed at JMTR since 1978. This report, following previous reports, JAERI-M 8533 and 9343, summarizes the results of performance test performed in 1981 on the 3 He power controlled boiling water capsule, which is a basic part of the facility. Various measurements were carried out during reactor operation on each part of the capsule, i.e. capsule itself, capsule control unit and 3 He power control unit, after a long-time cold run test of the units. Through the test, it was confirmed that the capsule satisfies the specifications which stated that LWR fuel pin should be power-ramped under BWR conditions up to 50 kW/m with a change factor of more than 2, and that the control units operate in a good condition. (author)

  11. Technical viability and development needs for waste forms and facilities

    Energy Technology Data Exchange (ETDEWEB)

    Pegg, I.; Gould, T.

    1996-05-01

    The objective of this breakout session was to provide a forum to discuss technical issues relating to plutonium-bearing waste forms and their disposal facilities. Specific topics for discussion included the technical viability and development needs associated with the waste forms and/or disposal facilities. The expected end result of the session was an in-depth (so far as the limited time would allow) discussion of key issues by the session participants. The session chairs expressed allowance for, and encouragement of, alternative points of view, as well as encouragement for discussion of any relevant topics not addressed in the paper presentations. It was not the intent of this session to recommend or advocate any one technology over another.

  12. Development of decommissioning technology for nuclear fuel facility

    International Nuclear Information System (INIS)

    Tanimoto, Ken-ichi

    1998-01-01

    There are many kinds of objects for decommissioning and their properties are greatly different in respects of morphology, constituent materials, contamination history, etc. Therefore, the techniques for decontamination and dismantlement are required to have a great applicability. In addition, most of contamination nuclides have long half-life and so, it is desirable to rapidly take measures to stop or close a contaminated facility. In consideration of these characteristics developments of elementary techniques for decontamination have been attempted. This report summarized the present states of decommissioning technology for nuclear fuel facility. The function and performance of each elementary technique were examined through test operation and simulation was made for the important techniques of them aiming at generalization and optimization. For remote handling technology, two operation tools; 'metal splitting saw cutting tool' and 'plasma cutting tool' were produced and utilizations of these tools in combination with a robot for conveyance are under investigation now. (M.N.)

  13. Progress in developing the concept for the irradiation research facility

    International Nuclear Information System (INIS)

    Lee, A.G.; Bishop, W.E.; Gillespie, G.E.; Zeng, Y.

    1996-04-01

    At the 16th annual Canadian Nuclear Society conference, AECL presented the case for replacing the NRU reactor with an Irradiation Research Facility (IRF) to test CANDU fuels and materials and to perform advanced materials research using neutrons. AECL developed a cost estimate of $500 million for the reference IRF concept, and estimated that it would require 87 months to complete. AECL has initiated a pre-project program to develop the IRF concept and to minimize uncertainties related to feasibility and licensability, and to examine options for reducing the overall project cost before project implementation begins. (author) 10 refs., 2 figs

  14. Conceptual design of a technology development facility (TDF)

    International Nuclear Information System (INIS)

    Doggett, J.N.; Damm, C.C.

    1981-01-01

    We have developed a concept for employing a single-cell mirror machine in a facility for testing and developing fusion reactor materials, components, and subsystems in a fusion reactor environment. Our approach is similar to that of the 1974 FERF study, except that we have added an auxiliary thermal-barrier cell at each end of the yin-yang magnet. In this way, we provide for plasma microstability by confining a warm plasma component between potential peaks at each end of the device (just as in the tandem mirror with auxiliary barrier cells) while we further improve confinement by the inherent reduction in ambipolar potential drop in the central cell

  15. Developing a framework for assessing muscle effort and postures during computer work in the field: The effect of computer activities on neck/shoulder muscle effort and postures

    NARCIS (Netherlands)

    Garza, J.L.B.; Eijckelhof, B.H.W.; Johnson, P.W.; Raina, S.M.; Rynell, P.; Huysmans, M.A.; Dieën, J.H. van; Beek, A.J. van der; Blatter, B.M.; Dennerlein, J.T.

    2012-01-01

    The present study, a part of the PROOF (PRedicting Occupational biomechanics in OFfice workers) study, aimed to determine whether trapezius muscle effort was different across computer activities in a field study of computer workers, and also investigated whether head and shoulder postures were

  16. Developing a framework for assessing muscle effort and postures during computer work in the field: the effect of computer activities on neck/shoulder muscle effort and postures

    NARCIS (Netherlands)

    Bruno-Garza, J.L.; Eijckelhof, B.H.W.; Johnson, P.W.; Raina, S.M.; Rynell, P.; Huijsmans, M.A.; van Dieen, J.H.; van der Beek, A.J.; Blatter, B.M.; Dennerlein, J.T.

    2012-01-01

    The present study, a part of the PROOF (PRedicting Occupational biomechanics in OFfice workers) study, aimed to determine whether trapezius muscle effort was different across computer activities in a field study of computer workers, and also investigated whether head and shoulder postures were

  17. Development of thermo-plastic heating and compaction facility

    International Nuclear Information System (INIS)

    Ko, Dae Hak; Lim, Suk Nam

    1998-01-01

    Low- and intermediate-level radioactive wastes consist of spent resin, spent filter, concentrated waste and dry active waste(DAW) and they are solidified or packaged into drums or high integrated containers(HICs). DAWs occupy 50 percent of all low- and intermediate-level radioactive wastes generated from nuclear power plants in Korea. Incinerable wastes in the DAWs are about 60 percent. Therefore, it is very important for us to reduce the volume of incinerable wastes in DAWs. Experience of supercompaction turned out that thermo-plastic wastes have a swelling effect after supercompaction process due to their repulsive power. And the thermo-plastic heating and compaction facility has been developed by KEPCO. In conclusion, heating and compaction facility can reduce the volume of DAWs as well as upgrade the quality of treated wastes, because the swelling effect by repulsive power after compaction is removed, final wastes form the shape of block and they have no free-standing water in the wastes. Plan for practical use is that this facility will be installed in other nuclear power plants in Korea in 1999. (Cho, G. S.). 1 tab., 2 figs

  18. Development and use of consolidated criteria for evaluation of emergency preparedness plans for DOE facilities

    International Nuclear Information System (INIS)

    Lerner, K.; Kier, P.H.; Baldwin, T.E.

    1995-01-01

    Emergency preparedness at US Department of Energy (DOE) facilities is promoted by development and quality control of response plans. To promote quality control efforts, DOE has developed a review document that consolidates requirements and guidance pertaining to emergency response planning from various DOE and regulatory sources. The Criteria for Evaluation of Operational Emergency Plans (herein referred to as the Criteria document) has been constructed and arranged to maximize ease of use in reviewing DOE response plans. Although developed as a review instrument, the document also serves as a de facto guide for plan development, and could potentially be useful outside the scope of its original intended DOE clientele. As regulatory and DOE requirements are revised and added in the future, the document will be updated to stay current

  19. Development of a quality system for a contract irradiation facility

    International Nuclear Information System (INIS)

    Siyakus, G.

    2002-01-01

    The use of Industrial Irradiation Systems, in order to process medical supplies and food commodities, has almost 50 years experiences in the world. The food irradiation process has been approved by more than 40 countries around the world and it has been endorsed or supported by numerous national and international organizations and professional groups. Today, radiation sterilization of medical supplies is the most preferred technology in almost every developed country. Other applications: such as waste and flue gas treatment, polymer processing are also put into practice in wider range than before. Higher capital cost compared to the operation cost, the nature of continuous decay of the radiation sources used to obtain gamma rays, obligate the owners of gamma facilities to operate systems based on the 24 hours a day and 7 days per week. On the other hand, higher throughput capacity and economical brake point for profitability, force irradiation companies to offer service for the varied products of the companies. Industrial irradiation facilities providing services for varied companies by irradiating different kind of commodities so called contract irradiator or multipurpose irradiator and most of the irradiation facilities, particularly gamma irradiators running in different locations of the World, operates as contract irradiators. The radiation facilities are considered as a part of the manufacturing process, and must conform to the pertinent general Code of Good Manufacturing Practice (GMP) which has been declared by the principal producer. Customers of these facilities may have petitions, such as irradiation temperature, dose rate, minimal and maximal doses; storage conditions before and after irradiation. Design parameters related to the dose rate, product size, density and weight, irradiation and storage temperatures are the main limitations. Varied process conditions can be easily applied in the laboratory may set forth difficulties in industrial processes

  20. Currently developing opportunities in food irradiation and modern irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Wanke, R [Director Business Development. SteriGenics International Inc. 17901 East Warren Avenue No. 4, Detroit, Michigan 48224-1333 (United States)

    1998-12-31

    I. Factor currently influencing advancing opportunities for food irradiation include: heightened incidence and awareness of food borne illnesses and causes. Concerns about ensuring food safety in international as well as domestic trade. Regulatory actions regarding commonly used fumigants/pesticides e.g. Me Br. II. Modern irradiator design: the SteriGenics {sup M}ini Cell{sup .} A new design for new opportunities. Faster installation of facility. Operationally and space efficient. Provides local {sup o}nsite control{sup .} Red meat: a currently developing opportunity. (Author)

  1. Currently developing opportunities in food irradiation and modern irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Wanke, R. [Director Business Development. SteriGenics International Inc. 17901 East Warren Avenue No. 4, Detroit, Michigan 48224-1333 (United States)

    1997-12-31

    I. Factor currently influencing advancing opportunities for food irradiation include: heightened incidence and awareness of food borne illnesses and causes. Concerns about ensuring food safety in international as well as domestic trade. Regulatory actions regarding commonly used fumigants/pesticides e.g. Me Br. II. Modern irradiator design: the SteriGenics {sup M}ini Cell{sup .} A new design for new opportunities. Faster installation of facility. Operationally and space efficient. Provides local {sup o}nsite control{sup .} Red meat: a currently developing opportunity. (Author)

  2. Dispersion prognoses and consequences in the environment. A Nordic development and harmonization effort

    International Nuclear Information System (INIS)

    Tveten, U.

    1994-01-01

    The project 'BER-1, Dispersion prognoses and environmental consequences' is described. The report describes the work performed and the results obtained. The bulk of the report is concerned with the first subject area, atmospheric dispersion models. The world-wide status of long-range atmospheric dispersion models at the start of the project period is described, descriptions are given of the models in use at the Nordic meteorological institutes, and validation/verification and intercomparison efforts that have been performed within the project are described. The main results of this work have been published separately. All aspects of environmental impact of releases to the atmosphere have been treated, and the end product of this part of the project is a computerized 'handbook' giving easy access to data on e.g. deposition, shielding, filtering, weathering, radionuclide transfer via all possible exposure pathways. (au)

  3. Development of the Los Alamos National Laboratory Plutonium Facility decontamination room

    International Nuclear Information System (INIS)

    Mosso, J.S.; Smith, F.E.; Owen, M.J.; Treadaway, W.A.

    1987-01-01

    For several years the Health Protection Group attempted to remedy the problem of a facility to adequately handle personnel plutonium contamination incidents. Through the efforts of our Quality Circle a presentation was made to management, which immediately appropriated space and funds for the construction of a complete decontamination facility. 9 refs

  4. Development of a 3D Finite Element code for Forging - An overview of the Brite/Euram project EFFORTS

    DEFF Research Database (Denmark)

    Bay, Niels; Andreasen, Jan Lasson; Olsson, David Dam

    2001-01-01

    The present paper presents an overview of the Brite/EuRam project EFFORTS (Enhanced Framework for FOrging design using Reliable Three-dimensional Simulation). A short description is given of methodologies developed including improvements of the numerical analysis, establishment of new constitutive...

  5. Upgrade of the BATMAN test facility for H- source development

    Science.gov (United States)

    Heinemann, B.; Fröschle, M.; Falter, H.-D.; Fantz, U.; Franzen, P.; Kraus, W.; Nocentini, R.; Riedl, R.; Ruf, B.

    2015-04-01

    The development of a radio frequency (RF) driven source for negative hydrogen ions for the neutral beam heating devices of fusion experiments has been successfully carried out at IPP since 1996 on the test facility BATMAN. The required ITER parameters have been achieved with the prototype source consisting of a cylindrical driver on the back side of a racetrack like expansion chamber. The extraction system, called "Large Area Grid" (LAG) was derived from a positive ion accelerator from ASDEX Upgrade (AUG) using its aperture size (ø 8 mm) and pattern but replacing the first two electrodes and masking down the extraction area to 70 cm2. BATMAN is a well diagnosed and highly flexible test facility which will be kept operational in parallel to the half size ITER source test facility ELISE for further developments to improve the RF efficiency and the beam properties. It is therefore planned to upgrade BATMAN with a new ITER-like grid system (ILG) representing almost one ITER beamlet group, namely 5 × 14 apertures (ø 14 mm). Additionally to the standard three grid extraction system a repeller electrode upstream of the grounded grid can optionally be installed which is positively charged against it by 2 kV. This is designated to affect the onset of the space charge compensation downstream of the grounded grid and to reduce the backstreaming of positive ions from the drift space backwards into the ion source. For magnetic filter field studies a plasma grid current up to 3 kA will be available as well as permanent magnets embedded into a diagnostic flange or in an external magnet frame. Furthermore different source vessels and source configurations are under discussion for BATMAN, e.g. using the AUG type racetrack RF source as driver instead of the circular one or modifying the expansion chamber for a more flexible position of the external magnet frame.

  6. Upgrade of the BATMAN test facility for H− source development

    International Nuclear Information System (INIS)

    Heinemann, B.; Fröschle, M.; Falter, H.-D.; Fantz, U.; Franzen, P.; Kraus, W.; Nocentini, R.; Riedl, R.; Ruf, B.

    2015-01-01

    The development of a radio frequency (RF) driven source for negative hydrogen ions for the neutral beam heating devices of fusion experiments has been successfully carried out at IPP since 1996 on the test facility BATMAN. The required ITER parameters have been achieved with the prototype source consisting of a cylindrical driver on the back side of a racetrack like expansion chamber. The extraction system, called “Large Area Grid” (LAG) was derived from a positive ion accelerator from ASDEX Upgrade (AUG) using its aperture size (ø 8 mm) and pattern but replacing the first two electrodes and masking down the extraction area to 70 cm2. BATMAN is a well diagnosed and highly flexible test facility which will be kept operational in parallel to the half size ITER source test facility ELISE for further developments to improve the RF efficiency and the beam properties. It is therefore planned to upgrade BATMAN with a new ITER-like grid system (ILG) representing almost one ITER beamlet group, namely 5 × 14 apertures (ø 14 mm). Additionally to the standard three grid extraction system a repeller electrode upstream of the grounded grid can optionally be installed which is positively charged against it by 2 kV. This is designated to affect the onset of the space charge compensation downstream of the grounded grid and to reduce the backstreaming of positive ions from the drift space backwards into the ion source. For magnetic filter field studies a plasma grid current up to 3 kA will be available as well as permanent magnets embedded into a diagnostic flange or in an external magnet frame. Furthermore different source vessels and source configurations are under discussion for BATMAN, e.g. using the AUG type racetrack RF source as driver instead of the circular one or modifying the expansion chamber for a more flexible position of the external magnet frame

  7. Power conditioning development for the National Ignition Facility

    International Nuclear Information System (INIS)

    Newton, M.A.; Larson, D.W.; Wilson, J.M.; Harjes, H.C.; Savage, M.E.; Anderson, R.L.

    1996-10-01

    The National Ignition Facility (NIF) is a high energy glass laser system and target chamber that will be used for research in inertial confinement fusion. The 192 beams of the NIF laser system are pumped by over 8600 Xenon flashlamps. The power conditioning system for NIF must deliver nearly 300 MJ of energy to the flashlamps in a cost effective and reliable manner. The present system design has over 200 capacitive energy storage modules that store approximately 1.7 MJ each and deliver that energy through a single switch assembly to 20 parallel sets of two series flashlamps. Although there are many possible system designs, few will meet the aggressive cost goals necessary to make the system affordable. Sandia National Laboratory (SNL) and Lawrence Livermore National Laboratory (LLNL) are developing the system and component technologies that will be required to build the power conditioning system for the National Ignition Facility. This paper will describe the ongoing development activities for the NIF power conditioning system

  8. Development of PSA procedure for a criticality in reprocessing facilities

    International Nuclear Information System (INIS)

    Endo, Shigeki; Takanashi, Mitsuhiro; Ueda, Yoshinori

    2012-08-01

    Utilization of risk information for the nuclear safety regulation is being discussed in Japan. The development of probabilistic safety assessment (PSA) procedure is indispensable for the utilization of risk information. The Japan Nuclear Energy Safety Organization (JNES) has been conducting trial PSA to a model plant for major events, i.e. hydrogen explosion, solution boiling, rapid decomposition of TBP complexes, criticality, solvent fire, leakage of molten glass, leakage of high active concentrated liquid waste, loss of all AC electricity, drop of a fuel assembly, for the purpose of developing the PSA procedure for reprocessing facilities. For criticality events results of trial PSA were summarized as a report in which how to evaluate an amount of radioactive materials released from a facility and a health effect on the public were emphasized. Therefore, for criticality events the results of trial PSA were summarized in this report to emphasize procedures from making event progression scenarios to quantifying event sequences, which were not handled in the previous report, in a style of a document describing PSA procedures. (author)

  9. The Legal Efforts on Marine Culture Development in Pacitan, 1999-2015

    Directory of Open Access Journals (Sweden)

    Heru Arif Pianto

    2017-06-01

    Full Text Available Beach is one of the most famous tourism areas in Pacitan. Beaches in Pacitan have special features compared to other beaches. The beautiful nature is able to attract tourists to come, visit and enjoy it. Therefore, the beaches in Pacitan have a lot of possibilities to be a tourism area of marine culture. This article is a historical research. The method used in this study was a historical research method, consisting of four steps, heuristics, criticism, interpretation and historiography. The results of this study indicate that the beaches in the Pacitan region have special attraction for tourists to visit. Thus, to be a tourism area of marine culture, Pacitan requires a better management. Based on research conducted so far, the beaches in Pacitan have not been managed optimally, due to a lack of facilities, and low human resources as managers. In short, it is the responsibility of communities, private parties and local governments to maximize the quality of management of coastal tourism around Pacitan, and their cooperation is need. Therefore, the beaches can be a tourist area of marine culture that can grow rapidly in Pacitan region.

  10. MYRRHA. An experimental ADS Facility for Research and Development

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    2006-01-01

    Full text of publication follows: Since 1998, SCK-CEN in partnership with IBA s.a. and many European research laboratories, is designing a multipurpose ADS for R and D applications MYRRHA - and is conducting an associated R and D support programme. MYRRHA is an Accelerator Driven System (ADS) under development at Mol in Belgium and aiming to serve as a basis for the European experimental ADS to provide protons and neutrons for various R and D applications. It consists of a proton accelerator delivering a 350 MeV * 5 mA proton beam to a liquid Pb-Bi spallation target that in turn couples to a Pb-Bi cooled, subcritical fast core. In a first stage, the project focuses mainly on demonstration of the ADS concept, safety research on sub-critical systems and nuclear waste transmutation studies. In a later stage, the device will also be dedicated to research on structural materials, nuclear fuel, liquid metal technology and associated aspects and on sub-critical reactor physics. Subsequently, it will be used as fast spectrum irradiation facility and as radioisotope production facility. Along the above design features, the MYRRHA project team is developing the MYRRHA project as a multipurpose irradiation facility for R and D applications on the basis of an Accelerator Driven System (ADS). The project is intended to fit into the European strategy towards an ADS Demo facility for nuclear waste transmutation as described in the PDS-XADS FP5 Project. As such it should serve the following task catalogue: ADS concept demonstration, Safety studies for ADS, MA transmutation studies, LLFP transmutation studies, Medical radioisotopes, Material research, Fuel research. A first preliminary conceptual design file of MYRRHA was completed by the end of 2001 and has been reviewed by an International Technical Guidance Committee that concluded that there are no show stoppers in the project even thought some topics such as the safety studies and the fuel qualification need to be addressed

  11. Intergenerational Efforts to Develop a Healthy Environment for Everyone: Sustainability as a Human Rights Issue.

    Science.gov (United States)

    Kruger, Tina M; Savage, Caroline E; Newsham, Patrick

    2014-12-01

    As climate change proceeds at an unprecedented rate, concern for the natural environment has increased. The world's population aging also continues to rise at an unprecedented rate, giving greater attention to the implications of an older population. The two trends are linked through the fact that changes to the environment affect older adults, and older adults affect the environment. Sustainability is, therefore, an intergenerational phenomenon, and protecting resources today leaves a positive legacy and enhances quality of life for future generations. Older adults have much to share with younger generations about behaviors that promote sustainable living, yet few sustainability efforts are intergenerational in nature. As large numbers of people currently subsist without secure access to basic needs, ensuring equitable resource consumption for all generations is urgent and aligns with the Universal Declaration of Human Rights. Through exploring linkages between aging and sustainability, we identify intergenerational strategies to protect the environment and promote human rights and quality of life for older adults. © The Author(s) 2015.

  12. The development of functional requirement for integrated test facility

    International Nuclear Information System (INIS)

    Sim, B.S.; Oh, I.S.; Cha, K.H.; Lee, H.C.

    1994-01-01

    An Integrated Test Facility (ITF) is a human factors experimental environment comprised of a nuclear power plant function simulator, man-machine interfaces (MMI), human performance recording systems, and signal control and data analysis systems. In this study, we are going to describe how the functional requirements are developed by identification of both the characteristics of generic advanced control rooms and the research topics of world-wide research interest in human factors community. The functional requirements of user interface developed in this paper together with those of the other elements will be used for the design and implementation of the ITF which will serve as the basis for experimental research on a line of human factors topics. (author). 15 refs, 1 fig

  13. Implementation study for the NRC Application and Development Facility

    International Nuclear Information System (INIS)

    Sherwood, R.J.; Ross, D.J.; Sasser, D.W.

    1979-01-01

    The Nuclear Regulatory Commission (NRC) has expressed the desire to establish an Application and Development Facility (ADF) for NRC Headquarters. The ADF is a computer system which will provide safeguards analysts access to safeguards analysis computer software. This report analyzes the issues, requirements and options available in the establishment of an ADF. The purpose and goals of the ADF are presented, along with some general issues to be considered in the implementation of such a system. A phased approach for ADF implementation, which will allow for the earliest possible access to existing codes and also allow for future expansion, is outlined. Several options for central computers are discussed, along with the characteristics and approximate costs for each. The report concludes with recommended actions proposed to start the development of the ADF

  14. The technical development on recycled aggregate concrete for nuclear facility

    International Nuclear Information System (INIS)

    Sukekiyo, M.; Saishu, S.; Ishikura, T.; Ishigure, K.

    2000-01-01

    The large amount of non-radioactive concrete waste generated by decommissioning has a very big impact on the final disposal site. Therefore, NUPEC has been developing technology which recovers at a high ratio the aggregate from the dismantling concrete with a quality which can be used to construct a new nuclear power plant. The developed high-quality recycled aggregate meets the quality standards of the natural aggregate stipulated by the Japanese architectural standard specifications for nuclear power plant facilities. As a result of these experiments, it was confirmed that the recycled concrete which used this high-quality recycled aggregate had a performance equal or better than ordinary concrete which used natural aggregate. (authors)

  15. A review of the Los Alamos effort in the development of nuclear rocket propulsion

    International Nuclear Information System (INIS)

    Durham, F.P.; Kirk, W.L.; Bohl, R.J.

    1991-01-01

    This paper reviews the achievements of the Los Alamos nuclear rocket propulsion program and describes some specific reactor design and testing problems encountered during the development program along with the progress made in solving these problems. The relevance of these problems to a renewed nuclear thermal rocket development program for the Space Exploration Initiative (SEI) is discussed. 11 figs

  16. Leadership and Leader Developmental Self-Efficacy: Their Role in Enhancing Leader Development Efforts.

    Science.gov (United States)

    Murphy, Susan Elaine; Johnson, Stefanie K

    2016-01-01

    This chapter describes the role of two types of self-efficacy-leader self-efficacy and leader developmental efficacy-for enhancing leadership development. Practical implications for designing and developing leadership programs that take into account these two types of self-efficacy are discussed. © 2016 Wiley Periodicals, Inc., A Wiley Company.

  17. The National Carbon Capture Center at the Power Systems Development Facility: Topical Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2011-03-01

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy and dedicated to the advancement of clean coal technology. In addition to the development of advanced coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to study CO2 capture from coal-derived syngas and flue gas. The newly established NCCC will include multiple, adaptable test skids that will allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity. During the Budget Period One reporting period, efforts at the PSDF/NCCC focused on developing a screening process for testing consideration of new technologies; designing and constructing pre- and post-combustion CO2 capture facilities; developing sampling and analytical methods; expanding fuel flexibility of the Transport Gasification process; and operating the gasification process for technology research and for syngas generation to test syngas conditioning technologies.

  18. Development of Prescription Drug Information Leaflets: Impact of Cognitive Effort and Patient Involvement on Prescription Medication Information Processing.

    Science.gov (United States)

    Patel, Harshali K; Bapat, Shweta S; Bhansali, Archita H; Sansgiry, Sujit S

    2018-01-01

    The objective of this study was to develop a one-page (1-page) prescription drug information leaflet (PILs) and assess their impact on the information processing variables, across 2 levels of patient involvement. One-page PILs were developed using cognitive principles to lower mental effort and improve comprehension. An experimental, 3 × 2 repeated measures study was conducted to determine the impact of cognitive effort, manipulated using leaflet type on comprehension across 2 levels (high/low) of patient involvement. Adults (≥18 years) in a university setting in Houston were recruited for the study. Each participant was exposed to 3 different types of prescription drug information leaflet (the current practice, preexisting 1-page text-only, and 1-page PILs) for the 3 drugs (Celebrex, Ventolin HFA, Prezista) for a given involvement scenario. A prevalidated survey instrument was used to measure product knowledge, attitude toward leaflet, and intention to read. Multivariate analysis of variance indicated significant positive effect of cognitive effort, involvement, and their interaction effect across all measured variables. Mean scores for product knowledge, attitude toward leaflet, and intention to read were highest for PILs ( P information processing for consumers by reducing their cognitive effort.

  19. Development of hull compaction system for nuclear recycle facility

    International Nuclear Information System (INIS)

    Manole, A.A.; Karkhanis, P.P.; Agarwal, Kailash; Basu, Sekhar

    2013-01-01

    India has adopted closed fuel cycle strategy for efficient management of available resources to meet long term energy requirements. Nuclear Recycle Facility (NRF) provides a vital link in three-stage Indian nuclear power programme. In a NRF for PHWR fuel cycle, reprocessing of spent fuel bundles from PHWRs is carried out using a chop-leach process where the spent fuel bundles are chopped into small pieces using a spent fuel chopper and the contents inside the zircaloy clad are dissolved using concentric nitric acid. This process generates empty zircaloy shells called 'hulls'. The present practice followed for management of hulls is to transfer them into SS drums and store these drums in underground RCC tile holes at a Waste Management Facility (WMF). This waste needs to be stored in an engineered WMF for at least 30-60 years before transferred to a final repository. The storage volumes required for this hull waste will keep increasing as the reprocessing capacity is being enhanced multi-folds. Compaction of hull waste has been employed internationally to reduce the volume required for storage. Hence indigenous development of hull compaction system was initiated by NRB to meet the future requirements. This is being achieved through a set of experiments and analysis with the available resources within the country. This paper describes the process of compaction, conceptualization of the system and benefits accrued from it. (author)

  20. The development of nuclear power and the research effort in the Community

    International Nuclear Information System (INIS)

    Davies, D.H.

    1985-01-01

    The development of nuclear power in the Community is analysed at the light of the oil crisis which hit the world in 1973. Before 1973, nuclear energy was rapidly penetrating the market all over the world: nuclear power plants were being ordered in large numbers and the development of advanced nuclear reactors and of their fuel cycle was vigorously pursued in almost all industrialized countries. In all logic the 1973 oil crisis should have quickened the pace of nuclear energy development; in reality the expected rapid expansion of nuclear energy in the most industrialized countries did not materialize. Despite the setbacks to the global pace of nuclear development, the nuclear energy's share of electricity production in the Community increased from 5.4% in 1973 to 22.4% in 1983. Today the installed nuclear electricity generating capacity is about 55 GWe and the nuclear energy's share exceeds 25%. In 1990 these figures should be about 100 GWe and 35% respectively

  1. Assessment of U.S. and Coalition Efforts to Develop Leaders in the Afghan National Army

    Science.gov (United States)

    2013-06-24

    Literacy remains an enabler for soldier and NCO development, and creates a more discerning citizen for Afghan society . Despite challenges, the...level and economic capacity of the society as a whole. In terms of its importance to professional development, both ANA and NTM-A senior...available in the account, nor if the account is actuarially sound. The NTM-A/CSTC-A lnsp.ector General continues to work with the MoD to resolve a

  2. Development of Decontamination and Decommissioning Technologies for Nuclear Facilities

    International Nuclear Information System (INIS)

    Moon, Jei Kwon; Lee, Kune Woo; Won, Hui Jun

    2010-04-01

    A laser ablation decontamination technology which is reportedly effective for a removal of fixed contaminants has been developed for three years as the first stage of the development. Lab scale experimental equipment was fabricated and the process variables have been assessed for determination of appropriate decontamination conditions at the laser wave lengths of 1,064 nm and 532 nm, respectively. The decontamination tests using radioactive specimens showed that the decontamination efficiency was about 100 which is quite a high value. An electrokinetic-flushing, an agglomeration leaching and a supercritical CO 2 soil decontamination technology were development for a decontamination of radioactive soil wastes from the decommissioned sites of the TRIGA research reactor and the uranium conversion facilities. An electrokinetic-flushing process was found to be effective for soil wastes aged for a long time and an agglomeration leaching process was effective for soil wastes of surface contamination. On the other hand, a supercritical CO 2 soil decontamination technology was found to be applicable for U or TRU bearing soil wastes. The remediation monitoring key technologies such as a representative sample taking and a measurement concept for the vertical distribution of radionuclides were developed for an assessment of the site remediation. Also an One-Dimensional Water Flow and Contaminant Transport in Unsaturated Zone (FTUNS) code was developed to interpretate the radionuclide migration in the unsaturated zone

  3. An effort to develop accessible tourism in Greece and Turkey: the MEDRA project approach

    Directory of Open Access Journals (Sweden)

    Aristotelis Naniopoulos

    2016-03-01

    Full Text Available Purpose – The purpose of this paper is to develop accessible tourism in two areas of Greece and Turkey. The areas of Drama in Greece and Mersin in Turkey have cooperated in the frame of MEDRA project to assess their potential and set up a plan for developing accessible tourism. Design/methodology/approach – The choice of the two areas was not random. Mersin currently enjoys continuous development, as one of Turkey’s biggest ports and a free trade zone. Drama is a developing area in agricultural manufacturing and high-tech sectors with a rich physical environment which aspires to develop a healthy alternative tourism industry. Findings – The findings include, amongst others, the identification of needs of tourists with disabilities, and the relevant historical evolution, legislative framework, international good practices, policy-improvement proposals, accessibility assessment in Mersin and Drama, and suggestions for developing accessible infrastructure together with the training of stakeholders. Practical implications – Greece although made a lot of progress regarding the issues of disability and accessibility still is not on the same level as many European countries, while Turkey has a lot to learn in order to deal with accessibility from a holistic point of view. Social implications – Both countries owe a large percentage of their national income, to the tourist industry and seek ways to gain advantages in this highly competitive sector. Originality/value – The successful implementation of the MEDRA project constitutes an example worthy of a wider application in the development of accessible tourism, not only in the two countries but also to countries with similar characteristics.

  4. The national carbon capture center at the power systems development facility

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2012-09-01

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy and dedicated to the advancement of clean coal technology. In addition to the development of advanced coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to study CO2 capture from coal-derived syngas and flue gas. The NCCC includes multiple, adaptable test skids that allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity. During the Budget Period Three reporting period, efforts at the NCCC/PSDF focused on testing of pre-combustion CO2 capture and related processes; commissioning and initial testing at the post-combustion CO2 capture facilities; and operating the gasification process to develop gasification related technologies and for syngas generation to test syngas conditioning technologies.

  5. THE NATIONAL CARBON CAPTURE CENTER AT THE POWER SYSTEMS DEVELOPMENT FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2011-05-11

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy and dedicated to the advancement of clean coal technology. In addition to the development of advanced coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to study CO2 capture from coal-derived syngas and flue gas. The NCCC includes multiple, adaptable test skids that allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity. During the Budget Period Two reporting period, efforts at the PSDF/NCCC focused on new technology assessment and test planning; designing and constructing post-combustion CO2 capture facilities; testing of pre-combustion CO2 capture and related processes; and operating the gasification process to develop gasification related technologies and for syngas generation to test syngas conditioning technologies.

  6. Investigating factors influencing construction waste management efforts in developing countries: an experience from Thailand.

    Science.gov (United States)

    Manowong, Ektewan

    2012-01-01

    Rapid economic growth and urbanization in developing countries lead to extensive construction activities that generate a large amount of waste. A challenge is how to manage construction waste in the most sustainable way. In the developing world, research on construction waste management is scarce and such academic knowledge needs to be responsive to actual practices in the industry in order to be implemented. As construction projects involve a number of participants and stakeholders, their participation and commitment can have a major influence on the goals of green and sustainable construction for urban development. This study provides a significant step in conducting a very first research of this kind in Thailand by aiming to investigate the level of construction stakeholders' commitment as well as the achievement of construction waste management in order to improve short-term practices and to establish a long-term strategic construction waste management plan. In this study, a structural equation model was employed to investigate the influence of factors that are related to environmental aspects, social aspects, and economic aspect of construction waste management. Concern about health and safety was found to be the most significant and dominant influence on the achievement of sustainable construction waste management. Other factors affecting the successful management of construction waste in Thai construction projects were also identified. It is perceived that this study has potential to contribute useful guidelines for practitioners both in Thailand and other developing countries with similar contexts.

  7. Energy and low carbon development efforts in Ghana: institutional arrangements, initiatives, challenges and the way forward

    DEFF Research Database (Denmark)

    Tutu Benefoh, Daniel; Ackom, Emmanuel

    2016-01-01

    , clearer institutional mandates, continuous improvements in institutional coordination (intra and inter), capacity and skills development, sustained visibility of the essence of energy and LCD at high political levels as well as engagement by civil societies. Equally important are the issues of finance...

  8. 75 FR 65281 - Public Meeting To Discuss NIOSH's Respirator Standards Development Efforts

    Science.gov (United States)

    2010-10-22

    ... Institute for Occupational Safety and Health (NIOSH), Centers for Disease Control and Prevention (CDC... meeting will be open to the public, limited only by the space available. The meeting room accommodates... development of the concepts being considered for performance criteria of various classes of respirators...

  9. Development of the Decommissioning Technology for Nuclear Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kim, G. N.; Kim, S. G.

    2010-04-01

    The evaluation technology of decommissioning process must be developed and will be used for the ALARA planning tool of decommissioning process and demonstrated for tools of decommissioning equipment. Also, this technology can be used for tools workplaces with high work difficulty such as large-scale chemical plant, under water and space. The monitoring system for high alpha radioactive contamination measurement will be use in the high radioactivity decommissioning sites such as hot-cell or glove box. Also, it will be use in the general nuclear facilities as the radiation monitoring unit. The preparation technology of the radiation sensor for high radioactive contamination measurement will be transferred to the company for the industrialization. The remote monitoring system can prevent the workers exposure using the optical fiber to separate the sensor and electronics

  10. Development of the Decontamination and Decommissioning Technology for Nuclear Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Moon, J. K.; Won, C. H.

    2010-04-01

    The research results could be used for a design of a remote ablation decontamination system and ultimately applicable for an decontamination of high radiation facilities such as the DUPIC and PIEF. The evaluation technology of decommissioning process must be developed and will be used for the ALARA planning tool of decommissioning process and demonstrated for tools of decommissioning equipment. Also, this technology can be used for tools workplaces with high work difficulty such as large-scale chemical plant, under water and space. It is expected that the technology for a volume reduction and self-disposal of dismantled concrete wastes can be contributed to the establishment of a management plan for radioactive dismantled concrete wastes through the minimization of final waste volume

  11. The Dortmund low background facility. Current status and recent developments

    Energy Technology Data Exchange (ETDEWEB)

    Goessling, Claus; Kroeninger, Kevin; Nitsch, Christian [Experimentelle Physik IV, TU Dortmund, 44221 Dortmund (Germany)

    2016-07-01

    The Dortmund Low Background Facility (DLB) is a low-background gamma ray spectrometry system with an artificial overburden. The overburden of ten meters of water equivalent, in combination with a multi-layer lead castle and an active muon veto are shielding a high-purity germanium detector of 60 % relative efficiency. The background level is remarkably low compared to a conventional spectrometer system without special shielding and enables sensitivities well below 1 Bq/kg. Thus, material screening measurements as well as environmental monitoring measurements are possible on an easy-accessible location above ground at the campus of the Technische Universitaet Dortmund. The integral background count rate between 40 keV and 2700 keV is 2.528±0.004 counts/kg/min, which is comparable to systems that are situated below ground. In the talk, an overview of the current status of the DLB is given and recent developments are presented.

  12. Sustainable Forest Bioenergy Development Strategies in Indochina: Collaborative Effort to Establish Regional Policies

    Directory of Open Access Journals (Sweden)

    Viktor J. Bruckman

    2018-04-01

    Full Text Available We conducted a feasibility study in Indochina (Cambodia, Laos, Myanmar, Thailand, and Vietnam with the aim of promoting biomass and bioenergy markets, technology transfer, rural development, and income generation. Policy development is guided by the International Union of Forest Research Institutions (IUFRO Task Force “Sustainable Forest Bioenergy Network”. In this paper, we highlight the achievements up to now and present results of a multi-stakeholder questionnaire in combination with a quantitative analysis of the National Bioenergy Development Plans (NBDPs. We found a gap between official documents and working group assessments. NBDPs are focused on the market development, technology transfer, and funding possibilities of a regional bioenergy strategy, while the respondents of a questionnaire (working groups favored more altruistic goals, i.e., sustainable resource management, environmental protection and climate change mitigation, generation of rural income, and community involvement, etc. We therefore suggest the following measures to ensure regulations that support the original aims of the network (climate change mitigation, poverty alleviation, sustainable resource use, and diversification of energy generation: (i Consideration of science-based evidence for drafting bioenergy policies, particularly in the field of biomass production and harvesting; (ii invitation of stakeholders representing rural communities to participate in this process; (iii development of sustainability criteria; (iv feedback cycles ensuring more intensive discussion of policy drafts; (v association of an international board of experts to provide scientifically sound feedback and input; and (vi establishment of a local demonstration region, containing various steps in the biomass/bioenergy supply chain including transboundary collaboration in the ACMECS region.

  13. Scenario Development for Trgovska Gora Shallow Land Facility

    International Nuclear Information System (INIS)

    Skanata, D.; Medakovic, S.; Lokner, V.; Levanat, I.

    2002-01-01

    Safety assessments, either preliminary or final, consist of a qualitative and a quantitative part. The qualitative part of the assessment implies a selection of relevant scenarios to be analyzed, while the quantitative part of the assessment consists of their mathematical modeling. This work is dealing with the qualitative part of safety assessment concerning a specific radioactive waste disposal system, i.e., the shallow land facility situated on the macrolocation Trgovska gora. This article has as its purpose a brief presentation of the ISAM methodology application results (Improvement of Safety Assessment Methodologies for Near Surface Radioactive Waste Facilities;), a methodology developed within the framework of a project of the same name, organized by the IAEA. The above mentioned methodology is based on the development of the so-called FEP list (Features, Events, Process), on selection procedure of the FEP list, specifically regarding particular criteria defined in advance, and on application of systematic methods of selecting relevant scenarios (in this case the matrix of interactions method has been applied). The main aim and purpose of a methodology based on the analysis of FEPs (identification, classification, selection, construction of the matrix of interactions) consists of observing and documenting all the features, events and processes due to be taken into consideration while assessing safety of a particular radioactive waste disposal system. In this connection, by radioactive waste disposal system we mean a system consisting of radioactive waste and engineer features (barriers), geological environment within which the disposal site is located, surface-environment (soil, sediments, vegetation, etc.) and human population near the disposal site. The final step of the application of this methodology consists of generating the scenario using the matrix of interactions. So, for shallow land facility situated on the macrolocation Trgovska gora, applying

  14. Development of holdup monitor system (HMOS) during facility maintenance

    International Nuclear Information System (INIS)

    Nakamura, Hironobu; Hosoma, Takashi; Tanaka, Izumi

    1999-01-01

    Holdup MOnitor System (HMOS) was developed for the purpose of verifying the constant holdup during facility maintenance in Plutonium Conversion Development Facility (PCDF). The glove box assay system (GBAS; big slab) has been used by inspectors, measures the holdup periodically (i.e. IIV) using coincidence counting. The GBAS couldn't be used for inspection during maintenance period. Because many glove boxes (GB) set in process area had been occupied by large vinyl green-houses due to maintenance. We aimed that the holdup except for the maintenance GB should be constant during maintenance period, the HMOSs were set to 3 GBs. The system had been used from June '98 to July '99 for verification. The HMOS detector is located top/bottom of the GB, counts total neutron variation in the GB continuously. Detector efficiencies are 1.2%(top) and 0.12%(bottom), respectively. The measurement variation is observed up to 1.5%(3σ). The HMOS has high sensitivity 8 to 90g Pu (3σ; In case of 1kg Pu holdup, the sensitivity depends on position in the GB). The movement of equipment or nuclear material from/in the GB can be detected effectively. Though the HMOS observes measurement variation related to humidity in the GB, hygroscopic effect of denitration MOX powder, material/equipment movement and mainly 241 Pu nuclear decay, this system can verify that the holdup is constant qualitatively. As a result, in PCDF, safeguard related to the inventory verification during maintenance period (more than 1 year) were successfully performed using holdup monitor system. (author)

  15. The development of robot application technology in nuclear facilities

    International Nuclear Information System (INIS)

    Kim, Seung Ho; Lee, Jong Min; Kim, Chang Hoe; Kim, Byung Soo; Sohn, Surg Won; Hwoang, Suk Yeoung; Lee, Yong Bum; Kim, Woong Ki

    1992-12-01

    The objective of this project is to establish the basic technologies for advanced robotic systems operated in unstructured environment. The developed robotic system, which is remotely controlled, is expected to reduce the radiation dosage for workers who do the maintenance, inspection, and repairing work in nuclear facilities. The two major work scopes of this project in this year are to study the control scheme of advanced robotic system and develop a mobile robot. An inverse kinematic algorithm of 7 degrees of freedom anthropomorphic manipulator is investigated for dexterous control. Extended closed-loop schemes for solving the inverse kinematics of the redundant manipulator have been proposed and decentralized adaptive controller was designed by utilizing a new cartesian space controller. Control architecture of neural network has been developed, which has a strong capability on solving the kinematics of manipulator. The planetary wheel assembly has been implemented in the design to be suitable for plant. The design of manipulator has been implemented to operate with the battery power in the mobile system. This project will continue to be a major technical driver, with nuclear plant maintenance and waste management applications in conjunction with 'Long-term nuclear development program' over the next decade. (Author)

  16. Recent efforts directed to the development of more sustainable asymmetric organocatalysis.

    Science.gov (United States)

    Hernández, José G; Juaristi, Eusebio

    2012-06-04

    In line with the principles of "green" chemistry, organocatalysis seeks to reduce energy consumption and to optimize the use of the available resources, aiming to become a sustainable strategy in chemical transformations. Nevertheless, during the last decade diverse experimental protocols have made organocatalysis an even "greener" alternative by the use of friendlier reaction conditions, or via the application of solvent-free methodologies, or through the design and synthesis of more selective catalysts, or via the development of multicomponent one-pot organocatalytic reactions, or by the recycling and reuse of organocatalysts, or by means of the application of more energy-efficient activation techniques, among other approaches. In this feature article we review some of the remarkable advancements that have made it possible to develop even more sustainable asymmetric organocatalyzed methodologies.

  17. Perspective on present and future alloy development efforts on austenitic stainless steels for fusion application

    International Nuclear Information System (INIS)

    Maziasz, P.J.

    1984-01-01

    The purpose of this paper is to address important questions concerning how to effect further alloy development of austenitic stainless steels for resistance, and to what extent the behavior of other properties under irradiation, such as strength/embrittlement, fatigue/irradiation creep, corrosion (under irradiation), and radiation-induced activation must be influenced. To summarize current understanding, helium has been found to have major effects on swelling and embrittlement, but several metallurgical avenues are available for significant improvement relative to type 316 stainless steel. Studies on fatigue and irradiation creep, particularly including helium effects, are preliminary but have yet to reveal engineering problems requiring additional alloy development remedies. The effects of irradiation on corrosion behavior are unknown, but higher alloy nickel contents make thermal corrosion in lithium worse. 67 refs

  18. An Overview of the Cooperative Effort between the United States Department of Energy and the China Atomic Energy Authority to Enhance MPC and A Inspections for Civil Nuclear Facilities in China

    International Nuclear Information System (INIS)

    Ahern, Keith; Daming, Liu; Hanley, Tim; Livingston, Linwood; McAninch, Connie; McGinnis, Brent R.; Ning, Shen; Qun, Yang; Roback, Jason William; Tuttle, Glenn; Xuemei, Gao; Galer, Regina; Peterson, Nancy; Jia, Jinlie

    2011-01-01

    The United States Department of Energy, National Nuclear Security Administration (DOE/NNSA) and the China Atomic Energy Authority (CAEA) are cooperating to enhance the domestic regulatory inspections capacity for special nuclear material protection, control and accounting (MPC and A) requirements for civil nuclear facilities in China. This cooperation is conducted under the auspices of the Agreement between the Department of Energy of the United States of America and the State Development and Planning Commission of the People s Republic of China on Cooperation Concerning Peaceful Uses of Nuclear Technology. This initial successful effort was conducted in three phases. Phase I focused on introducing CAEA personnel to DOE and U. S. Nuclear Regulatory Commission inspection methods for U. S. facilities. This phase was completed in January 2008 during meetings in Beijing. Phase II focused on developing physical protection and material control and accounting inspection exercises that enforced U. S. inspection methods identified during Phase 1. Hands on inspection activities were conducted in the United States over a two week period in July 2009. Simulated deficiencies were integrated into the inspection exercises. The U. S. and Chinese participants actively identified and discussed deficiencies noted during the two week training course. The material control and accounting inspection exercises were conducted at the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, KY. The physical protection inspection exercises were conducted at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, TN. Phase III leveraged information provided under Phase I and experience gained under Phase II to develop a formal inspection guide that incorporates a systematic approach to training for Chinese MPC and A field inspectors. Additional hands on exercises that are applicable to Chinese regulations were incorporated into the Phase III training material. Phase III was completed in May 2010 at

  19. A Pilot Health Information Technology-Based Effort to Increase the Quality of Transitions From Skilled Nursing Facility to Home: Compelling Evidence of High Rate of Adverse Outcomes.

    Science.gov (United States)

    Donovan, Jennifer L; Kanaan, Abir O; Gurwitz, Jerry H; Tjia, Jennifer; Cutrona, Sarah L; Garber, Lawrence; Preusse, Peggy; Field, Terry S

    2016-04-01

    Older adults are often transferred from hospitals to skilled nursing facilities (SNFs) for post-acute care. Patients may be at risk for adverse outcomes after SNF discharges, but little research has focused on this period. Assessment of the feasibility of a transitional care intervention based on a combination of manual information transmission and health information technology to provide automated alert messages to primary care physicians and staff; pre-post analysis to assess potential impact. A multispecialty group practice. Adults aged 65 and older, discharged from SNFs to home; comparison group drawn from SNF discharges during the previous 1.5 years, matched on facility, patient age, and sex. For the pre-post analysis, we tracked rehospitalization within 30 days after discharge and adverse drug events within 45 days. The intervention was developed and implemented with manual transmission of information between 8 SNFs and the group practice followed by entry into the electronic health record. The process required a 5-day delay during which a large portion of the adverse events occurred. Over a 1-year period, automated alert messages were delivered to physicians and staff for the 313 eligible patients discharged from the 8 SNFs to home. We compared outcomes to those of individually matched discharges from the previous 1.5 years and found similar percentages with 30-day rehospitalizations (31% vs 30%, adjusted HR 1.06, 95% CI 0.80-1.4). Within the adverse drug event (ADE) study, 30% of the discharges during the intervention period and 30% of matched discharges had ADEs within 45 days. Older adults discharged from SNFs are at high risk of adverse outcomes immediately following discharge. Simply providing alerts to outpatient physicians, especially if delivered multiple days after discharge, is unlikely to have any impact on reducing these rates. Copyright © 2016 AMDA – The Society for Post-Acute and Long-Term Care Medicine. Published by Elsevier Inc. All

  20. Efforts of development on the next generation nuclear reactor in the Mitsubishi Heavy Industries, Ltd

    International Nuclear Information System (INIS)

    Mukai, Hiroshi

    2002-01-01

    At present, the Mitsubishi Heavy Industry, Ltd. (MHI) enters to development on APWR+ for a large-scale reactor, AP1000 and pebble bed modular reactor (PBMR) for middle- and small-scale one, and innovative one, under cooperation of power industries, manufacturers and institutes in and out of Japan. On APWR+, MHI occupies the most advanced position of conventional large-scale route, intends to carry out further upgrading of large capacity on a base of already developed 1500 MWe class APWR, and aims at further upgrading of economical efficiency. On the other reactor, as it becomes possible to perform value addition specific to the small-scale reactor with smaller output, it is planned to overcome its scale demerit by introducing more innovative techniques. And, on AP1000, it is intended to remove dynamic safety system by introducing a static one, to upgrade simplification of apparatus and reliability of safety system and to reduce its human factors. In addition, here was described on the next generation nuclear reactors under development. (G.K.)

  1. Geothermal energy development - a boon to Philippine energy self-reliance efforts

    International Nuclear Information System (INIS)

    Alcaraz, A.P.; Ogena, M.S.

    1997-01-01

    The Philippine success story in geothermal energy development is the first of the nation's intensified search for locally available alternative energy sources to oil. Due to its favorable location in the Pacific belt of fire, together with the presence of the right geologic conditions for the formation of geothermal (earth heat) reservoirs, the country has been able to develop commercially six geothermal fields. These are the Makiling-Banahaw area, just south of Manila, Tiwi in Albay, Bacon-Manito in Sorsogon, Tongonan in Leyte, Palinpinon in Southern Negros, and the Mt. Apo region of Mindanao. Together these six geothermal fields have a combined installed generation capacity of 1,448 Mwe, which the Philippines second largest user geothermal energy in the world today. Since 1977 to mid-1997, a total of 88,475 gigawatt-hours have been generated equivalent to 152.54 million barrels of oil. Based on the average yearly price of oil for the period, this translates into a savings of $3,122 billion for the country that otherwise would have gone for oil importations. It is planned that by the year 2000, geothermal shall be accounting for 28.4% of the 42,000 gigawatt-hours of the energy needed for that year, coal-based plants will contribute 24.6% and hydropower 18.6%. This will reduce oil-based contribution to just 28.4%. Geothermal energy as an indigenous energy resource provides the country a sustainable option to other conventional energy sources such as coal, oil and even hydro. Technologies have long been developed to maintain the environmental quality of the geothermal site. It serves to minimize changes in the support systems found on the land, water and air environments. The country has hopped, skipped and jumped towards energy self-reliance anchored on development of its large geothermal resources. And as the Philippines pole-vaults into the 21st century, the nation can look forward to geothermal energy to remain as one of the pillars of its energy self

  2. Metering management at the plutonium research and development facilities

    International Nuclear Information System (INIS)

    Hirata, Masaru; Miyamoto, Fujio; Kurosawa, Makoto; Abe, Jiro; Sakai, Haruyuki; Suzuki, Tsuneo.

    1996-01-01

    Nuclear fuel research laboratory of the Oarai Research Laboratory of the Japan Atomic Energy Research Institute is an R and D facility to treat with plutonium and processes various and versatile type samples in chemical and physical form for use of various experimental researches even though on much small amount. Furthermore, wasted and plutonium samples are often transported to other KMP and MBA such as radioactive waste management facility, nuclear reactor facility and so forth. As this facility is a place to treat plutonium important on the safeguards, it is a facility necessary for detection and allowance actions and for detail managements on the metering management data to report to government and IAEA in each small amount sample and different configuration. In this paper, metering management of internationally regulated matters and metering management system using a work station newly produced in such small scale facility were introduced. (G.K.)

  3. Facilities as teaching tools: A transformative participatory professional development experience

    Science.gov (United States)

    Wilson, Eric A.

    Resource consumption continues to increase as the population grows. In order to secure a sustainable future, society must educate the next generation to become "sustainability natives." Schools play a pivotal role in educating a sustainability-literate society. However, a disconnect exists between the hidden curriculum of the built environment and the enacted curriculum. This study employs a transformative participatory professional development model to instruct teachers on how to use their school grounds as teaching tools for the purpose of helping students make explicit choices in energy consumption, materials use, and sustainable living. Incorporating a phenomenological perspective, this study considers the lived experience of two sustainability coordinators. Grounded theory provides an interpretational context for the participants' interactions with each other and the professional development process. Through a year long professional development experience - commencing with an intense, participatory two-day workshop -the participants discussed challenges they faced with integrating facilities into school curriculum and institutionalizing a culture of sustainability. Two major needs were identified in this study. For successful sustainability initiatives, a hybrid model that melds top-down and bottom-up approaches offers the requisite mix of administrative support, ground level buy-in, and excitement vis-a-vis sustainability. Second, related to this hybrid approach, K-12 sustainability coordinators ideally need administrative capabilities with access to decision making, while remaining connected to students in a meaningful way, either directly in the classroom, as a mentor, or through work with student groups and projects.

  4. Development and operation of a mobile test facility for education

    Science.gov (United States)

    Davis, Christopher T.

    The automotive industry saw a large shift towards vehicle electrification after the turn of the century. It became necessary to ensure that new and existing engineers were qualified to design and calibrate these new systems. To ensure this training, Michigan Tech received a grant to develop a curriculum based around vehicle electrification. As part of this agenda, the Michigan Tech Mobile Laboratory was developed to provide hands-on training for professional engineers and technicians in hybrid electric vehicles and vehicle electrification. The Mobile Lab has since then increased the scope of the delivered curriculum to include other automotive areas and even customizable course content to meet specific needs. This thesis outlines the development of the Mobile Laboratory and its powertrain test facilities. The focus of this thesis is to discuss the different hardware and software systems within the lab and test cells. Detailed instructions on the operation and maintenance of each of the systems are discussed. In addition, this thesis outlines the setup and operation of the necessary equipment for several of the experiments for the on and off campus courses and seminars.

  5. Diagnostic development and support of MHD test facilities: Technical progress report for the period January, February, March 1985

    International Nuclear Information System (INIS)

    Shepard, W.S.; Cook, R.L.

    1985-04-01

    Mississippi State University is developing diagnostic instruments for MHD power train data acquisition and for support of MHD component development test facilities. Microprocessor-controlled optical instruments, initially developed for HRSR support, are being refined, and new systems to measure temperatures and gas-seed-slag stream characteristics are being developed. To further data acquisition and analysis capabilities, the diagnostic systems are being interfaced with MHD Energy Center computers. Additionally, technical support of the diagnostic needs of the national MHD research effort is being provided

  6. Development of a nasogastric tube insertion simulator: a collaborative interdisciplinary effort.

    Science.gov (United States)

    Summer, Lindsay; Gonzalez, Laura; Jimeno, Miguel; Christensen, Ken

    2009-01-01

    The nursing faculty shortage has created the need for more innovative and effective ways to better stimulate nursing students. Simulation technology is one way to increase the effectiveness of teaching faculty. In this article, a collaborative project between the College of Nursing and College of Engineering at the University of South Florida to develop and evaluate a PC-based software simulator based on videogame technologies for nursing skill acquisition is discussed. A software simulator for teaching and assessing mastery of the procedure for nasogastric tube insertion is described. The purpose of the simulator is to complement the standard training of nasogastric tube insertion that uses static mannequins and instruction/assessment by nursing instructors. The simulator was used in a fundamentals of nursing class at the University of South Florida, with 75 students enrolled. Evaluation showed that the simulator significantly increased the confidence of the students in their ability to perform nasogastric tube insertion.

  7. STUDY OF INSTRUCTIONAL MODELS AND SYNTAX AS AN EFFORT FOR DEVELOPING ‘OIDDE’ INSTRUCTIONAL MODEL

    Directory of Open Access Journals (Sweden)

    Atok Miftachul Hudha

    2016-07-01

    Full Text Available The 21st century requires the availability of human resources with seven skills or competence (Maftuh, 2016, namely: 1 critical thinking and problem solving skills, 2 creative and innovative, 3 behave ethically, 4 flexible and quick to adapt, 5 competence in ICT and literacy, 6 interpersonal and collaborative capabilities, 7 social skills and cross-cultural interaction. One of the competence of human resources of the 21st century are behaving ethically should be established and developed through learning that includes the study of ethics because ethical behavior can not be created and owned as it is by human, but must proceed through solving problem, especially ethical dilemma solving on the ethical problems atau problematics of ethics. The fundamental problem, in order to ethical behavior competence can be achieved through learning, is the right model of learning is not found yet by teachers to implement the learning associated with ethical values as expected in character education (Hudha, et al, 2014a, 2014b, 2014c. Therefore, it needs a decent learning model (valid, practical and effective so that ethics learning, to establish a human resources behave ethically, can be met. Thus, it is necessary to study (to analyze and modificate the steps of learning (syntax existing learning model, in order to obtain the results of the development model of learning syntax. One model of learning that is feasible, practical, and effective question is the learning model on the analysis and modification of syntax model of social learning, syntax learning model systems behavior (Joyce and Weil, 1980, Joyce, et al, 2009 as well as syntax learning model Tri Prakoro (Akbar, 2013. The modified syntax generate learning model 'OIDDE' which is an acronym of orientation, identify, discussion, decision, and engage in behavior.

  8. Effortful echolalia.

    Science.gov (United States)

    Hadano, K; Nakamura, H; Hamanaka, T

    1998-02-01

    We report three cases of effortful echolalia in patients with cerebral infarction. The clinical picture of speech disturbance is associated with Type 1 Transcortical Motor Aphasia (TCMA, Goldstein, 1915). The patients always spoke nonfluently with loss of speech initiative, dysarthria, dysprosody, agrammatism, and increased effort and were unable to repeat sentences longer than those containing four or six words. In conversation, they first repeated a few words spoken to them, and then produced self initiated speech. The initial repetition as well as the subsequent self initiated speech, which were realized equally laboriously, can be regarded as mitigated echolalia (Pick, 1924). They were always aware of their own echolalia and tried to control it without effect. These cases demonstrate that neither the ability to repeat nor fluent speech are always necessary for echolalia. The possibility that a lesion in the left medial frontal lobe, including the supplementary motor area, plays an important role in effortful echolalia is discussed.

  9. Developing International Guidelines on Volcanic Hazard Assessments for Nuclear Facilities

    Science.gov (United States)

    Connor, Charles

    2014-05-01

    Worldwide, tremendous progress has been made in recent decades in forecasting volcanic events, such as episodes of volcanic unrest, eruptions, and the potential impacts of eruptions. Generally these forecasts are divided into two categories. Short-term forecasts are prepared in response to unrest at volcanoes, rely on geophysical monitoring and related observations, and have the goal of forecasting events on timescales of hours to weeks to provide time for evacuation of people, shutdown of facilities, and implementation of related safety measures. Long-term forecasts are prepared to better understand the potential impacts of volcanism in the future and to plan for potential volcanic activity. Long-term forecasts are particularly useful to better understand and communicate the potential consequences of volcanic events for populated areas around volcanoes and for siting critical infrastructure, such as nuclear facilities. Recent work by an international team, through the auspices of the International Atomic Energy Agency, has focused on developing guidelines for long-term volcanic hazard assessments. These guidelines have now been implemented for hazard assessment for nuclear facilities in nations including Indonesia, the Philippines, Armenia, Chile, and the United States. One any time scale, all volcanic hazard assessments rely on a geologically reasonable conceptual model of volcanism. Such conceptual models are usually built upon years or decades of geological studies of specific volcanic systems, analogous systems, and development of a process-level understanding of volcanic activity. Conceptual models are used to bound potential rates of volcanic activity, potential magnitudes of eruptions, and to understand temporal and spatial trends in volcanic activity. It is these conceptual models that provide essential justification for assumptions made in statistical model development and the application of numerical models to generate quantitative forecasts. It is a

  10. Developing operating procedures for a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G.

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures

  11. Developing operating procedures for a low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

  12. An Overview of Communications Technology and Development Efforts for 2015 SBIR Phase I

    Science.gov (United States)

    Nguyen, Hung D.; Steele, Gynelle C.

    2017-01-01

    This report highlights innovative SBIR 2015 Phase I projects specifically addressing areas in Communications Technology and Development which is one of six core competencies at NASA Glenn Research Center. There are fifteen technologies featured with emphasis on a wide spectrum of applications such as novel solid state lasers for space-based water vapor dial; wide temperature, high voltage and energy density capacitors for aerospace exploration; instrument for airborne measurement of carbonyl sulfide; high-power tunable seed laser for methane Lidar transmitter; ROC-rib deployable ka-band antenna for nanosatellites; a SIC-based microcontroller for high-temperature in-situ instruments and systems; improved yield, performance and reliability of high-actuator-count deformable mirrors; embedded multifunctional optical sensor system; switching electronics for space-based telescopes with advanced AO systems; integrated miniature DBR laser module for Lidar instruments; and much more. Each article in this booklet describes an innovation, technical objective, and highlights NASA commercial and industrial applications. space-based water vapor dial; wide temperature, high voltage and energy density capacitors foraerospace exploration; instrument for airborne measurement of carbonyl sulfide; high-power tunable seed laser formethane Lidar transmitter; ROC-rib deployable ka-band antenna for nanosatellites.

  13. Research on the Construction Management and Sustainable Development of Large-Scale Scientific Facilities in China

    Science.gov (United States)

    Guiquan, Xi; Lin, Cong; Xuehui, Jin

    2018-05-01

    As an important platform for scientific and technological development, large -scale scientific facilities are the cornerstone of technological innovation and a guarantee for economic and social development. Researching management of large-scale scientific facilities can play a key role in scientific research, sociology and key national strategy. This paper reviews the characteristics of large-scale scientific facilities, and summarizes development status of China's large-scale scientific facilities. At last, the construction, management, operation and evaluation of large-scale scientific facilities is analyzed from the perspective of sustainable development.

  14. Why the developing nations like India need strong capacity building efforts in greenhouse gases mitigation?

    Science.gov (United States)

    Vishal, V.; Sudhakaran, A.; Singh, T. N.

    2014-12-01

    Today, India rubs shoulders with nations like USA and China for being the major shareholders in global greenhouse emissions and has more emissions than Russia! Carbon Capture, Utilization and Storage (CCUS) has been proven as a reliable method to counter global warming and keep the 2ºC per year policy in check and is currently in the pilot stage in many developed nations. The three major requirements for CCUS are: manpower in diverse fields, implementation potential and capital. Keeping other social problems aside, India still has sufficient mankind in all spheres of research ranging from earth science, engineering, basic sciences, economy, policy making, regulation, public outreach etc. to successfully work on such challenges. India has leading academic institutions, research labs and universities in science and engineering. They also have a working power force in aspects like economy, policy making, regulation, public outreach etc. in various management institutes of repute. India, however, lacks in sufficient funding for advanced research and capacity building schemes to support projects of such scale. Deployment of facts and concepts on climate change need an approach of much greater scope than what is anticipated. The above workforces can put forth a clear picture about the various entities surrounding CCUS and provide sensible planning and implementation information through scientific research. CCUS is only possible when the direct anthropogenic emitters like fossil fuel plants modify their features to incorporate the methods associated with it. The rural population has to be educated in context to the safety of the storage sites. Above all, the Indian government must holistically divert funds for such programs and provide economic incentives to the industries for the industries. The bottom line is that India has been working in lots of aspects with not very clear cuts objectives. There are CO2 capture technologies like amine scrubbing and membrane

  15. Power Systems Development Facility Gasification Test Campaing TC18

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2005-08-31

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device (PCD), advanced syngas cleanup systems, and high pressure solids handling systems. This report details Test Campaign TC18 of the PSDF gasification process. Test campaign TC18 began on June 23, 2005, and ended on August 22, 2005, with the gasifier train accumulating 1,342 hours of operation using Powder River Basin (PRB) subbituminous coal. Some of the testing conducted included commissioning of a new recycle syngas compressor for gasifier aeration, evaluation of PCD filter elements and failsafes, testing of gas cleanup technologies, and further evaluation of solids handling equipment. At the conclusion of TC18, the PSDF gasification process had been operated for more than 7,750 hours.

  16. Development of 3He-BOCA power ramping facility, 1

    International Nuclear Information System (INIS)

    Nakata, Hirokatsu; Ishii, Tadahiko; Itoh, Haruhiko; Abe, Hiroshi; Nakazaki, Chozaburo

    1979-11-01

    Development of a He-3 power controlled boiling water capsule, 3 He-BOCS, for LWR fuels power ramping test in JMTR has been carried out since 1978 on a five-year program; in the reactor, irradiation tests of various fuels and structual materials have been made since 1969. Using stagnant-pressurized water as a thermal medium, the capsule provides pressure and temperature conditions similar to those in LWRs. Heat generation of a fuel pin can be controlled by a He-3 gas screen surrounding the capsule. The facility is capable of testing numbers of both fresh and irradiated fuel pins under LWR operating conditions for power ramping and cycling. After explaining the operating priciples of 3 He-BOCA and the development program, the following are described: the results of preliminary out-of-pile test on heat conductive characteristics of the capsule and a conceptual design of the 3 He-BOCA for power ramping of a short fuel pin from 250 W/cm to 500 W/cm under BWR conditions. (author)

  17. Anatomy Education in Namibia: Balancing Facility Design and Curriculum Development

    Science.gov (United States)

    Wessels, Quenton; Vorster, Willie; Jacobson, Christian

    2012-01-01

    The anatomy curriculum at Namibia's first, and currently only, medical school is clinically oriented, outcome-based, and includes all of the components of modern anatomical sciences i.e., histology, embryology, neuroanatomy, gross, and clinical anatomy. The design of the facilities and the equipment incorporated into these facilities were directed…

  18. The National Carbon Capture Center at the Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2014-07-14

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy (DOE) and dedicated to the advancement of clean coal technology. In addition to the development of high efficiency coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to promote new technologies for CO2 capture from coal-derived flue gas and syngas. The NCCC includes multiple, adaptable test skids that allow technology development of CO2 capture concepts using coal-derived flue gas and syngas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity and accelerate their development paths to commercialization. During the calendar year 2013 portion of the Budget Period Four reporting period, efforts at the NCCC focused on post-combustion CO2 capture, gasification, and pre-combustion CO2 capture technology testing. Preparations for future testing were on-going as well, and involved facility upgrades and collaboration with numerous technology developers. In the area of post-combustion, testing was conducted on an enzyme-based technology, advanced solvents from two major developers, and a gas separation membrane. During the year, the gasification process was operated for three test runs, supporting development of water-gas shift and COS hydrolysis catalysts, a mercury sorbent, and several gasification support technologies. Syngas produced during gasification operation was also used for pre-combustion capture technologies, including gas separation membranes from three different technology developers, a CO2 sorbent, and CO2 solvents.

  19. Hardware Development Process for Human Research Facility Applications

    Science.gov (United States)

    Bauer, Liz

    2000-01-01

    The simple goal of the Human Research Facility (HRF) is to conduct human research experiments on the International Space Station (ISS) astronauts during long-duration missions. This is accomplished by providing integration and operation of the necessary hardware and software capabilities. A typical hardware development flow consists of five stages: functional inputs and requirements definition, market research, design life cycle through hardware delivery, crew training, and mission support. The purpose of this presentation is to guide the audience through the early hardware development process: requirement definition through selecting a development path. Specific HRF equipment is used to illustrate the hardware development paths. The source of hardware requirements is the science community and HRF program. The HRF Science Working Group, consisting of SCientists from various medical disciplines, defined a basic set of equipment with functional requirements. This established the performance requirements of the hardware. HRF program requirements focus on making the hardware safe and operational in a space environment. This includes structural, thermal, human factors, and material requirements. Science and HRF program requirements are defined in a hardware requirements document which includes verification methods. Once the hardware is fabricated, requirements are verified by inspection, test, analysis, or demonstration. All data is compiled and reviewed to certify the hardware for flight. Obviously, the basis for all hardware development activities is requirement definition. Full and complete requirement definition is ideal prior to initiating the hardware development. However, this is generally not the case, but the hardware team typically has functional inputs as a guide. The first step is for engineers to conduct market research based on the functional inputs provided by scientists. CommerCially available products are evaluated against the science requirements as

  20. Thermal and flow analysis of the Fluor Daniel, Inc., Nuclear Material Storage Facility renovation design (initial 30% effort of Title 1)

    International Nuclear Information System (INIS)

    Steinke, R.G.; Mueller, C.; Knight, T.D.

    1998-03-01

    The computational fluid dynamics code CFX4.2 was used to evaluate steady-state thermal-hydraulic conditions in the Fluor Daniel, Inc., Nuclear Material Storage Facility renovation design (initial 30% of Title 1). Thirteen facility cases were evaluated with varying temperature dependence, drywell-array heat-source magnitude and distribution, location of the inlet tower, and no-flow curtains in the drywell-array vault. Four cases of a detailed model of the inlet-tower top fixture were evaluated to show the effect of the canopy-cruciform fixture design on the air pressure and flow distributions

  1. Improvement in Product Development: Use of back-end data to support upstream efforts of Robust Design Methodology

    Directory of Open Access Journals (Sweden)

    Vanajah Siva

    2012-12-01

    Full Text Available In the area of Robust Design Methodology (RDM less is done on how to use and work with data from the back-end of the product development process to support upstream improvement. The purpose of this paper is to suggest RDM practices for the use of customer claims data in early design phases as a basis for improvements. The back-end data, when systematically analyzed and fed back into the product development process, aids in closing the product development loop from claims to improvement in the design phase. This is proposed through a flow of claims data analysis tied to an existing tool, namely Failure Mode and Effects Analysis (FMEA. The systematic and integrated analysis of back-end data is suggested as an upstream effort of RDM to increase understanding of noise factors during product usage based on the feedback of claims data to FMEA and to address continuous improvement in product development.

  2. The National Carbon Capture Center at the Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Mosser, Morgan [Southern Company Services, Inc., Wilsonville, AL (United States)

    2012-12-31

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy and dedicated to the advancement of clean coal technology. In addition to the development of high efficiency coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to promote new technologies for CO2 capture from coal-derived syngas and flue gas. The NCCC includes multiple, adaptable test skids that allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity and accelerate their development path to commercialization. During the calendar year 2012 portion of the Budget Period Four reporting period, efforts at the NCCC focused on testing of pre- and post-combustion CO2 capture processes and gasification support technologies. Preparations for future testing were on-going as well, and involved facility upgrades and collaboration with numerous technology developers. In the area of pre-combustion, testing was conducted on a new water-gas shift catalyst, a CO2 solvent, and gas separation membranes from four different technology developers, including two membrane systems incorporating major scale-ups. Post-combustion tests involved advanced solvents from three major developers, a gas separation membrane, and two different enzyme technologies. An advanced sensor for gasification operation was evaluated, operation with biomass co-feeding with coal under oxygen-blown conditions was achieved, and progress continued on refining several gasification support technologies.

  3. Developing of the protocol for electron beam food irradiation facility

    International Nuclear Information System (INIS)

    Petreska, Svetlana

    2012-01-01

    By establishing the needs for institution of new technologies in the process of food processing, in this case a randomized choice of electron beam accelerator facility, arises the need for designing a protocol for safe and secure performance of the facility. The protocol encompasses safety and security measures for protection from ionizing radiation of the individuals who work at the facility, as well as, the population and the environment in the immediate neighborhood of the facility. Thus, the adopted approach is the establishment of appropriate systems responding to the protocol. Dosimetry system, which includes appropriate procedures for accurate measure and recording of the absorbed dose values, according to the provisions for protection from ionizing radiation. Ionizing radiation protection system and providing the safety and security of the facility for food processing by means of ionizing radiation. System for providing quality and safety control of the facility for food processing by means of ionizing radiation. Pursuant to the designed a protocol for safe and secure performance of the facility for electron beam food processing, contributes to protection against ionizing radiation as occupationally exposed persons as well the population. (Author)

  4. Assessing Development Impacts Associated with Low Emission Development Strategies: Lessons Learned from Pilot Efforts in Kenya and Montenegro

    Energy Technology Data Exchange (ETDEWEB)

    Cox, S. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Katz, J. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Wurtenberger, L. [Energy Research Centre of the Netherlands (ECN), Petten (Netherlands)

    2014-01-01

    Low emission development strategies (LEDS) articulate economy-wide policies and implementation plans designed to enable a country to meet its long-term development objectives while reducing greenhouse gas emissions. A development impact assessment tool was developed to inform an analytically robust and transparent prioritization of LEDS actions based on their economic, social, and environmental impacts. The graphical tool helps policymakers communicate the development impacts of LEDS options and identify actions that help meet both emissions reduction and development goals. This paper summarizes the adaptation and piloting of the tool in Kenya and Montenegro. The paper highlights strengths of the tool and discusses key needs for improving it.

  5. Development of the RRR cold neutron beam facility

    International Nuclear Information System (INIS)

    Lovotti, Osvaldo; Masriera, Nestor; Lecot, Carlos; Hergenreder, Daniel

    2002-01-01

    This paper describes some general design issues on the neutron beam facilities (cold neutron source and neutron beam transport system) of the Replacement Research Reactor (RRR) for the Australian Nuclear Science and Technology Organisation (ANSTO). The description covers different aspect of the design: the requirements that lead to an innovative design, the overall design itself, the definition of a technical approach in order to develop the necessary design solutions, and finally the organizational framework by which international expertise from five different institutions is integrated. From the technical viewpoint, the RRR-CNS is a liquid Deuterium (LD2) moderator, sub-cooled to ensure maximum moderation efficiency, flowing within a closed natural circulation thermosyphon loop. The thermosyphon is surrounded by a zirconium alloy CNS vacuum containment that provides thermal insulation and a multiple barriers scheme to prevent Deuterium from mixing with water or air. Consistent with international practice, this vessel is designed to withstand any hypothetical energy reaction should Deuterium and air mix in its interior. The 'cold' neutrons are then taken by the NBTS and transported by the neutron guide system into the reactor beam hall and neutron guide hall, where neutron scattering instruments are located. From the management viewpoint, the adopted distributed scheme is successful to manage the complex interfacing between highly specialized technologies, allowing a smooth integration within the project. (author)

  6. Development of self-running underwater cleaner for nuclear facilities

    International Nuclear Information System (INIS)

    Ito, Haruo; Mizutani, Takeshi; Miki, Masamichi

    1979-01-01

    A self-running underwater cleaner for removing sediment accumulated on the bottoms of water tanks in nuclear power stations by remote operation was developed. This cleaner is used in the state maintaining the shielding effect of water against radiation as water is filled in equipment pits, and by the remote operation using cables, it runs freely in water and sucks bottom sediment. The sediment is transported through a drain hose to a treating facility in a power station, and treated in a lump. The cleaner is composed of the carriage with electric steering wheels and driving wheels and a high head submerged pump. Front and rear suction mouths are provided, and suck sediment with high speed water flow while scraping with rubber boards. The cleaner can be used in the water depth of 7 m, and as the results of practical test, it was confirmed that the decontaminating effect and maneuverability were very good so that the sediment at the corner was scarcely left behind, and the effects of labor saving and the reduction of exposure of employees were large. The fundamental experiments were carried out on the running mechanism, the coefficient of friction in water, and the construction of suction mouth. The trial manufacture of the under water cleaner, the water tank experiment and the test in the Mamaoka No. 1 plant are reported. (Kako, I.)

  7. Development of Spectrophotometric Process Monitors for Aqueous Reprocessing Facilities

    International Nuclear Information System (INIS)

    Smith, N.; Krebs, J.; Hebden, A.

    2015-01-01

    The safeguards envelope of an aqueous reprocessing plant can be extended beyond traditional measures to include surveillance of the process chemistry itself. By observing the concentration of accountable species in solution directly, a measure of real time accountancy can be applied. Of equal importance, select information on the process chemistry can be determined that will allow the operator and inspectors to verify that the process is operating as intended. One of the process monitors that can be incorporated is molecular spectroscopy, such as UV-Visible absorption spectroscopy. Argonne National Laboratory has developed a process monitoring system that can be tailored to meet the specific chemistry requirements of a variety of processes. The Argonne Spectroscopic Process monitoring system (ASP) is composed of commercial-off-the-shelf (COTS) spectroscopic hardware, custom manufactured sample handling components (to meet end user requirements) and the custom Plutonium and Uranium Measurement and Acquisition System (PUMAS) software. Two versions of the system have been deployed at the Savannah River Site's H-Canyon facility, tailored for high and low concentration streams. (author)

  8. Power Systems Development Facility Gasification Test Run TC09

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-09-30

    This report discusses Test Campaign TC09 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode of operation using a particulate control device (PCD). The Transport Gasifier was operated as a pressurized gasifier during TC09 in air- and oxygen-blown modes. Test Run TC09 was started on September 3, 2002, and completed on September 26, 2002. Both gasifier and PCD operations were stable during the test run, with a stable baseline pressure drop. The oxygen feed supply system worked well and the transition from air to oxygen was smooth. The gasifier temperature varied between 1,725 and 1,825 F at pressures from 125 to 270 psig. The gasifier operates at lower pressure during oxygen-blown mode due to the supply pressure of the oxygen system. In TC09, 414 hours of solid circulation and over 300 hours of coal feed were attained with almost 80 hours of pure oxygen feed.

  9. Development of a test facility for analyzing supercritical fluid blowdown

    International Nuclear Information System (INIS)

    Roberto, Thiago D.; Alvim, Antonio C.M.

    2015-01-01

    The generation IV nuclear reactors under development mostly use supercritical fluids as the working fluid because higher temperatures improve the thermal efficiency. Supercritical fluids are used by modern nuclear power plants to achieve thermal efficiencies of around 45%. With water as the supercritical working fluid, these plants operate at a high temperature and pressure. However, experiments on supercritical water are limited by technical and financial difficulties. These difficulties can be overcome by using model fluids, which have more feasible supercritical conditions and exhibit a lower critical pressure and temperature. Experimental research is normally used to determine the conditions under which model fluids represent supercritical fluids under steady-state conditions. A fluid-to-fluid scaling approach has been proposed to determine model fluids that can represent supercritical fluids in a transient state. This paper presents an application of fractional scale analysis to determine the simulation parameters for a depressurization test facility. Carbon dioxide (CO 2 ) and R134a gas were considered as the model fluids because their critical point conditions are more feasible than those of water. The similarities of water (prototype), CO 2 (model) and R134a (model) for depressurization in a pressure vessel were analyzed. (author)

  10. Power Systems Development Facility Gasification Test Run TC11

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2003-04-30

    This report discusses Test Campaign TC11 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode of operation using a particulate control device (PCD). Test run TC11 began on April 7, 2003, with startup of the main air compressor and the lighting of the gasifier start-up burner. The Transport Gasifier operated until April 18, 2003, when a gasifier upset forced the termination of the test run. Over the course of the entire test run, gasifier temperatures varied between 1,650 and 1,800 F at pressures from 160 to 200 psig during air-blown operations and around 135 psig during enriched-air operations. Due to a restriction in the oxygen-fed lower mixing zone (LMZ), the majority of the test run featured air-blown operations.

  11. The development of a field method for evaluating the success of reclamation efforts on abandoned mine lands

    International Nuclear Information System (INIS)

    Hunsberger, E.L.; Michaud, L.H.

    1994-01-01

    Abandoned Mine Lands (AML) are prevalent throughout Pennsylvania and in other areas of the US. Reclamation of these sites has been an ongoing concern of the Pennsylvania Department of Environmental Resources (PA DER) for over 20 yr. As the state of the technology improves, a variety of techniques have been utilized to rehabilitate AML. These reclamation efforts have resulted in vast improvements in the conditions of the sites, especially in water quality, erosion control, and aesthetic beauty. However, little work has been done to evaluate and document the success of individual reclamation techniques. Working with the Bureau of Abandoned Mine Reclamation, PA DER, a study was conducted at The Pennsylvania State University to address this need. The main goal of the project was to develop an evaluation system that could be easily carried out in the field by one person. The result of this study was the development of the Reclamation Success Evaluation System (RSES). The system utilizes three main parameters to evaluate reclamation success: (1) Surface Water Quality, (2) Extent of Erosion, and (3) Success of the Vegetative Cover. A series of guidelines and recommendations was developed for each of these evaluation parameters. The RSES was tested under field conditions by applying it to a watershed that contains both reclaimed and unreclaimed AML sites. This test proved that the RSES is an easily implemented and effective tool for evaluating the success of AML reclamation efforts. The system facilitates the comparison of reclamation efforts at different sites, it can be conducted by one person, and the results are easily interpreted

  12. Power Systems Development Facility Gasification Test Campaign TC25

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2008-12-01

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This report summarizes the results of TC25, the second test campaign using a high moisture lignite coal from the Red Hills mine in Mississippi as the feedstock in the modified Transport Gasifier configuration. TC25 was conducted from July 4, 2008, through August 12, 2008. During TC25, the PSDF gasification process operated for 742 hours in air-blown gasification mode. Operation with the Mississippi lignite was significantly improved in TC25 compared to the previous test (TC22) with this fuel due to the addition of a fluid bed coal dryer. The new dryer was installed to dry coals with very high moisture contents for reliable coal feeding. The TC25 test campaign demonstrated steady operation with high carbon conversion and optimized performance of the coal handling and gasifier systems. Operation during TC25 provided the opportunity for further testing of instrumentation enhancements, hot gas filter materials, and advanced syngas cleanup technologies. The PSDF site was also made available for testing of the National Energy Technology Laboratory's fuel cell module and Media Process Technology's hydrogen selective membrane with syngas from the Transport Gasifier.

  13. Power Systems Development Facility Gasification Test Campaign TC24

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2008-03-30

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This report summarizes the results of TC24, the first test campaign using a bituminous coal as the feedstock in the modified Transport Gasifier configuration. TC24 was conducted from February 16, 2008, through March 19, 2008. The PSDF gasification process operated for about 230 hours in air-blown gasification mode with about 225 tons of Utah bituminous coal feed. Operational challenges in gasifier operation were related to particle agglomeration, a large percentage of oversize coal particles, low overall gasifier solids collection efficiency, and refractory degradation in the gasifier solids collection unit. The carbon conversion and syngas heating values varied widely, with low values obtained during periods of low gasifier operating temperature. Despite the operating difficulties, several periods of steady state operation were achieved, which provided useful data for future testing. TC24 operation afforded the opportunity for testing of various types of technologies, including dry coal feeding with a developmental feeder, the Pressure Decoupled Advanced Coal (PDAC) feeder; evaluating a new hot gas filter element media configuration; and enhancing syngas cleanup with water-gas shift catalysts. During TC24, the PSDF site was also made available for testing of the National Energy Technology Laboratory's fuel cell module and Media Process Technology's hydrogen selective membrane.

  14. Tourism and Facilities Development in Three Art Traditions of Benin ...

    African Journals Online (AJOL)

    FIRST LADY

    some of the problems associated with the production of some Benin traditional art ... weather condition, facilities and patronage are important factors to be considered in .... vii. Ugie Ewere: This is the day the young ones in the City symbolically.

  15. Development laser light facility for uranium isotope separation

    International Nuclear Information System (INIS)

    Dickinson, G.J.

    1992-01-01

    A laser light facility has been built and successfully commissioned as part of a programme to explore the economic potential of Laser Isotope Separation of Uranium. The laser systems are comprised of tunable dye lasers pumped by copper vapour lasers. The requirements for optical beam stability, alignment of lasers in chains, and protection of optical coatings have made challenging demands on the engineering design and operation of the facility. (Author)

  16. Dance Facilities.

    Science.gov (United States)

    Ashton, Dudley, Ed.; Irey, Charlotte, Ed.

    This booklet represents an effort to assist teachers and administrators in the professional planning of dance facilities and equipment. Three chapters present the history of dance facilities, provide recommended dance facilities and equipment, and offer some adaptations of dance facilities and equipment, for elementary, secondary and college level…

  17. Environmental challenges and opportunities of the evolving North American electricity market : European electricity generating facilities: an overview of European regulatory requirements and standardization efforts

    International Nuclear Information System (INIS)

    Nichols, L.

    2002-06-01

    Several factors are affecting power generating facilities, such as the opening of both electricity and gas markets, and the pressure applied on generators and governments to ensure a steady energy supply for consumers. An additional factor is the pressure for the closing of nuclear power facilities. European siting and emissions requirements for coal-fired and natural gas generating facilities were presented in this background paper. In addition, the author provided an overview of the standardization process in place in Europe. The European Union and its functioning were briefly described, as well as a listing of relevant organizations. The current trends were examined. The document first introduced the European Union, and the next section dealt with Regulatory regime: the internal energy market. The third section examined the issue of Regulatory regime: generation and environmental regulations. Section four presented environmental management systems, followed by a section on standardization. Section six discussed European organizations involved in electricity issues, while the following section dealt with European commission programs. The last section briefly looked at the trends in the electricity sector, broaching topics such as compliance, electricity generation, and emissions trading. 52 refs., 2 tabs

  18. Innovative and practical technical development of nuclear energy. Efforts on proposal and recruitment type technical development of nuclear energy

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Shioiri, Akio; Hamada, Jun; Kanagawa, Takashi; Mori, Yukihide; Kouno, Koji

    2003-01-01

    In technical development of nuclear energy conceiving a view on energy environment problem at the 21st Century, technical development on innovative nuclear energy system as well as next generation LWR is an important subject. Even in Japan, on the 'Long-term program for research, development and utilization of nuclear energy (LPRNE)' summarized by the Atomic Energy Commission, investigation on R and Ds of innovative reactors under cooperation of government, industrial field, and universities is required. In the Energy Generalized Engineering Institute, by receiving a subsidy from the Ministry of Economy and Industry since 2000, a proposal recruitment business on innovative and practical technical development of nuclear energy has been carried out. Here were introduced hopeful and unique five themes out of them applied to the recruitment, such as a super-critical pressure water cooling reactor (SCPR), an integrated modular LWR (IMR): technical development for practice, technical development on general purpose boiling transitional analysis method, technical development on direct extraction of U and Pu from consumed fuels based on super-DIREX reprocessing method, and material transfer forecasting in natural barriers at landfill disposal of radioactive wastes. (G.K.)

  19. Power Systems Development Facility Gasification Test Run TC07

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-04-05

    This report discusses Test Campaign TC07 of the Kellogg Brown & Root, Inc. (KBR) Transport Reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). The Transport Reactor was operated as a pressurized gasifier during TC07. Prior to TC07, the Transport Reactor was modified to allow operations as an oxygen-blown gasifier. Test Run TC07 was started on December 11, 2001, and the sand circulation tests (TC07A) were completed on December 14, 2001. The coal-feed tests (TC07B-D) were started on January 17, 2002 and completed on April 5, 2002. Due to operational difficulties with the reactor, the unit was taken offline several times. The reactor temperature was varied between 1,700 and 1,780 F at pressures from 200 to 240 psig. In TC07, 679 hours of solid circulation and 442 hours of coal feed, 398 hours with PRB coal and 44 hours with coal from the Calumet mine, and 33 hours of coke breeze feed were attained. Reactor operations were problematic due to instrumentation problems in the LMZ resulting in much higher than desired operating temperatures in the reactor. Both reactor and PCD operations were stable and the modifications to the lower part of the gasifier performed well while testing the gasifier with PRB coal feed.

  20. Power Systems Development Facility Gasification Test Run TC08

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-06-30

    This report discusses Test Campaign TC08 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode using a particulate control device (PCD). The Transport Gasifier was operated as a pressurized gasifier in air- and oxygen-blown modes during TC08. Test Run TC08 was started on June 9, 2002 and completed on June 29. Both gasifier and PCD operations were stable during the test run with a stable baseline pressure drop. The oxygen feed supply system worked well and the transition from air to oxygen blown was smooth. The gasifier temperature was varied between 1,710 and 1,770 F at pressures from 125 to 240 psig. The gasifier operates at lower pressure during oxygen-blown mode due to the supply pressure of the oxygen system. In TC08, 476 hours of solid circulation and 364 hours of coal feed were attained with 153 hours of pure oxygen feed. The gasifier and PCD operations were stable in both enriched air and 100 percent oxygen blown modes. The oxygen concentration was slowly increased during the first transition to full oxygen-blown operations. Subsequent transitions from air to oxygen blown could be completed in less than 15 minutes. Oxygen-blown operations produced the highest synthesis gas heating value to date, with a projected synthesis gas heating value averaging 175 Btu/scf. Carbon conversions averaged 93 percent, slightly lower than carbon conversions achieved during air-blown gasification.

  1. Facilities for radiotherapy with ion beams status and worldwide developments

    CERN Document Server

    Wolf, B H

    1999-01-01

    Forty-five years after the first ion beam therapy in Berkeley around 25,000 cancer patients worldwide have been treated successfully. Ion accelerators, designed for nuclear research, delivered most of this treatment. The first hospital-based facility started operation in 1998 at Loma Linda California, the first for heavier ions at Chiba, Japan in 1994 and the first commercially delivered facilities started operation in 1998 at Kashiwa, Japan. In 2000, the Harvard Medical Centre, Boston, US, will commence operation and several new facilities are planned or under construction worldwide, although none in Australia. This paper will discuss the physical and biological advantages of ion beams over x-rays and electrons. In the treatment of cancer patients ion beam therapy is especially suited for localised tumours in radiation sensitive areas like skull or spine. Heavier ions are also effective in anoxic tumour cells (found around the normally oxygenated cell population). An additional advantage of the heavier carbo...

  2. Developing a safety report for an existing conversion facility

    International Nuclear Information System (INIS)

    Carisse, Hess

    2013-01-01

    A review of the process used to meet the regulatory requirements for a Safety Report at an existing conversion facility is described. This paper will cover the establishment of the regulatory criteria, selection of appropriate methodologies, identification of events and modeling of credible events. Once established there is on-going maintenance to deal with design changes and the need for periodic reviews will also be discussed. Challenges in dealing with the various phases, including incorporation of historical licensing documents, and lessons learned are presented. Of specific interest is the failure of the selected methodology to deal with infrastructure issues. One aspect of lessons learned that will be explored is the lack of an available mechanism for sharing information with similar fuel cycle facilities which is compounded by the fact that there are a small number of fuel cycle facilities compared to nuclear power plants. Possible approaches to dealing with this issue are also discussed. (authors)

  3. Estimation of inspection effort

    International Nuclear Information System (INIS)

    Mullen, M.F.; Wincek, M.A.

    1979-06-01

    An overview of IAEA inspection activities is presented, and the problem of evaluating the effectiveness of an inspection is discussed. Two models are described - an effort model and an effectiveness model. The effort model breaks the IAEA's inspection effort into components; the amount of effort required for each component is estimated; and the total effort is determined by summing the effort for each component. The effectiveness model quantifies the effectiveness of inspections in terms of probabilities of detection and quantities of material to be detected, if diverted over a specific period. The method is applied to a 200 metric ton per year low-enriched uranium fuel fabrication facility. A description of the model plant is presented, a safeguards approach is outlined, and sampling plans are calculated. The required inspection effort is estimated and the results are compared to IAEA estimates. Some other applications of the method are discussed briefly. Examples are presented which demonstrate how the method might be useful in formulating guidelines for inspection planning and in establishing technical criteria for safeguards implementation

  4. 32 CFR 22.310 - Statutes concerning certain research, development, and facilities construction grants.

    Science.gov (United States)

    2010-07-01

    ... higher education for the performance of research and development or for the construction of research or... for research and development, or of a grant for the construction of research or other facilities... research and development or for the construction of research or other facilities are to be awarded to...

  5. Research and development activities of a neutron generator facility

    International Nuclear Information System (INIS)

    Darsono Sudjatmoko; Pramudita Anggraita; Sukarman Aminjoyo

    2000-01-01

    The neutron generator facility at YNRC is used for elemental analysis, nuclear data measurement and education. In nuclear data measurement the focus is on re-evaluating the existing scattered nuclear activation cross-section to obtain systematic data for nuclear reactions such as (n,p), (n,α), and (n,2n). In elemental analysis it is used for analyzing the Nitrogen (N), Phosphor (P) and Potassium (K) contents in chemical and natural fertilizers (compost), protein in rice, soybean, and corn and pollution level in rivers. The neutron generator is also used for education and training of BATAN staff and university students. The facility can also produce neutron generator components. (author)

  6. Development of new irradiation facility for BWR safety research

    International Nuclear Information System (INIS)

    Okada, Yuji; Magome, Hirokatsu; Iida, Kazuhiro; Hanawa, Hiroshi; Ohmi, Masao

    2013-01-01

    In JAEA (Japan Atomic Energy Agency), about the irradiation embrittlement of the reactor pressure vessel and the stress corrosion cracking of reactor core composition apparatus concerning the long-term use of the light water reactor (BWR), in order to check the influence of the temperature, pressure, and water quality, etc on BWR condition. The water environmental control facility which performs irradiation assisted stress corrosion-cracking (IASCC) evaluation under BWR irradiation environment was fabricated in JMTR (Japan Materials Testing Reactor). This report is described the outline of manufacture of the water environmental control facility for doing an irradiation test using the saturation temperature capsule after JMTR re-operation. (author)

  7. Summary on experimental facilities and future developments at SINQ

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, G S [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-11-01

    With 13 experimental facilities under construction to become available during the first year of SINQ operation, a nearly complete suite of options for users will be made available to carry out research with neutrons at PSI. Three more facilities are under design and will come on line somewhat later. To complete the suite, three more specialized instruments are being evaluated. SINQ being a novel neutron source concept, significant scope for improvement is also seen on the source side. It is a major goal of PSI to exploit these opportunities and to make - among others - use of neutron instruments to carry out the necessary research. (author) 9 figs., 1 tab., 11 refs.

  8. Closed nuclear facilities in Estonia: developments and problems

    International Nuclear Information System (INIS)

    Realo, E.; Realo, K.

    2000-01-01

    At present Estonia has no operating nuclear or a radioactive material production facility. As a legacy of the past the country has become responsible for the decommissioning of two large nuclear cycle facilities of the former USSR. Besides limited funding, major problems arise from deficiencies in legislation, expertise, training and research. International co-operation has been of immense importance to overcome the problems, to establish the national radiation protection and radioactive waste management infrastructure and to launch decommissioning and remediation activities. An overview is given on the status and problems. Copyright (2000) Australasian Radiation Protection Society Inc

  9. Female genital mutilation and efforts to achieve Millennium Development Goals 3, 4, and 5 in southeast Nigeria.

    Science.gov (United States)

    Lawani, Lucky O; Onyebuchi, Azubuike K; Iyoke, Chukwuemeka A; Okeke, Nwabunike E

    2014-05-01

    To determine the prevalence of female genital mutilation (FGM), the common forms of FGM, reasons for the practice, associated obstetric outcomes, and how these have affected efforts to achieve Millennium Development Goals (MDGs) 3, 4, and 5 in southeast Nigeria. A prospective descriptive study of parturients in southeast Nigeria was conducted from January to December 2012. All primigravid women attending delivery services at 2 health institutions during the study period were recruited, examined, and classified using the 2008 WHO classification for FGM. The mean age of the 516 participants was 27.24±4.80 years and most (66.3%) had undergone FGM. Type II FGM was the most common form, accounting for 59.6% of cases. Most FGM procedures were performed in infancy (97.1%) and for cultural reasons (60.8%). Women who had undergone FGM had significantly higher risk for episiotomy, perineal tear, hemorrhage, cesarean delivery, neonatal resuscitation, fresh stillbirth/early neonatal death, and longer hospitalization, with higher risk ratios associated with higher degrees of FGM. FGM is still a common practice in southeast Nigeria, where its association with adverse reproductive outcomes militates against efforts to achieve MDGs 3, 4, and 5. Copyright © 2014 International Federation of Gynecology and Obstetrics. Published by Elsevier Ireland Ltd. All rights reserved.

  10. Developments in radiation, stimulation and observation facilities in luminescence measurements

    DEFF Research Database (Denmark)

    Bøtter-Jensen, L.; Andersen, C.E.; Duller, G.A.T.

    2003-01-01

    of magnitude up to more than 2 Gy/s. A separate bleaching facility has also been added to the reader, new powerful infrared (IR) light-emitting diodes have replaced the IR laser diode in the general OSL unit, and an IR laser has been included in the single-grain OSL attachment. This paper describes these new...

  11. Development techniques of computerized maintenance management system for nuclear fuel cycle examination facilities

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Yon Woo; Kim, S D; Soong, W S; Kim, G H; Oh, W H; Kim, Y G

    2000-12-01

    Normal operation of the facility is one of the key factors in the accomplishments of research goals. As confirmed by a case study of the influence of the facility operation condition on the research results, emphasis should be put on the facility preserve management. Facilities should be maintained in solid operational condition and their malfunctions should be repaired as soon as possible. The purpose of this project is to make propositions on the development of the facility Preserve management system which is to maximize the efficiency of the budget execution, manpower organization and maintenance planning, and is to minimize the duration of the operational pause due to malfunctions with the least disbursement.

  12. Development techniques of computerized maintenance management system for nuclear fuel cycle examination facilities

    International Nuclear Information System (INIS)

    Oh, Yon Woo; Kim, S. D.; Soong, W. S.; Kim, G. H.; Oh, W. H.; Kim, Y. G.

    2000-12-01

    Normal operation of the facility is one of the key factors in the accomplishments of research goals. As confirmed by a case study of the influence of the facility operation condition on the research results, emphasis should be put on the facility preserve management. Facilities should be maintained in solid operational condition and their malfunctions should be repaired as soon as possible. The purpose of this project is to make propositions on the development of the facility Preserve management system which is to maximize the efficiency of the budget execution, manpower organization and maintenance planning, and is to minimize the duration of the operational pause due to malfunctions with the least disbursement

  13. Development of a EUV Test Facility at the Marshall Space Flight Center

    Science.gov (United States)

    West, Edward; Pavelitz, Steve; Kobayashi, Ken; Robinson, Brian; Cirtain, Johnathan; Gaskin, Jessica; Winebarger, Amy

    2011-01-01

    This paper will describe a new EUV test facility that is being developed at the Marshall Space Flight Center (MSFC) to test EUV telescopes. Two flight programs, HiC - high resolution coronal imager (sounding rocket) and SUVI - Solar Ultraviolet Imager (GOES-R), set the requirements for this new facility. This paper will discuss those requirements, the EUV source characteristics, the wavelength resolution that is expected and the vacuum chambers (Stray Light Facility, Xray Calibration Facility and the EUV test chamber) where this facility will be used.

  14. Development of a Commonwealth Radioactive Waste Management Facility in Australia

    International Nuclear Information System (INIS)

    Hesterman, R.

    2006-01-01

    Full text: The Australian Government has commenced a process to build a Commonwealth Radioactive Waste Management Facility in the Northern Territory for management of radioactive wastes produced by Australian Government agencies. The Government is committed to safely managing its relatively small volume of low level radioactive waste (approximately 3800 cubic metres) and even smaller volume of intermediate level waste (around 400 cubic metres) that have been generated since the early 1950s from the research, medical and industrial use of radioactive materials. Australia has no high level radioactive waste as it does not have any nuclear power reactors. Australian states and territories are responsible for the safe and secure management of low level and intermediate level waste generated within their jurisdictions. They have jointly generated approximately 200 cubic metres of low level radioactive waste and under 100 cubic metres of intermediate level for the same period. In July 2004, the Prime Minister announced that the Australian Government would examine the suitability of Commonwealth land holdings, both onshore and offshore, for establishing the Facility. An initial assessment of offshore territories by the Department of Education, Science and Training (DEST) did not find any sufficiently suitable sites for hosting the Facility. This was due to the low elevation of most territories, inadequate infrastructure and incompatibility with existing land uses. In July 2005, Dr Nelson, then the Minister for Education, Science and Training, announced that three Department of Defence properties in the Northern Territory would be investigated for siting the Facility. The three properties are Fishers Ridge, about 43 kilometres southeast of Katherine; Harts Range, 100 kilometres directly northeast of Alice Springs; and Mt Everard, about 27 kilometres directly northwest of Alice Springs. In addition, the Commonwealth Radioactive Waste Management Act 2005, enacted in December

  15. Development of a distributed control system for the JAERI tandem accelerator facility

    International Nuclear Information System (INIS)

    Hanashima, Susumu

    2005-01-01

    In the JAERI tandem accelerator facility, we are building accelerator complex aiming generation and acceleration of radio nuclear beam. Several accelerators, ion sources and a charge breeder are installed in the facility. We are developing a distributed control system enabling smooth operation of the facility. We report basic concepts of the control system in this article. We also describe about a control hardware using plastic optical fiber, which is developed for the control system. (author)

  16. Establishing cause for developing and implementing a broad-based marketing effort for the health education field.

    Science.gov (United States)

    Stellefson, Michael; Barry, Adam; Chaney, Beth H; Chaney, J Don; Hanik, Bruce

    2011-05-01

    What exactly is health education? Professionals with advanced degrees in health education have most likely encountered questions such as these either during introductory coursework or from those inquiring about the field. These queries can prove quite perplexing when asked by individuals who are unaware of the health education profession. Because the act of marketing health education is crucial to the sustainability of the field, the purpose of this article is to (a) explore the issue of describing and promoting health education, (b) establish ideas that can facilitate the provision of coordinated marketing efforts, and (c) offer marketing management and implementation principles that can assist in marketing both health education and health educators. Based on this discussion, the authors suggest building mainstream consensus in regards to marketing message development and implementation to better position health education.

  17. Development of the Visegrad Group in the Context of Efforts to Accelerate the Convergence Processes by Joining the European Union

    Directory of Open Access Journals (Sweden)

    Hudec Martin

    2016-06-01

    Full Text Available The European integration efforts have been underway on the European continent for several centuries. Therefore, it is important for a better clarity and transparency of selected processes to understand the term European integration, meaning the integration endeavour into the European Union, which in the case of the Visegrad countries took a notable place since the early nineties of the 20th century. This research paper focuses on analysis and comparison of selected development processes in Czech Republic, Slovakia, Poland, and Hungary since the fall of the communist regime in 1989, resulting into the Visegrad Group formation, until joining the European Union in 2004. This research is based on the hypothesis that during this period, the V4 countries had a similar initial economic situation, converging together towards developed structures and corresponding mainly to questions such as what they were their starting situation and how have those countries developed further. It will be further addressed what was the cause of this development and how it continued, showing which countries have led the way, and what factors did influence them the most.

  18. Recommendations for energy conservation standards for new residential buildings - volume 3: Introduction and Background to the Standard Development Effort

    Energy Technology Data Exchange (ETDEWEB)

    1989-05-01

    The Energy Conservation for New Buildings Act of 1976, as amended, 42 U.S.C Section 6831 et. seq. requires the US Department of Energy to issue energy conservation standards for the design of new residential and commercial buildings. The standards will be mandatory only for the design of new federal buildings, and will serve as voluntary guidelines for the design of new non-federal buildings. This report documents the development and testing of a set of recommendations, from the American Society of Heating, Refrigeration and Air Conditioning Engineers, Inc. (ASHRAE) Special Projects Committee No. 53, designed to provide the technical foundation for the Congressionally-mandated energy standard for new residential buildings. The recommendations have been developed over the past 25 months by a multidisciplinary project team, under the management of the US Department of Energy and its prime contractor, Pacific Northwest Laboratory. Volume III -- Introduction and Background to the Standard Development Effort is a description of the Standard development process and contains the rationale for the general approach and specific criteria contained within the recommendations.

  19. Production Facility SCADA Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Holloway, Michael Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Baily, Scott A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wheat, Robert Mitchell Jr. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-03-23

    The following report covers FY 14 activities to develop supervisory control and data acquisition (SCADA) system for the Northstar Moly99 production facility. The goal of this effort is to provide Northstar with a baseline system design.

  20. Technical support to environmental restoration division for groundwater level monitoring effort at entombed Hallam Nuclear Power Facility. Final report, August 1, 1993--July 31, 1993

    International Nuclear Information System (INIS)

    1994-01-01

    This report provides an interim summary of information from a water-level monitoring program. The information was collected by the US Geological Survey (USGS) over a 6-month period. The monitoring program between the US DOE and the USGS was set up to measure water levels in 16 observation wells at the Hallam Nuclear Facility in Hallam, Nebraska. The summary of USGS data includes: (1) a description of the USGS monitoring program; (2) a description of the collection of continuous water-level data; (3) a description of the collection of monthly water-level data; (4) table of observation well number, latitude, longitude, and depth; (5) table of monthly ground-water levels data; (6) table of recorder wells, rainfall, and barometric pressure values; (7) table of recorder well, rainfall, and barometric pressure daily values; and (8) hydrographs of selected wells. 7 figs., 3 tabs

  1. Spatial development of sports facilities in Hungarian cities of county rank

    Directory of Open Access Journals (Sweden)

    Kozma Gábor

    2016-03-01

    Full Text Available Nowadays more and more attention is devoted to the spatial development of the location of sports facilities within cities. The main aim of our paper is to observe the most important spatial characteristics of their development in Hungarian cities of county rank. In these cities three main periods of development of sports facilities can be observed. Larger sports facilities were constructed especially on the edge of cities or in the suburbs, while in the case of smaller facilities a bigger role was played by locations within the city boundaries. As regards the factors influencing the location of sports facilities, the most important role was played by the location of available land areas, besides accessibility and from the mid-1960s links to existing facilities can be mentioned as well.

  2. The development of the advanced cryogenic radiometer facility at NRC

    Science.gov (United States)

    Gamouras, A.; Todd, A. D. W.; Côté, É.; Rowell, N. L.

    2018-02-01

    The National Research Council (NRC) of Canada has established a next generation facility for the primary realization of optical radiant power. The main feature of this facility is a new cryogenic electrical substitution radiometer with a closed-cycle helium cryocooler. A monochromator-based approach allows for detector calibrations at any desired wavelength. A custom-designed motion apparatus includes two transfer standard radiometer mounting ports which has increased our measurement capability by allowing the calibration of two photodetectors in one measurement cycle. Measurement uncertainties have been improved through several upgrades, including newly designed and constructed transimpedance amplifiers for the transfer standard radiometers, and a higher power broadband light source. The most significant improvements in uncertainty arise from the enhanced characteristics of the new cryogenic radiometer including its higher cavity absorptance and reduced non-equivalence effects.

  3. ICH antenna development on the ORNL RF Test Facility

    International Nuclear Information System (INIS)

    Gardner, W.L.; Bigelow, T.S.; Haste, G.R.; Hoffman, D.J.; Livesey, R.L.

    1987-01-01

    A compact resonant loop antenna is installed on the ORNL Radio Frequency Test Facility (RFTF). Facility characteristics include a steady-state magnetic field of ∼ 0.5 T at the antenna, microwave-generated plasmas with n e ∼ 10 12 cm -3 and T e ∼ 8 eV, and 100 kW of 25-MHz rf power. The antenna is tunable from ∼22--75 MHz, is designed to handle ≥1 MW of rf power, and can be moved 5 cm with respect to the port flange. Antenna characteristics reported and discussed include the effect of magnetic field on rf voltage breakdown at the capacitor, the effects of magnetic field and plasma on rf voltage breakdown between the radiating element and the Faraday shield, the effects of graphite on Faraday shield losses, and the efficiency of coupling to the plasma. 2 refs., 4 figs

  4. 32 CFR 644.424 - Development of public port or industrial facilities.

    Science.gov (United States)

    2010-07-01

    ... industrial facilities upon the available land shall file a written application with the District Engineer... development of public port or industrial facilities, the District Engineer shall give notice of such... 32 National Defense 4 2010-07-01 2010-07-01 true Development of public port or industrial...

  5. Diagnostic development at LLNL for the National Ignition Facility

    International Nuclear Information System (INIS)

    Sangster, T.C.; Cable, M.D.; Kilkenny, J.D.; Lerche, R.A.

    1996-01-01

    ICF implosions at the NIF will produce core plasma temperatures in excess of 10-keV and densities of order 100 g/cm 3 . Properties of these plasmas can be measured using a variety of optical, x-ray and nuclear techniques similar to those now in use at facilities such as Nova and Omega. Some of these techniques will be directly applicable on NIF while others, particularly the nuclear-based techniques, will change significantly

  6. Recent developments at the ISOL facility of GSI Darmstadt

    CERN Document Server

    Roeckl, E; Burkard, K; Döring, J; Grawe, H; Hüller, W; Kirchner, R; Mazzocchi, C; Mukha, I; Plettner, C

    2003-01-01

    The research programme pursued at the ISOL facility of GSI Darmstadt focuses on the study of decay properties of nuclei along the N congruent with Z line between the double shell closures at sup 5 sup 6 Ni and sup 1 sup 0 sup 0 Sn. In this report, the major scientific achievements obtained in the past two years are reviewed, with particular emphasis being put on the detection techniques.

  7. Professional Development for Early Childhood Educators: Efforts to Improve Math and Science Learning Opportunities in Early Childhood Classrooms

    Science.gov (United States)

    Piasta, Shayne B.; Logan, Jessica A. R.; Pelatti, Christina Yeager; Capps, Janet L.; Petrill, Stephen A.

    2014-01-01

    Because recent initiatives highlight the need to better support preschool-aged children’s math and science learning, the present study investigated the impact of professional development in these domains for early childhood educators. Sixty-five educators were randomly assigned to experience 10.5 days (64 hours) of training on math and science or on an alternative topic. Educators’ provision of math and science learning opportunities were documented, as were the fall-to-spring math and science learning gains of children (n = 385) enrolled in their classrooms. Professional development significantly impacted provision of science, but not math, learning opportunities. Professional development did not directly impact children’s math or science learning, although science learning was indirectly affected via the increase in science learning opportunities. Both math and science learning opportunities were positively associated with children’s learning. Results suggest that substantive efforts are necessary to ensure that children have opportunities to learn math and science from a young age. PMID:26257434

  8. Development of Demonstration Facility Design Technology for Advanced Nuclear Fuel Cycle Process

    International Nuclear Information System (INIS)

    Cho, Il Je; You, G. S.; Choung, W. M.

    2010-04-01

    The main objective of this R and D is to develop the PRIDE (PyRoprocess Integrated inactive DEmonstration) facility for engineering-scale inactive test using fresh uranium, and to establish the design requirements of the ESPF (Engineering Scale Pyroprocess Facility) for active demonstration of the pyroprocess. Pyroprocess technology, which is applicable to GEN-IV systems as one of the fuel cycle options, is a solution of the spent fuel accumulation problems. PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. The PRIDE evaluation data, such as performance evaluation data of equipment and operation experiences, will be directly utilized for the design of ESPF

  9. Summary report on development of bilateral servo manipulator (BSM) for nuclear fuel cycle facilities in the Japan Nuclear Cycle Development Institute

    International Nuclear Information System (INIS)

    Miki, Yasuo; Koizumi, Tsutomu; Aoshima, Atsushi; Kawanobe, Kazunori; Kobayashi, Yuichi

    2000-03-01

    In order to improve availability of nuclear fuel cycle facilities such as fuel reprocessing plants, reduce occupational radiation exposure, the Japan Nuclear Cycle Development Institute (JNC) has been developing an advanced remote manipulative system for fully remote maintenance and repair tasks in large volume repair cells. Fully remote maintenance and repair task is performed primarily by the utilization of overhead bridge cranes, mechanical master-slave manipulators and electro-mechanical power manipulators. This system requires also that plant process and remote processing equipment should be designed to provide modular or unit replacement based on the potential mode of system failures. Repair of equipment is performed following removal of the failed component from process line and transfer to the repair cell. Equipment repair in the cell is commonly carried out by the use of remote manipulators. However, the realization of fully remote maintenance facility requires so remote manipulative systems as to provide excellent controllability, durability and remote maintenance capability, development of a bilateral servo-manipulator was initiated in 1982. Two of BSM were installed in the Tokai Vitrification Facility (TVF) cell and their remote maintenance feasibility was evaluated. Following installation in the TVF, developing efforts toward achieving advanced remote maintenance capability for the Recycle Equipment Test Facility (RETF) have been made. This report summarizes mainly mechanical and control system design for improvement, particularly upgrading controllability. (Itami, H.)

  10. Savannah River Site human error data base development for nonreactor nuclear facilities

    International Nuclear Information System (INIS)

    Benhardt, H.C.; Held, J.E.; Olsen, L.M.; Vail, R.E.; Eide, S.A.

    1994-01-01

    As part of an overall effort to upgrade and streamline methodologies for safety analyses of nonreactor nuclear facilities at the Savannah River Site (SRS), a human error data base has been developed and is presented in this report. The data base fulfills several needs of risk analysts supporting safety analysis report (SAR) development. First, it provides a single source for probabilities or rates for a wide variety of human errors associated with the SRS nonreactor nuclear facilities. Second, it provides a documented basis for human error probabilities or rates. And finally, it provides actual SRS-specific human error data to support many of the error probabilities or rates. Use of a single, documented reference source for human errors, supported by SRS-specific human error data, will improve the consistency and accuracy of human error modeling by SRS risk analysts. It is envisioned that SRS risk analysts will use this report as both a guide to identifying the types of human errors that may need to be included in risk models such as fault and event trees, and as a source for human error probabilities or rates. For each human error in this report, ffime different mean probabilities or rates are presented to cover a wide range of conditions and influencing factors. The ask analysts must decide which mean value is most appropriate for each particular application. If other types of human errors are needed for the risk models, the analyst must use other sources. Finally, if human enors are dominant in the quantified risk models (based on the values obtained fmm this report), then it may be appropriate to perform detailed human reliability analyses (HRAS) for the dominant events. This document does not provide guidance for such refined HRAS; in such cases experienced human reliability analysts should be involved

  11. Common Data Acquisition Systems (DAS) Software Development for Rocket Propulsion Test (RPT) Test Facilities - A General Overview

    Science.gov (United States)

    Hebert, Phillip W., Sr.; Hughes, Mark S.; Davis, Dawn M.; Turowski, Mark P.; Holladay, Wendy T.; Marshall, PeggL.; Duncan, Michael E.; Morris, Jon A.; Franzl, Richard W.

    2012-01-01

    The advent of the commercial space launch industry and NASA's more recent resumption of operation of Stennis Space Center's large test facilities after thirty years of contractor control resulted in a need for a non-proprietary data acquisition system (DAS) software to support government and commercial testing. The software is designed for modularity and adaptability to minimize the software development effort for current and future data systems. An additional benefit of the software's architecture is its ability to easily migrate to other testing facilities thus providing future commonality across Stennis. Adapting the software to other Rocket Propulsion Test (RPT) Centers such as MSFC, White Sands, and Plumbrook Station would provide additional commonality and help reduce testing costs for NASA. Ultimately, the software provides the government with unlimited rights and guarantees privacy of data to commercial entities. The project engaged all RPT Centers and NASA's Independent Verification & Validation facility to enhance product quality. The design consists of a translation layer which provides the transparency of the software application layers to underlying hardware regardless of test facility location and a flexible and easily accessible database. This presentation addresses system technical design, issues encountered, and the status of Stennis' development and deployment.

  12. Development of construction specifications to attain clean rooms for the NOVA laser facility

    International Nuclear Information System (INIS)

    Benedix, C.P.

    1980-02-01

    This paper describes the process of defining technical requirements for a major Department of Energy Research and Development Facility and subsequent development of construction specifications for the clean spaces in that facility. The organizational interactions between technical client, Engineering and Construction elements are described. The importance of an interdisciplinary team approach is stressed. A brief description of the SHIVA Laser and NOVA Laser Clean Spaces is included to indicate the scope of the facility undertaking. A number of potential pitfalls are discussed that may be helpful to designers of new facilities

  13. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  14. An International Coordinated Effort to Further the Documentation & Development of Quality Assurance, Quality Control, and Best Practices for Oceanographic Observations

    Science.gov (United States)

    Bushnell, M.; Waldmann, C.; Hermes, J.; Tamburri, M.

    2017-12-01

    Many oceanographic observation groups create and maintain QA, QC, and best practices (BP) to ensure efficient and accurate data collection and quantify quality. Several entities - IOOS® QARTOD, AtlantOS, ACT, WMO/IOC JCOMM OCG - have joined forces to document existing practices, identify gaps, and support development of emerging techniques. While each group has a slightly different focus, many underlying QA/QC/BP needs can be quite common. QARTOD focuses upon real-time data QC, and has produced manuals that address QC tests for eleven ocean variables. AtlantOS is a research and innovation project working towards the integration of ocean-observing activities across all disciplines in the Atlantic Basin. ACT brings together research institutions, resource managers, and private companies to foster the development and adoption of effective and reliable sensors for coastal, freshwater, and ocean environments. JCOMM promotes broad international coordination of oceanographic and marine meteorological observations and data management and services. Leveraging existing efforts of these organizations is an efficient way to consolidate available information, develop new practices, and evaluate the use of ISO standards to judge the quality of measurements. ISO standards may offer accepted support for a framework for an ocean data quality management system, similar to the meteorological standards defined by WMO (https://www.wmo.int/pages/prog/arep/gaw/qassurance.html). We will first cooperatively develop a plan to create a QA/QC/BP manual. The resulting plan will describe the need for such a manual, the extent of the manual, the process used to engage the community in creating it, the maintenance of the resultant document, and how these things will be done. It will also investigate standards for metadata. The plan will subsequently be used to develop the QA/QC/BP manual, providing guidance which advances the standards adopted by IOOS, AtlantOS, JCOMM, and others.

  15. Development of safeguards information treatment system at facility level in Korea

    International Nuclear Information System (INIS)

    So, D.S.; Lee, B.D.; Song, D.Y.

    2001-01-01

    Safeguards Information Treatment System (SITS) at Facility level was developed to implement efficiently the obligations under IAEA comprehensive Safeguards Agreement, bilateral nuclear cooperation Agreements with other countries and domestic law, and to manage efficiently the information related to safeguards implementation at facility level in Korea. Nuclear facilities in Korea are categorized into 8 types based on its accounting characteristics as follows: (1) Item counting facility or bulk handling facility; (2) Batch follow-up facility or not; (3) MUF (Material Unaccounted For) occurrence or not; (4) Nuclear production facility or not; (5) Operation status of facility; (6) Information management of nuclear material transfer status between KMPs or not; (7) Indication of inventory KMP on the inventory change of nuclear material is required or not. Hardware and Software for SITS can be loaded on a personal computer under operation system of Window 2000 or Window NT. MS SQL server 7 and MS Internet Information Server were adopted for database management system and Web server, respectively. Network environment of SITS was designed to include nuclear research institute, nuclear power plants of PWR and CANDU, nuclear fuel fabrication facilities and other facilities. SITS can be operated standalone or under the client-server system if intranet exists. More detailed contents of SITS are described elsewhere. Each module of SITS will be tested during incorporation of existing data into SITS and SITS will be distributed to nuclear facilities in Korea

  16. Development and bin mapping of gene-associated interspecific SNPs for cotton (Gossypium hirsutum L.) introgression breeding efforts.

    Science.gov (United States)

    Hulse-Kemp, Amanda M; Ashrafi, Hamid; Zheng, Xiuting; Wang, Fei; Hoegenauer, Kevin A; Maeda, Andrea B V; Yang, S Samuel; Stoffel, Kevin; Matvienko, Marta; Clemons, Kimberly; Udall, Joshua A; Van Deynze, Allen; Jones, Don C; Stelly, David M

    2014-10-30

    Cotton (Gossypium spp.) is the largest producer of natural fibers for textile and is an important crop worldwide. Crop production is comprised primarily of G. hirsutum L., an allotetraploid. However, elite cultivars express very small amounts of variation due to the species monophyletic origin, domestication and further bottlenecks due to selection. Conversely, wild cotton species harbor extensive genetic diversity of prospective utility to improve many beneficial agronomic traits, fiber characteristics, and resistance to disease and drought. Introgression of traits from wild species can provide a natural way to incorporate advantageous traits through breeding to generate higher-producing cotton cultivars and more sustainable production systems. Interspecific introgression efforts by conventional methods are very time-consuming and costly, but can be expedited using marker-assisted selection. Using transcriptome sequencing we have developed the first gene-associated single nucleotide polymorphism (SNP) markers for wild cotton species G. tomentosum, G. mustelinum, G. armourianum and G. longicalyx. Markers were also developed for a secondary cultivated species G. barbadense cv. 3-79. A total of 62,832 non-redundant SNP markers were developed from the five wild species which can be utilized for interspecific germplasm introgression into cultivated G. hirsutum and are directly associated with genes. Over 500 of the G. barbadense markers have been validated by whole-genome radiation hybrid mapping. Overall 1,060 SNPs from the five different species have been screened and shown to produce acceptable genotyping assays. This large set of 62,832 SNPs relative to cultivated G. hirsutum will allow for the first high-density mapping of genes from five wild species that affect traits of interest, including beneficial agronomic and fiber characteristics. Upon mapping, the markers can be utilized for marker-assisted introgression of new germplasm into cultivated cotton and in

  17. Research reactor facilities, recent developments at Imperial College, London

    International Nuclear Information System (INIS)

    Franklin, S.J.; Goddard, A.J.H.; O Connell, J.

    1998-01-01

    The 100 kW CONSORT pool-type reactor is now the only Research Reactor in the UK. Because of its strategic importance, Imperial College is continuing and accelerating a programme of refurbishment of the control system, and planning for a further fuel charge. These plans are described and the progress to date discussed. To this end, a description of the enhanced Safety Case being written is provided here and refueling plans discussed. The current range of facilities available is described, and future plans highlighted. (author)

  18. Developing a clinical proton accelerator facility: Consortium-assisted technology transfer

    International Nuclear Information System (INIS)

    Slater, J.M.; Miller, D.W.; Slater, J.W.

    1991-01-01

    A hospital-based proton accelerator facility has emerged from the efforts of a consortium of physicists, engineers and physicians from several high-energy physics laboratories, industries and universities, working together to develop the requirements and conceptual design for a clinical program. A variable-energy medical synchrotron for accelerating protons to a prescribed energy, intensity and beam quality, has been placed in a hospital setting at Loma Linda University Medical Center for treating patients with localized cancer. Treatments began in October 1990. Scientists from Fermi National Accelerator Laboratory; Harvard Cyclotron Laboratory; Lawrence Berkeley Laboratories; the Paul Scherrer Institute; Uppsala, Sweden; Argonne, Brookhaven and Los Alamos National Laboratories; and Loma Linda University, all cooperated to produce the conceptual design. Loma Linda University contracted with Fermi National Accelerator Laboratory to design and build a 250 MeV synchrotron and beam transport system, the latter to guide protons into four treatment rooms. Lawrence Berkeley Laboratories consulted with Loma Linda University on the design of the beam delivery system (nozzle). A gantry concept devised by scientists at Harvard Cyclotron Laboratory, was adapted and fabricated by Science Applications International Corporation. The control and safety systems were designed and developed by Loma Linda University Radiation Research Laboratory. Presently, the synchrotron, beam transport system and treatment room hardware have been installed and tested and are operating satisfactorily

  19. BACK MUSCLES STRENGTH DEVELOPMENT BY MEANS OF INCREASE AND DECREASE OF EFFORT LOAD DURING GIANT SETS IN BODYBUILDING FOR MASSES

    Directory of Open Access Journals (Sweden)

    TIMNEA OLIVIA

    2013-01-01

    Full Text Available Abstract The aim of the study is to highlight methodological issues on the back muscle strength development by combining methodological procedures in masses bodybuilding.Methods. The study was conducted in three stages over a period of two months (March-April 2011, performing three workouts per week, monitoring the effective use of strength exercises to develop back muscles in the same muscle area by means of giant sets during workouts. In this context, we conducted a case study in "Tonik Fitness Club" in Bucharest, applied to two athletes of 28 and 34 years old. We recorded subjects’ evolutions during the training session, using statistical and mathematical method and graphical representation method.Results. The study content highlights the training programs depending on muscle zone and the specific methodological aspects, the weekly training program per muscle groups, the stages of study carrying out, the test and control trials applied in terms of anthropometric measurements and of back muscle strength development, and the application of the methodical procedure of effort load increase and decrease within the giant sets in a training micro-cycle.Discussion. The study focused on the training programs over two months, monitoring statistically the development of back muscle strength through the application of the procedure of effort load increase and decrease during giant sets in bodybuilding for masses. From the analysis of training programs content we noticed that three giant sets of exercises were used, performed in four series; each exercise within the giant sets was applied by means of the procedure of increasing and decreasing effort load. Study results emphasize the anthropometric measurement results: the study subjects have the age mean of 24.75, with a size of 175.2 cm and a weight of 83.75 kg at initial testing and a decrease by 2.12 kg in final testing. Regarding the chest perimeter, the inspiration is averaging 89.5 in initial

  20. Development of an auditable safety analysis in support of a radiological facility classification

    International Nuclear Information System (INIS)

    Kinney, M.D.; Young, B.

    1995-01-01

    In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23

  1. Preliminary analysis of West Valley Waste Removal System equipment development and mock demonstration facilities

    International Nuclear Information System (INIS)

    Janicek, G.P.

    1981-06-01

    This report defines seven areas requiring further investigation to develop and demonstrate a safe and viable West Valley Waste Removal System. These areas of endeavor are discussed in terms of their minimum facility requirements. It is concluded that utilizing separated specific facilities at different points in time is of a greater advantage than an exact duplication of the West Valley tanks. Savannah River Plant's full-scale, full-circle and half-circle tanks, and their twelfth scale model tank would all be useful to varying degrees but would require modifications. Hanford's proposed full-size mock tank would be useful, but is not seriously considered because its construction may not coincide with West Valley needs. Costs of modifying existing facilities and/or constructing new facilities are assessed in terms of their benefit to the equipment development and mock demonstration. Six facilities were identified for further analysis which would benefit development of waste removal equipment

  2. Development of DCC software dynamic test facility: past and future

    International Nuclear Information System (INIS)

    McDonald, A.M.; Thai, N.D.; Buijs, W.J.

    1996-01-01

    This paper describes a test facility for future dynamic testing of DCC software used in the control computers of CANDU nuclear power stations. It is a network of three computers: the DCC emulator, the dynamic CANDU plant simulator and the testing computer. Shared network files are used for input/output data exchange between computers. The DCC emulator runs directly on the binary image of the DCC software. The dynamic CANDU plant simulator accepts control signals from the DCC emulator and returns realistic plant behaviour. The testing computer accepts test scripts written in AECL Test Language. Both dynamic test and static tests may be performed on the DCC software to verify control program outputs and dynamic responses. (author)

  3. Professional Development through Organizational Assessment: Using APPA's Facilities Management Evaluation Program

    Science.gov (United States)

    Medlin, E. Lander; Judd, R. Holly

    2013-01-01

    APPA's Facilities Management Evaluation Program (FMEP) provides an integrated system to optimize organizational performance. The criteria for evaluation not only provide a tool for organizational continuous improvement, they serve as a compelling leadership development tool essential for today's facilities management professional. The senior…

  4. The development and operation of the international solar-terrestrial physics central data handling facility

    Science.gov (United States)

    Lehtonen, Kenneth

    1994-01-01

    The National Aeronautics and Space Administration (NASA) Goddard Space Flight Center (GSFC) International Solar-Terrestrial Physics (ISTP) Program is committed to the development of a comprehensive, multi-mission ground data system which will support a variety of national and international scientific missions in an effort to study the flow of energy from the sun through the Earth-space environment, known as the geospace. A major component of the ISTP ground data system is an ISTP-dedicated Central Data Handling Facility (CDHF). Acquisition, development, and operation of the ISTP CDHF were delegated by the ISTP Project Office within the Flight Projects Directorate to the Information Processing Division (IPD) within the Mission Operations and Data Systems Directorate (MO&DSD). The ISTP CDHF supports the receipt, storage, and electronic access of the full complement of ISTP Level-zero science data; serves as the linchpin for the centralized processing and long-term storage of all key parameters generated either by the ISTP CDHF itself or received from external, ISTP Program approved sources; and provides the required networking and 'science-friendly' interfaces for the ISTP investigators. Once connected to the ISTP CDHF, the online catalog of key parameters can be browsed from their remote processing facilities for the immediate electronic receipt of selected key parameters using the NASA Science Internet (NSI), managed by NASA's Ames Research Center. The purpose of this paper is twofold: (1) to describe how the ISTP CDHF was successfully implemented and operated to support initially the Japanese Geomagnetic Tail (GEOTAIL) mission and correlative science investigations, and (2) to describe how the ISTP CDHF has been enhanced to support ongoing as well as future ISTP missions. Emphasis will be placed on how various project management approaches were undertaken that proved to be highly effective in delivering an operational ISTP CDHF to the Project on schedule and

  5. Development of Facility Type Information Packages for Design of Air Force Facilities.

    Science.gov (United States)

    1983-03-01

    Washington: Government Printing Office. 49. U.S. Department of the Army. Project Development Brochures ; Part I, Functional Requirements. TM 5-800-3...Washington: Government Printing Office. May, 1974. 50. U.S. Department of the Air Force. Air Force Interior Design Pamplet . AFP 88-41. Washington: Govern

  6. Efforts for nuclear energy human resource development by industry-government-academic sectors cooperation. Nuclear Energy Human Resource Development Council Report

    International Nuclear Information System (INIS)

    Yamamoto, Shinji

    2009-01-01

    The report consists of eighteen sections such as the present conditions of nuclear energy, decreasing students in the department of technology and decreasing numbers of nuclear-related subjects, The Nuclear Energy Human Resources Development Program (HRD Program), The Nuclear Energy Human Resources Development Council (HRD Council), the industry-academia partnership for human resource development, the present situation of new graduates in the nuclear field, new workers of nuclear industry, the conditions of technical experts in the nuclear energy industry, long-range forecast of human resource, increasing international efforts, nuclear energy human resources development road map, three points for HRD, six basic subjects for HRD, the specific efforts of the industrial, governmental and academic sectors, promoting a better understanding of nuclear energy and supporting job hunting and employment, students to play an active part in the world, and support of the elementary and secondary schools. Change of numbers of nuclear-related subjects of seven universities, change of number of new graduates in nuclear field of various companies from 1985 to 2006, number of people employed by nuclear industries from 1998 to 2007, number of technical experts in the electric companies and the mining and manufacturing industries and forecast of number of technical experts in total nuclear industries are illustrated. (S.Y.)

  7. Responding to the 2015 CMS Proposed Rule Changes for LTC Facilities: A Call to Redouble Efforts to Prepare Students and Practitioners for Nursing Homes.

    Science.gov (United States)

    Bern-Klug, Mercedes; Connolly, Robert; Downes, Deirdre; Galambos, Colleen; Kusmaul, Nancy; Kane, Rosalie; Hector, Paige; Beaulieu, Elise

    2016-01-01

    In July of 2015, the Federal Register published for public comment proposed rule changes for nursing homes certified to receive Medicare and/or Medicaid. If the final rules are similar to the proposed rules, they will represent the largest change in federal rules governing nursing homes since the Nursing Home Reform Act which was part of OBRA 1987. The proposed changes have the potential to enhance the quality of care and quality of life of nursing home residents. Many of the proposed changes would directly affect the practice of social work and would likely expand the role for nursing home social workers. This article discusses the role that members of the National Nursing Home Social Work Network (NNHSW Network) played in developing and submitting a response to CMS. The article provides the context for the publication of the proposed rules, describes the process used by the NNHSW Network to develop and build support for comments on these rules, and also includes the actual comments submitted to CMS. Social work education programs and continuing education programs throughout the country will continue to have an important role to play in helping to prepare social work students and practitioners for a career in long-term care.

  8. Progress of JT-60SA Project: EU-JA joint efforts for assembly and fabrication of superconducting tokamak facilities and its research planning

    Energy Technology Data Exchange (ETDEWEB)

    Shirai, Hiroshi, E-mail: shirai.hiroshi@jaea.go.jp [JT-60SA Project Team, Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193 (Japan); Barabaschi, Pietro [JT-60SA EU-Home Team, Fusion for Energy, Boltsmannstr 2, Garching 85748 (Germany); Kamada, Yutaka [JT-60SA JA-Home Team, Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193 (Japan)

    2016-11-01

    Highlights: • JT-60SA Project is promoted under the BA Agreement and JA national programme. • JT-60SA is designed to operate in break-even equivalent condition for a long period. • JT-60SA Project supports and complements the ITER project, and promotes DEMO design. • Fabrication of JT-60SA components and assembly in Naka are steadily going on. • JT-60SA Research Plan has been developed jointly by EU and JA fusion communities. - Abstract: Aiming at supporting the early realization of fusion energy, the JT-60SA Project has shown steady progress for several years toward the first plasma in 2019 under the dual frameworks: the Satellite Tokamak Programme of the Broader Approach Agreement between EU and Japan, and the Japanese national programme. JT-60SA is a superconducting tokamak designed to operate in break-even equivalent conditions for a long pulse duration (typically 100 s) with a maximum plasma current of 5.5 MA. A variety of plasma control capabilities enable JT-60SA to contribute directly to the ITER project and also to DEMO by addressing key engineering and physics issues for advanced plasma operation. Design and fabrication of JT-60SA components, shared by the EU and Japan, started in 2007. Assembly in the torus hall started in January 2013, and welding work of the vacuum vessel sectors (seven 40° sectors and two 30° sectors) is currently ongoing on the cryostat base. Other components such as TF coils, PF coils, power supplies, cryogenic system, cryostat vessel, thermal shields and so on were or are being delivered to the Naka site for installation, assembly and commissioning. This paper gives technical progress on fabrication, installation and assembly of tokamak components and ancillary systems, as well as progress of the JT-60SA Research Plan being developed jointly by European and Japanese fusion communities.

  9. Development, application, and validation of a survey for infectious disease control practices at equine boarding facilities.

    Science.gov (United States)

    Kirby, Alanna T; Traub-Dargatz, Josie L; Hill, Ashley E; Kogan, Lori R; Morley, Paul S; Heird, James C

    2010-11-15

    To develop a questionnaire for self-assessment of biosecurity practices at equine boarding facilities and to evaluate infectious disease control practices in these facilities in Colorado. Cross-sectional study. 64 equine boarding facilities in Colorado. Survey questions were rated according to importance for prevention and containment of equine infectious diseases. Point values (range, 0 to 20) were assigned for possible responses, with greater values given for optimal infection control methods. Questionnaires were mailed to equine boarding facilities in Colorado advertised on the World Wide Web. Survey responses were compared with assessments made by a member of the research team during visits to 30 randomly selected facilities. Agreement among results was analyzed via a kappa test and rated as poor, fair, moderate, substantial, or nearly perfect. Survey responses were received for 64 of 163 (39%) equine boarding facilities. Scores ranged from 106 to 402 points (maximum possible score, 418). Most facilities received better scores for movement and housing of equids than for other sections of the survey. Respondents at 24 of 48 (50%) facilities that routinely received new equids reported isolation of new arrivals. Agreement between self-assessment by survey respondents and evaluation by a member of the research team was determined to be fair to substantial. Most equine boarding facilities have opportunities to improve measures for prevention or containment of contagious diseases (eg, isolation of newly arrived equids and use of written health management protocols). Most self-assessments of infection control practices were accurate.

  10. Development of Advanced Multizone Facilities for Microgravity Processing

    Science.gov (United States)

    1998-01-01

    NASA has been interested in experimental ground based study to investigate the fundamental processes involved in phase transformation processes during growth of metallic, nonmetallic and electronic materials. Solidification, vapor growth and solution growth techniques of growing crystals are of special interest because of the inherent importance of convection in the nutrient solution. Convection enhances the mass transport through the nutrient and results in faster growth rates. Availability of low gravity environment of space has provided scientists a new variable to control the extent of convection and thus isolate the diffusive phenomena for their better understanding. The thermal gradient at the liquid-solid interface is determined by the alloy characteristics, the hot zone temperature, cold zone temperature and the width of the insulating zone. The thermal profiles get established by the existing material and geometrical constraints of the experimental set up. The major effort under this research was devoted to designing a programmable furnace which can be used to obtain thermal profiles along the length of the sample as per the demands of the scientists. The furnace did not have active cooling of the zones. Only active heating and passive cooling were utilized.

  11. Testing and Development of a Shrouded Gas Turbine Engine in a Freejet Facility

    National Research Council Canada - National Science Library

    Garcia, Hector

    2000-01-01

    .... The combined cycle engine (CCE) could be incorporated into a variety of applications. The building of a new freejet facility and engine test rig at the Naval Postgraduate School enabled dynamic testing of the ongoing development of a turboramjet...

  12. Description of European Space Agency (ESA) Concept Development for a Mars Sample Receiving Facility (MSRF)

    Science.gov (United States)

    Vrublevskis, J.; Berthoud, L.; Guest, M.; Smith, C.; Bennett, A.; Gaubert, F.; Schroeven-Deceuninck, H.; Duvet, L.; van Winnendael, M.

    2018-04-01

    This presentation gives an overview of the several studies conducted for the European Space Agency (ESA) since 2007, which progressively developed layouts for a potential implementation of a Mars Sample Receiving Facility (MSRF).

  13. Development of an engineered safeguards system concept for a mixed-oxide fuel fabrication facility

    International Nuclear Information System (INIS)

    Chapman, L.D.; de Montmollin, J.M.; Deveney, J.E.; Fienning, W.C.; Hickman, J.W.; Watkins, L.D.; Winblad, A.E.

    1976-08-01

    An initial concept of an Engineered Safeguards System for a representative commercial mixed-oxide fuel fabrication facility is presented. Computer simulation techniques for evaluation and further development of the concept are described. An outline of future activity is included

  14. Conceptual design of a 6-10 MJ driver for a high gain target development facility

    International Nuclear Information System (INIS)

    Olson, R.E.

    1986-01-01

    Commercial application of inertial confinement fusion would require low yield (≅200-500 MJ), high gain (≥80) fusion targets. It is thought that the development off such targets would reqiure a 5-10 year research program utilizing one or more dedicated nuclear facilities with drivers capable of delivering on-target pulses of 6-10 MJ at the rate of several shots per day. The ''Target Development Facility'' (TDF) is the light ion driven version of such a facility. A TDF driver concept based upon reasonable extrapolation from present-day technology is described in this paper

  15. Development of a spent fuel management technology research and test facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, S W; Noh, S K; Lee, J S. and others

    1997-12-01

    This study was intended to develop concept for a pilot-scale remote operation facility for longer term management of spent fuel and therefrom to provide technical requirement for later basic design of the facility. Main scope of work for the study was to revise the past (1990) conceptual design in functions, scale, hot cell layout, etc. based on user requirements. Technical reference was made to the PKA facility in Germany, through collaboration with appropriate partner, to elaborate the design and requirements. A simulator of the conceptual design was also developed by use of virtual reality technique by 3-D computer graphics for equipment and building. (author). 18 tabs., 39 figs

  16. Development and Commissioning of a Small/Mid-Size Wind Turbine Test Facility: Preprint

    Energy Technology Data Exchange (ETDEWEB)

    Valyou, D.; Arsenault, T.; Janoyan, K.; Marzocca, P.; Post, N.; Grappasonni, G.; Arras, M.; Coppotelli, G.; Cardenas, D.; Elizalde, H.; Probst, O.

    2015-01-01

    This paper describes the development and commissioning tests of the new Clarkson University/Center for Evaluation of Clean Energy Technology Blade Test Facility. The facility is a result of the collaboration between the New York State Energy Research and Development Authority and Intertek, and is supported by national and international partners. This paper discusses important aspects associated with blade testing and includes results associated with modal, static, and fatigue testing performed on the Sandia National Laboratories' Blade Systems Design Studies blade. An overview of the test capabilities of the Blade Test Facility are also provided.

  17. Design, fabrication, and mockup testing in the Remote Maintenance Development Facility

    International Nuclear Information System (INIS)

    Carter, J.A.; Jacobs, R.T.; Bingham, G.E.

    1978-01-01

    The Remote Maintenance Development Facility (RMDF) at the Idaho National Engineering Laboratory (INEL) was installed and used extensively for full-scale development, mockup and testing of remote maintenance requirements for the New Waste Calcining Facility (NWCF). By performing remote handling tests, the NWCF handling concepts, techniques and remote capabilities were proven workable prior to construction. Presented in this paper is a description of the RMDF and its purpose, functions, and handling capabilities as they were used in support of the NWCF

  18. Design, fabrication, and mockup testing in the remote maintenance development facility

    International Nuclear Information System (INIS)

    Carter, J.A.; Jacobs, R.T.; Bingham, G.E.

    1978-01-01

    The Remote Maintenance Development Facility at the Idaho National Engineering Laboratory was installed and used extensively for full-scale development, mockup, and testing of remote maintenance requirements for the New Waste Calcining Facility (NWCF). By performing remote handling tests, the NWCF handling concepts, techniques, and remote capabilities were proven workable prior to construction. A description of the RMDF and its purpose, functions, and handling capabilities as they were used in support of the NWCF is presented

  19. Influence of fleet renewal and trawl development on landings per unit effort of the Danish northern shrimp (Pandalus borealis) fishery

    DEFF Research Database (Denmark)

    Eigaard, Ole Ritzau; Munch-Petersen, Sten

    2011-01-01

    Recent stock assessments of the Pandalus stock in the Skagerrak (ICES Division IIIa) and the Norwegian Deep (Division IVa east) have relied largely on a time-series of landings per unit effort (lpue) calculated from Danish logbook data. Because of fleet renewal and trawl-size changes, the relatio......Recent stock assessments of the Pandalus stock in the Skagerrak (ICES Division IIIa) and the Norwegian Deep (Division IVa east) have relied largely on a time-series of landings per unit effort (lpue) calculated from Danish logbook data. Because of fleet renewal and trawl-size changes...

  20. The development of radiation hardened robot for nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Ho; Jung, Seung Ho; Kim, Byung Soo and others

    2000-04-01

    The work conducted in this stage covers development of core technology of tele-robot system including monitoring technique in high-level radioactive area, tele-sensing technology and radiation-hardened technology for the non-destructive tele-inspection system which monitors the primary coolant system during the normal operations of PHWR(Pressurized Heavy Water Reactor) NPPs and measures the decrease of bending part of feeder pipe during overall. Based on the developed core technology, the monitoring mobile robot system of the primary coolant system and the feeder pipe inspecting robot system are developed.

  1. The development of radiation hardened robot for nuclear facility

    International Nuclear Information System (INIS)

    Kim, Seung Ho; Jung, Seung Ho; Kim, Byung Soo and others

    2000-04-01

    The work conducted in this stage covers development of core technology of tele-robot system including monitoring technique in high-level radioactive area, tele-sensing technology and radiation-hardened technology for the non-destructive tele-inspection system which monitors the primary coolant system during the normal operations of PHWR(Pressurized Heavy Water Reactor) NPPs and measures the decrease of bending part of feeder pipe during overall. Based on the developed core technology, the monitoring mobile robot system of the primary coolant system and the feeder pipe inspecting robot system are developed

  2. Development of High-Level Safety Requirements for a Pyroprocessing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Seok Jun; Jo, Woo Jin; You, Gil Sung; Choung, Won Myung; Lee, Ho Hee; Kim, Hyun Min; Jeon, Hong Rae; Ku, Jeong Hoe; Lee, Hyo Jik [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    Korea Atomic Energy Research Institute (KAERI) has been developing a pyroproceesing technology to reduce the waste volume and recycle some elements. The pyroprocessing includes several treatment processes which are related with not only radiological and physical but also chemical and electrochemical properties. Thus, it is of importance to establish safety design requirements considering all the aspects of those properties for a reliable pyroprocessing facility. In this study, high-level requirements are presented in terms of not only radiation protection, nuclear criticality, fire protection, and seismic safety but also confinement and chemical safety for the unique characteristics of a pyroprocessing facility. Several high-level safety design requirements such as radiation protection, nuclear criticality, fire protection, seismic, confinement, and chemical processing were presented for a pyroprocessing facility. The requirements must fulfill domestic and international safety technology standards for a nuclear facility. Furthermore, additional requirements should be considered for the unique electrochemical treatments in a pyroprocessing facility.

  3. Development of demonstration facility design technology for advanced nuclear fuel cycle process

    International Nuclear Information System (INIS)

    Cho, Il Je; You, G. S.; Choung, W. M.; Lee, E. P.; Hong, D. H.; Lee, W. K.; Ku, J. H.; Moon, S. I.; Kwon, K. C.; Lee, K. I. and other

    2012-04-01

    PRIDE Facility, pyroprocess mock-up facility, is the first facility that is operated in inert atmosphere in the country. By using the facility, the functional requirements and validity of pyroprocess technology and facility related to the advanced fuel cycle can be verified with a low cost. Then, PRIDE will contribute to evaluate the technology viability, proliferation resistance and possibility of commercialization of the pyroprocess technology. It is essential to develop design technologies for the advanced nuclear fuel cycle demonstration facilities and complete the detailed design of PRIDE facility with capabilities of the stringent inert atmosphere control, fully remote operation which are necessary to develop the high-temperature molten salts technology. For these, it is necessary to design the essential equipment of large scale inert cell structure and the control system to maintain the inert atmosphere, and evaluate the safety. To construct the hot cell system which is appropriate for pyroprocess, some design technologies should be developed, which include safety evaluation for effective operation and maintenance, radiation safety analysis for hot cell, structural analysis, environmental evaluation, HVAC systems and electric equipment

  4. Challenges and Opportunities for Biological Mass Spectrometry Core Facilities in the Developing World.

    Science.gov (United States)

    Bell, Liam; Calder, Bridget; Hiller, Reinhard; Klein, Ashwil; Soares, Nelson C; Stoychev, Stoyan H; Vorster, Barend C; Tabb, David L

    2018-04-01

    The developing world is seeing rapid growth in the availability of biological mass spectrometry (MS), particularly through core facilities. As proteomics and metabolomics becomes locally feasible for investigators in these nations, application areas associated with high burden in these nations, such as infectious disease, will see greatly increased research output. This article evaluates the rapid growth of MS in South Africa (currently approaching 20 laboratories) as a model for establishing MS core facilities in other nations of the developing world. Facilities should emphasize new services rather than new instruments. The reduction of the delays associated with reagent and other supply acquisition would benefit both facilities and the users who make use of their services. Instrument maintenance and repair, often mediated by an in-country business for an international vendor, is also likely to operate on a slower schedule than in the wealthiest nations. A key challenge to facilities in the developing world is educating potential facility users in how best to design experiments for proteomics and metabolomics, what reagents are most likely to introduce problematic artifacts, and how to interpret results from the facility. Here, we summarize the experience of 6 different institutions to raise the level of biological MS available to researchers in South Africa.

  5. Wire Scanner Beam Profile Measurements: LANSCE Facility Beam Development

    International Nuclear Information System (INIS)

    Gilpatrick, John D.; Batygin, Yuri K.; Gonzales, Fermin; Gruchalla, Michael E.; Kutac, Vincent G.; Martinez, Derwin; Sedillo, James Daniel; Pillai, Chandra; Rodriguez Esparza, Sergio; Smith, Brian G.

    2012-01-01

    The Los Alamos Neutron Science Center (LANSCE) is replacing Wire Scanner (WS) beam profile measurement systems. Three beam development tests have taken place to test the new wire scanners under beam conditions. These beam development tests have integrated the WS actuator, cable plant, electronics processors and associated software and have used H - beams of different beam energy and current conditions. In addition, the WS measurement-system beam tests verified actuator control systems for minimum profile bin repeatability and speed, checked for actuator backlash and positional stability, tested the replacement of simple broadband potentiometers with narrow band resolvers, and tested resolver use with National Instruments Compact Reconfigurable Input and Output (cRIO) Virtual Instrumentation. These beam tests also have verified how trans-impedance amplifiers react with various types of beam line background noise and how noise currents were not generated. This paper will describe these beam development tests and show some resulting data.

  6. Wire Scanner Beam Profile Measurements: LANSCE Facility Beam Development

    Energy Technology Data Exchange (ETDEWEB)

    Gilpatrick, John D. [Los Alamos National Laboratory; Batygin, Yuri K. [Los Alamos National Laboratory; Gonzales, Fermin [Los Alamos National Laboratory; Gruchalla, Michael E. [Los Alamos National Laboratory; Kutac, Vincent G. [Los Alamos National Laboratory; Martinez, Derwin [Los Alamos National Laboratory; Sedillo, James Daniel [Los Alamos National Laboratory; Pillai, Chandra [Los Alamos National Laboratory; Rodriguez Esparza, Sergio [Los Alamos National Laboratory; Smith, Brian G. [Los Alamos National Laboratory

    2012-05-15

    The Los Alamos Neutron Science Center (LANSCE) is replacing Wire Scanner (WS) beam profile measurement systems. Three beam development tests have taken place to test the new wire scanners under beam conditions. These beam development tests have integrated the WS actuator, cable plant, electronics processors and associated software and have used H{sup -} beams of different beam energy and current conditions. In addition, the WS measurement-system beam tests verified actuator control systems for minimum profile bin repeatability and speed, checked for actuator backlash and positional stability, tested the replacement of simple broadband potentiometers with narrow band resolvers, and tested resolver use with National Instruments Compact Reconfigurable Input and Output (cRIO) Virtual Instrumentation. These beam tests also have verified how trans-impedance amplifiers react with various types of beam line background noise and how noise currents were not generated. This paper will describe these beam development tests and show some resulting data.

  7. Development of beam instruments at JAERI cyclotron facility

    Energy Technology Data Exchange (ETDEWEB)

    Okumura, Susumu; Fukuda, Mitsuhiro; Ishibori, Ikuo; Agematsu, Takashi; Yokota, Watalu; Nara, Takayuki; Nakamura, Yoshiteru; Arakawa, Kazuo [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment

    1997-03-01

    A beam phase monitor and two kinds of fluence distribution monitors have been developed for measuring characteristics of cyclotron beams. The beam phase monitor provides a beam phase signal for tuning a beam chopping system and a beam phase selection system. A two-dimensional fluence distribution on a large area is measured with fluence distribution monitors. (author)

  8. 10 CFR 770.8 - May DOE transfer real property at defense nuclear facilities for economic development at less...

    Science.gov (United States)

    2010-01-01

    ... facilities for economic development at less than fair market value? 770.8 Section 770.8 Energy DEPARTMENT OF ENERGY TRANSFER OF REAL PROPERTY AT DEFENSE NUCLEAR FACILITIES FOR ECONOMIC DEVELOPMENT § 770.8 May DOE transfer real property at defense nuclear facilities for economic development at less than fair market...

  9. The development of robot application technology in nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Jong Min; Kim, Seung Ho; Kim, Chang Hoi; Kim, Byung Soo; Hwang, Suk Young; Sohn, Surg Won; Lee, Yong Bum; Kim, Woong Ki

    1991-01-01

    The project of this study is intended to develop the application technology for autonomous robotic systems operated in hostile environments where human access is prohibited. The mobile robot, named as KAEROT, has been designed by adopting the controller of multiprocessor of distributed system architecture in order to get flexibility. 2 driving wheel assembles and 1 steering mechanism has been adopted and each of them is made of planetary wheel which is composed of a couple of star-like arms with 3 wheels. The 6 D.O.F of manipulator is controlled by CCD camera mounted on the elbow and base, to provide wide view of the working area for tele-operation. The off-line programming system is being developed for checking robot constraint violations within workspace prior to execution of robot programming. (Author)

  10. The development of robot application technology in nuclear facilities

    International Nuclear Information System (INIS)

    Kim, Seung Ho; Lee, Jong Min; Kim, Chang Hoe; Kim, Byung Soo; Sohn, Surg Won; Hwoang, Suk Yeoung; Lee, Yong Bum; Kim, Woong Ki

    1992-01-01

    The goal of this project is to develop a mobile teleoperated system to do the job effectively of inspection and light duty maintenance work inside the containment buildings under severe environments. This is the second year of the project. Basically remotely controlled concept was adopted to a mobile robot which was equipped with 7 degrees of freedom anthropomorphic manipulator providing dexterous control. Closed-loop schemes for solving the inverse kinematics of the redundant manipulator were investigated and decentralized adaptive controller was designed for the end effector to track the desired trajectory. A new stair climbing algorithm was proposed to go over irregular stairs, and simulations and experiments were carried out. User-friendly teleoperated control console was designed to comply with human engineering. Off-line programming technique has been developing to enhance the safety and efficiency in task assignment of robot. This research will in consequence be in a strong position to bid for further work in this area. (Author)

  11. Progress towards developing consistent design and evaluation guidelines for DOE facilities subjected to natural phenomena hazards

    International Nuclear Information System (INIS)

    Kennedy, R.P.; Short, S.A.; McDonald, J.R.; McCann, M.W. Jr.; Reed, J.W.

    1985-01-01

    Probabilistic definitions of earthquake, wind and tornado natural phenomena hazards for many Department of Energy (DOE) facilities throughout the United States have been developed. In addition, definitions of the flood hazards which might affect these locations are currently being developed. The Department of Energy Natural Phenomena Hazards Panel is now preparing a document to provide guidance and criteria for DOE facility managers to assure that DOE facilities are adequately constructed to resist the effects of natural phenomena such as earthquake, strong wind and flood. The intent of this document is to provide instruction on how to utilize the hazard definitions to evaluate existing facilities and design new facilities in a manner such that the risk of adverse consequences is consistent with the cost, function, and danger to the public or environment of the facility. Potential effects on facilities of natural phenomena hazards are emphasized in this paper. The philosophy for mitigating these effects to be employed in the design and evaluation guidelines is also presented

  12. The development of radiation-hardened robot for nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Ho; Jung, S. H.; Kim, Chang Hoi; Seo, Yong Chil [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-11-01

    The objective of this project is to make a optimal design of differential planetary reducer through the stress analysis. The developed gears are able a high efficiency and manufactured with small size. This reducer of planetary type is able to transmit high rode torque in one stage. This light weight, high efficiency differential planetary reducer, as a new attempt of planetary reducer type, can obtain a high reduction ratio with the simple mechanism which is impossible with the traditional planetary reducer type. 19 refs., 26 figs., 11 tabs. (Author)

  13. Environmental consequences of hydroelectric development: the role of facility size and type

    International Nuclear Information System (INIS)

    Gleick, P.H.

    1992-01-01

    The development of hydroelectric power throughout the world is receiving renewed attention as the economic, political, and environmental costs of conventional energy production rise. There is currently a perception that hydroelectricity has environmental and economic advantages over electricity produced by conventional energy technologies, but there is a paucity of information about the environmental impacts of hydroelectric facilities as a function of size and type. We characterize the environmental impacts of hydroelectric developments and quantify these impacts as a function of the size and type of project. Several unexpected conclusions arise from our analysis. For most hydroelectric facilities, size, as measured by installed capacity, is not necessarily a good indicator or the severity of environmental costs. For impacts such as land flooded and evaporative water lost, smaller facilities cause greater environmental disruptions per unit of energy produced than do larger facilities. (Author)

  14. Development of a standardized transfusion ratio as a metric for evaluating dialysis facility anemia management practices.

    Science.gov (United States)

    Liu, Jiannong; Li, Suying; Gilbertson, David T; Monda, Keri L; Bradbury, Brian D; Collins, Allan J

    2014-10-01

    Because transfusion avoidance has been the cornerstone of anemia treatment for patients with kidney disease, direct measurement of red blood cell transfusion use to assess dialysis facility anemia management performance is reasonable. We aimed to explore methods for estimating facility-level standardized transfusion ratios (STfRs) to assess provider anemia treatment practices. Retrospective cohort study. Point prevalent US hemodialysis patients on January 1, 2009, with Medicare as primary payer and dialysis duration of 90 days or longer were included (n = 223,901). All dialysis facilities with eligible patients were included (n = 5,345). Dialysis facility assignment. Receiving a red blood cell transfusion in the inpatient or outpatient setting. We evaluated 3 approaches for estimating STfR: ratio of observed to expected numbers of transfusions (STfR(obs)), a Bayesian approach (STfR(Bayes)), and a modified version of the Bayesian approach (STfR(modBayes)). The overall national transfusion rate in 2009 was 23.2 per 100 patient-years. Our model for predicting the expected number of transfusions performed well. For large facilities, all 3 STfRs worked well. However, for small facilities, while the STfR(modBayes) worked well, STfR(obs) values demonstrated instability and the STfR(Bayes) may produce more bias. Administration of transfusions to dialysis patients reflects medical practice both within and outside the dialysis unit. Some transfusions may be deemed unavoidable and transfusion practices are subject to considerable regional variation. Development of an STfR metric is feasible and reasonable for assessing anemia treatment at dialysis facilities. The STfR(obs) is simple to calculate and works well for larger dialysis facilities. The STfR(modBayes) is more analytically complex, but facilitates comparisons across all dialysis facilities, including small facilities. Copyright © 2014 National Kidney Foundation, Inc. Published by Elsevier Inc. All rights reserved.

  15. Development of oilfield facilities on a nature reserve

    International Nuclear Information System (INIS)

    Long, P.J.; Long, V.L.

    1991-01-01

    This paper reports on Airlie Island which is a small (26 hectare) sand cay, located 35km north of Onslow in Western Australia. In common with other islands in the region, Airlie is a nesting site for seabirds and turtles, but its two primary conservation resources are the large Wedge-tailed Shearwater rookery which covers 64% of the island and an endemic skink species. Its conservation values have prompted the Western Australian State Government to declare the entire island a nature reserve set apart for the preservation of flora and fauna. In 1987 Western Mining Corporation Pty Ltd. developed the South Pepper and North herald oilfields and part of this development included the siting of an oil terminal on Airlie Island. It may be expected that the conservation resources of the island and the Company's requirements for land would be incompatible. However, a careful study of the local environment and the creation of a detailed plan to manage this environment resulted in an acceptable compromise

  16. Future aerospace ground test facility requirements for the Arnold Engineering Development Center

    Science.gov (United States)

    Kirchner, Mark E.; Baron, Judson R.; Bogdonoff, Seymour M.; Carter, Donald I.; Couch, Lana M.; Fanning, Arthur E.; Heiser, William H.; Koff, Bernard L.; Melnik, Robert E.; Mercer, Stephen C.

    1992-01-01

    Arnold Engineering Development Center (AEDC) was conceived at the close of World War II, when major new developments in flight technology were presaged by new aerodynamic and propulsion concepts. During the past 40 years, AEDC has played a significant part in the development of many aerospace systems. The original plans were extended through the years by some additional facilities, particularly in the area of propulsion testing. AEDC now has undertaken development of a master plan in an attempt to project requirements and to plan for ground test and computational facilities over the coming 20 to 30 years. This report was prepared in response to an AEDC request that the National Research Council (NRC) assemble a committee to prepare guidance for planning and modernizing AEDC facilities for the development and testing of future classes of aerospace systems as envisaged by the U.S. Air Force.

  17. Development of Design Concept and Applied Technology for RCP Performance Test Facility

    International Nuclear Information System (INIS)

    Park, Sang Jin; Lee, Jung Ho; Yoon, Seok Ho

    2010-02-01

    Performance test facility for RCP (reactor coolant pump) is essential to verify the performance and reliability of RCP before installation in the nuclear power plant. The development of RCP for new-type reactor and the performance verification of hydraulic revolving body also needs the RCP test facility. The design concept of test loop and the technology of flow rate measurement are investigated in this research

  18. Accident-generated radioactive particle source term development for consequence assessment of nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Sutter, S.L.; Ballinger, M.Y.; Halverson, M.A.; Mishima, J.

    1983-04-01

    Consequences of nuclear fuel cycle facility accidents can be evaluated using aerosol release factors developed at Pacific Northwest Laboratory. These experimentally determined factors are compiled and consequence assessment methods are discussed. Release factors can be used to estimate the fraction of material initially made airborne by postulated accident scenarios. These release fractions in turn can be used in models to estimate downwind contamination levels as required for safety assessments of nuclear fuel cycle facilities. 20 references, 4 tables

  19. Radioactive beam diagnostics status and development at the Spiral facility

    International Nuclear Information System (INIS)

    Chautard, F.; Baelde, J.L.; Bucaille, F.; Duneau, P.; Galard, C.; Le Blay, J.P.; Loyant, J.M.; Martina, L.; Ulrich, M.; Laune, B.

    2001-01-01

    In 2001 the first radioactive beam will be accelerated in the CIME cyclotron of the SPIRAL project at GANIL. In order to be able to tune such low intensity beams in the cyclotron (down to few particles per second), a silicon and a scintillator detectors are mounted on probes. They measure the beam energy and the beam phase/RF in the cyclotron as a function of the radius. Such fragile diagnostics are meant to be used routinely from the control room by non-specialists in instrumentation and in presence of various beam intensities. Therefore, a program is developed to control and secure the acquisition procedure, the measurements and the isochronism correction. Additional detectors are installed at a fixed position in the ejection line before the experimental areas. Additionally, a diamond detector is foreseen to be installed in the machine to be tested in order to ease the CIME operation. (authors)

  20. Status of electro-nuclear facilities development in ITEP

    Energy Technology Data Exchange (ETDEWEB)

    Chuvilo, I.V. [ITEP, Moscow (Russian Federation)

    1995-10-01

    The concept of plutonium management, both weapon-grade and power, should be developed taking into account the history of previous stages of the nuclear industry and ideas which guided the process of their implementation. Theoretical studies of several versions of a neutron multiplying subcritical system based on thermal and epithermal neutrons are conducted in ITEP. Systems with several neutron multiplying subcritical sections are considered connected by neutron flux propagation from a previous section to subsequent one. This could be implemented by the use of neutron valves separating these sections that permits to decrease the requirements imposed upon proton beam power significantly. Heterogeneous and homogeneous approaches to implementation of such systems are studied. There are many problems associated with nuclear constants and their classification. Measurements are performed of thermal effects in various materials under proton beam irradiation. Problems associated with materials are in the process of investigation too. Joint programs and division of labour should be organized.

  1. Development of Infrastructure Facilities for Superconducting RF Cavity Fabrication, Processing and 2 K Characterization at RRCAT

    Science.gov (United States)

    Joshi, S. C.; Raghavendra, S.; Jain, V. K.; Puntambekar, A.; Khare, P.; Dwivedi, J.; Mundra, G.; Kush, P. K.; Shrivastava, P.; Lad, M.; Gupta, P. D.

    2017-02-01

    An extensive infrastructure facility is being established at Raja Ramanna Centre for Advanced Technology (RRCAT) for a proposed 1 GeV, high intensity superconducting proton linac for Indian Spallation Neutron Source. The proton linac will comprise of a large number of superconducting Radio Frequency (SCRF) cavities ranging from low beta spoke resonators to medium and high beta multi-cell elliptical cavities at different RF frequencies. Infrastructure facilities for SCRF cavity fabrication, processing and performance characterization at 2 K are setup to take-up manufacturing of large number of cavities required for future projects of Department of Atomic Energy (DAE). RRCAT is also participating in a DAE’s approved mega project on “Physics and Advanced technology for High intensity Proton Accelerators” under Indian Institutions-Fermilab Collaboration (IIFC). In the R&D phase of IIFC program, a number of high beta, fully dressed multi-cell elliptical SCRF cavities will be developed in collaboration with Fermilab. A dedicated facility for SCRF cavity fabrication, tuning and processing is set up. SCRF cavities developed will be characterized at 2K using a vertical test stand facility, which is already commissioned. A Horizontal Test Stand facility has also been designed and under development for testing a dressed multi-cell SCRF cavity at 2K. The paper presents the infrastructure facilities setup at RRCAT for SCRF cavity fabrication, processing and testing at 2K.

  2. Developing tourism facilities based on geotourism in Silalahi Village, Geopark Toba Caldera

    Science.gov (United States)

    Ginting, Nurlisa; Sasmita, Anggun

    2018-03-01

    Toba Caldera is one of the biggest lakes in Indonesia with supervolcano geology phenomenon, and its result amazing natural resources. It makes Toba Lake become the number one tourism in North Sumatera. However, tourism in Toba Lake is still needed development. Geotourism is one of the concept that suitable for this case. It is because geotourism is a new development tourism concept that focuses on the natural and geological phenomenon. Silalahi Village is one of the areas in Toba Caldera that still needs development, especially in tourism facilities sector. This research aims to investigation the facilities concept based on geotourism in Silalahi Village that would be analyzed by three element of tourism facilities namely, accommodation, support facilities and tourism auxiliary facilities. The method used for this research is mixed methods by distributing 100 questionnaires, observations directly to the area and interviews with three informants related parties interested in tourism, such as local people, government, and academics. The data would be processed and analyzed with techniques of exploration. The result shows that the three elements of tourism facilities are still lacking and needs to improve to increase the economy and tourism in the area.

  3. Development of the RRR Cold Neutron Source facility

    International Nuclear Information System (INIS)

    Masriera, N.; Lecot, C.; Hergenreder, D.; Lovotti, O.; Serebrov, A.; Zakharov, A.; Mityukhlyaev, V.

    2003-01-01

    This paper describes some general design issues on the Cold Neutron Source (CNS) of the Replacement Research Reactor (RRR) for the Australian Nuclear Science and Technology Organisation (ANSTO). The description covers different aspects of the design: the requirements that lead to an innovative design, the overall design itself and the definition of a technical approach in order to develop the necessary design solutions. The RRR-CNS has liquid Deuterium (LD2) moderator, sub-cooled to ensure maximum moderation efficiency, flowing within a closed natural circulation Thermosiphon loop. The Thermosiphon is surrounded by a CNS Vacuum Containment made of zirconium alloy, that provides thermal insulation and a multiple barriers scheme to prevent Deuterium from mixing with water or air. Consistent with international practice, this vessel is designed to withstand any hypothetical energy reaction should Deuterium and air mix in its interior. The applied design approach allows ensuring that the RRR-CNS, in spite of being innovative, will meet all the design, performance and quality requirements. (author)

  4. Study of developing nuclear fabrication facility's integrated emergency response manual

    International Nuclear Information System (INIS)

    Kim, Taeh Yeong; Cho, Nam Chan; Han, Seung Hoon; Moon, Jong Han; Lee, Jin Hang; Min, Guem Young; Han, Ji Ah

    2016-01-01

    Public begin to pay attention to emergency management. Thus, public's consensus on having high level of emergency management system up to advanced country's is reached. In this social atmosphere, manual is considered as key factor to prevent accident or secure business continuity. Therefore, we first define possible crisis at KEPCO Nuclear Fuel (hereinafter KNF) and also make a 'Reaction List' for each crisis situation at the view of information-design. To achieve it, we analyze several country's crisis response manual and then derive component, indicate duties and roles at the information-design point of view. From this, we suggested guideline to make 'Integrated emergency response manual(IERM)'. The manual we used before have following few problems; difficult to applicate at the site, difficult to deliver information. To complement these problems, we searched manual elements from the view of information-design. As a result, we develop administrative manual. Although, this manual could be thought as fragmentary manual because it confined specific several agency/organization and disaster type

  5. The Development of a Radiation Hardened Robot for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Seung Ho; Kim, Chang Hoi; Seo, Yong Chil (and others)

    2007-04-15

    We has been developed two remotely controlled robotic systems. One is a underwater vehicle for inspection of the internal structures of PWRs and retrieving foreign stubs in the reactor pressure vessels and reactor coolant pipes. The other robotic system consists of a articulated-type mobile robot capable of recovering the failure of the fuel exchange machine and a mini modular mobile robot for inspection of feeder pipes with ultrasonic array sensors in PHWRs. The underwater robot has been designed by considering radiation effect, underwater condition, and accessibility to the working area. The size of underwater robot is designed to enter the cold legs. A extendable manipulator is mounted on the mobile robot, which can restore nuclear fuel exchange machine. The mini modular mobile robot is composed of dual inch worm mechanisms, which are constructed by two gripper bodies that can fix the robot body on to the pipe and move along the longitudinal and to rotate in a circumferential direction to access all of the outer surfaces of the pipe.

  6. Power Systems Development Facility. Quarterly report, July 1--September 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    This quarterly technical progress report summarizes the work completed during the third quarter of a project entitled Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion. The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phase expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: carbonizer/pressurized circulating fluidized bed gas source; hot gas cleanup units to mate to all gas streams; combustion gas turbine; and fuel cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF).

  7. Methods for developing seismic and extreme wind-hazard models for evaluating critical structures and equipment at US Department of Energy facilities and commercial plutonium facilities in the United States

    International Nuclear Information System (INIS)

    Coats, D.W.; Murray, R.C.; Bernreuter, D.L.

    1981-01-01

    Lawrence Livermore National Laboratory (LLNL) is developing seismic and wind hazard models for the US Department of Energy (DOE). The work is part of a three-phase effort to establish building design criteria developed with a uniform methodology for seismic and wind hazards at the various DOE sites throughout the United States. In Phase 1, LLNL gathered information on the sites and their critical facilities, including nuclear reactors, fuel-reprocessing plants, high-level waste storage and treatment facilities, and special nuclear material facilities. Phase 2 - development of seismic and wind hazard models - is discussed in this paper, which summarizes the methodologies used by seismic and extreme-wind experts and gives sample hazard curves for the first sites to be modeled. These hazard models express the annual probability that the site will experience an earthquake (or windspeed) greater than some specified magnitude. In the final phase, the DOE will use the hazards models and LLNL-recommended uniform design criteria to evaluate critical facilities. The methodology presented in this paper also was used for a related LLNL study - involving the seismic assessment of six commercial plutonium fabrication plants licensed by the US Nuclear Regulatory Commission (NRC). Details and results of this reassessment are documented in reference

  8. Development of post-irradiation test facility for domestic production of 99Mo

    International Nuclear Information System (INIS)

    Taguchi, Taketoshi; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Nishikata, Kaori; Ishida, Takuya; Kawamata, Kazuo

    2013-01-01

    JMTR focus on the activation method. By carrying out the preliminary tests using irradiation facilities existing, and verification tests using the irradiation facility that has developed in the cutting-edge research and development strategic strengthening business, as irradiation tests towards the production of 99 Mo, we have been conducting research and development that can contribute to supply about 25% for 99 Mo demand in Japan and the stable supply of radiopharmaceutical. This report describes a summary of the status of the preliminary tests for the production of 99 Mo: Maintenance of test equipment in the facility in JMTR hot laboratory in preparation for research and development for the production of 99 Mo in JMTR and using MoO 3 pellet irradiated at Kyoto University Research Reactor Institute (KUR). (author)

  9. Design concepts and advanced telerobotics development for facilities in the back end of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Feldman, M.J.

    1987-01-01

    In the Fuel Recycle Division at the Oak Ridge National Laboratory (ORNL), a comprehensive remote systems development program has existed for the past seven years. The new remote technology under development is expected to significantly improve remote operations by extending the range of tasks accomplished by remote means and increasing the efficiency of remote work undertaken. Five areas of the development effort are primary contributors to the goal of higher operating efficiency for major facilities for the back end of the nuclear fuel cycle. These areas are (1) the single-cell concept, (2) the low-flow ventilation concept, (3) television viewing, (4) equipment-mounting racks, and (5) force-reflecting manipulation. These somewhat innovative directions are products of a design process where the technical scenario to be accomplished, the remote equipment to accomplish the scenario, and the facility design to house the equipment, are considered in an iterative design process to optimize performance, maximize long-term costs effectiveness, and minimize initial capital outlay. (author)

  10. Design concepts and advanced telerobotics development for facilities in the back end of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Feldman, M.J.

    1987-01-01

    In the Fuel Recycle Division at the Oak Ridge National Laboratory, a comprehensive remote systems development program has existed for the past seven years. The new remote technology under development is expected to significantly improve remote operations by extending the range of tasks accomplished by remote means and increasing the efficiency of remote work undertaken. Five areas of the development effort are primary contributors to the goal of higher operating efficiency for major facilities for the back end of the nuclear fuel cycle. These areas are the single-cell concept, the low-flow ventilation concept, television viewing, equipment-mounting racks, and force-reflecting manipulation. These somewhat innovative directions are products of a design process where the technical scenario to be accomplished, the remote equipment to accomplish the scenario, and the facility design to house the equipment, are considered in an iterative design process to optimize performance, maximize long-term costs effectiveness, and minimize initial capital outlay. 14 refs., 3 figs

  11. Native American Technical Assistance and Training for Renewable Energy Resource Development and Electrical Generation Facilities Management

    Energy Technology Data Exchange (ETDEWEB)

    A. David Lester

    2008-10-17

    The Council of Energy Resource Tribes (CERT) will facilitate technical expertise and training of Native Americans in renewable energy resource development for electrical generation facilities, and distributed generation options contributing to feasibility studies, strategic planning and visioning. CERT will also provide information to Tribes on energy efficiency and energy management techniques.This project will provide facilitation and coordination of expertise from government agencies and private industries to interact with Native Americans in ways that will result in renewable energy resource development, energy efficiency program development, and electrical generation facilities management by Tribal entities. The intent of this cooperative agreement is to help build capacity within the Tribes to manage these important resources.

  12. Source term development for the 300 Area Treated Effluent Disposal Facility

    International Nuclear Information System (INIS)

    Bendixsen, R.B.

    1994-04-01

    A novel method for developing a source term for radiation and hazardous material content of sludge processing equipment and barrels in a new waste water treatment facility is presented in this paper. The 300 Area Treated Effluent Disposal Facility (TEDF), located at the Hanford Site near Richland, Washington, will treat process sewer waste water from the 300 Area and discharge a permittable effluent flow into the Columbia River. A process information and hazards analysis document needed a process flowsheet detailing the concentrations of radionuclides, inorganics, and organics throughout the process, including the sludge effluent flow. A hazards analysis for a processing facility usually includes a flowsheet showing the process, materials, heat balances, and instrumentation for that facility. The flow sheet estimates stream flow quantities, activities, compositions, and properties. For the 300 Area TEDF, it was necessary to prepare the flow sheet with all of the information so that radiation doses to workers could be estimated. The noble method used to develop the 300 Area TEDF flowsheet included generating recycle factors. To prepare each component in the flowsheet, precipitation, destruction, and two recycle factors were developed. The factors were entered into a spreadsheet and provided a method of estimating the steady-state concentrations of all of the components in the facility. This report describes how the factors were developed, explains how they were used in developing the flowsheet, and presents the results of using these values to estimate radiation doses for personnel working in the facility. The report concludes with a discussion of the effect of estimates of radioactive and hazardous material concentrations on shielding design and the need for containment features for equipment in the facility

  13. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I

    International Nuclear Information System (INIS)

    Abdou, M.

    1984-10-01

    The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios

  14. A stand alone computer system to aid the development of mirror fusion test facility RF heating systems

    International Nuclear Information System (INIS)

    Thomas, R.A.

    1983-01-01

    The Mirror Fusion Test Facility (MFTF-B) control system architecture requires the Supervisory Control and Diagnostic System (SCDS) to communicate with a LSI-11 Local Control Computer (LCC) that in turn communicates via a fiber optic link to CAMAC based control hardware located near the machine. In many cases, the control hardware is very complex and requires a sizable development effort prior to being integrated into the overall MFTF-B system. One such effort was the development of the Electron Cyclotron Resonance Heating (ECRH) system. It became clear that a stand alone computer system was needed to simulate the functions of SCDS. This paper describes the hardware and software necessary to implement the SCDS Simulation Computer (SSC). It consists of a Digital Equipment Corporation (DEC) LSI-11 computer and a Winchester/Floppy disk operating under the DEC RT-11 operating system. All application software for MFTF-B is programmed in PASCAL, which allowed us to adapt procedures originally written for SCDS to the SSC. This nearly identical software interface means that software written during the equipment development will be useful to the SCDS programmers in the integration phase

  15. Development of Accident Scenario for Interim Spent Fuel Storage Facility Based on Fukushima Accident

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dongjin; Choi, Kwangsoon; Yoon, Hyungjoon; Park, Jungsu [KEPCO-E and C, Yongin (Korea, Republic of)

    2014-05-15

    700 MTU of spent nuclear fuel is discharged from nuclear fleet every year and spent fuel storage is currently 70.9% full. The on-site wet type spent fuel storage pool of each NPP(nuclear power plants) in Korea will shortly exceed its storage limit. Backdrop, the Korean government has rolled out a plan to construct an interim spent fuel storage facility by 2024. However, the type of interim spent fuel storage facility has not been decided yet in detail. The Fukushima accident has resulted in more stringent requirements for nuclear facilities in case of beyond design basis accidents. Therefore, there has been growing demand for developing scenario on interim storage facility to prepare for beyond design basis accidents and conducting dose assessment based on the scenario to verify the safety of each type of storage.

  16. Stanford Synchrotron Radiation Laboratory 1991 activity report. Facility developments January 1991--March 1992

    International Nuclear Information System (INIS)

    Cantwell, K.; St. Pierre, M.

    1992-01-01

    SSRL is a national facility supported primarily by the Department of Energy for the utilization of synchrotron radiation for basic and applied research in the natural sciences and engineering. It is a user-oriented facility which welcomes proposals for experiments from all researchers. The synchrotron radiation is produced by the 3.5 GeV storage ring, SPEAR, located at the Stanford Linear Accelerator Center (SLAC). SPEAR is a fully dedicated synchrotron radiation facility which operates for user experiments 7 to 9 months per year. SSRL currently has 24 experimental stations on the SPEAR storage ring. There are 145 active proposals for experimental work from 81 institutions involving approximately 500 scientists. There is normally no charge for use of beam time by experimenters. This report summarizes the activity at SSRL for the period January 1, 1991 to December 31, 1991 for research. Facility development through March 1992 is included

  17. Stanford Synchrotron Radiation Laboratory 1991 activity report. Facility developments January 1991--March 1992

    Energy Technology Data Exchange (ETDEWEB)

    Cantwell, K.; St. Pierre, M. [eds.

    1992-12-31

    SSRL is a national facility supported primarily by the Department of Energy for the utilization of synchrotron radiation for basic and applied research in the natural sciences and engineering. It is a user-oriented facility which welcomes proposals for experiments from all researchers. The synchrotron radiation is produced by the 3.5 GeV storage ring, SPEAR, located at the Stanford Linear Accelerator Center (SLAC). SPEAR is a fully dedicated synchrotron radiation facility which operates for user experiments 7 to 9 months per year. SSRL currently has 24 experimental stations on the SPEAR storage ring. There are 145 active proposals for experimental work from 81 institutions involving approximately 500 scientists. There is normally no charge for use of beam time by experimenters. This report summarizes the activity at SSRL for the period January 1, 1991 to December 31, 1991 for research. Facility development through March 1992 is included.

  18. Development of computer model for radionuclide released from shallow-land disposal facility

    International Nuclear Information System (INIS)

    Suganda, D.; Sucipta; Sastrowardoyo, P.B.; Eriendi

    1998-01-01

    Development of 1-dimensional computer model for radionuclide release from shallow land disposal facility (SLDF) has been done. This computer model is used for the SLDF facility at PPTA Serpong. The SLDF facility is above 1.8 metres from groundwater and 150 metres from Cisalak river. Numerical method by implicit method of finite difference solution is chosen to predict the migration of radionuclide with any concentration.The migration starts vertically from the bottom of SLDF until the groundwater layer, then horizontally in the groundwater until the critical population group. Radionuclide Cs-137 is chosen as a sample to know its migration. The result of the assessment shows that the SLDF facility at PPTA Serpong has the high safety criteria. (author)

  19. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Warner, C.L. (comp.)

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described.

  20. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    International Nuclear Information System (INIS)

    Warner, C.L.

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described

  1. Development tendencies of energy facilities in Central and Eastern European countries in transition

    International Nuclear Information System (INIS)

    Riesner, W.; Stuits, I.; Zeltins, N.

    1999-01-01

    The present work considers development problems of energy facilities in Central and Eastern European countries being in transition in the period from 1990 to 1997. It outlines the changes in economical situation during this period. The paper also shows the development dynamics for economic indicators in 11 countries and analyses them for each country taken separately. (author)

  2. Principles of developing the knowledge portal on safety of nuclear facilities

    International Nuclear Information System (INIS)

    Klevtsov, A.; Orlov, V.Yu.; Trubchaninov, S.A.

    2010-01-01

    The general principles of developing the knowledge portal on safety of nuclear facilities are considered in the article. In future, these principles can be used for implementing the project on development of the knowledge portal for the State Nuclear Regulatory Committee of Ukraine.

  3. Development and evaluation of fully automated demand response in large facilities

    Energy Technology Data Exchange (ETDEWEB)

    Piette, Mary Ann; Sezgen, Osman; Watson, David S.; Motegi, Naoya; Shockman, Christine; ten Hope, Laurie

    2004-03-30

    This report describes the results of a research project to develop and evaluate the performance of new Automated Demand Response (Auto-DR) hardware and software technology in large facilities. Demand Response (DR) is a set of activities to reduce or shift electricity use to improve electric grid reliability, manage electricity costs, and ensure that customers receive signals that encourage load reduction during times when the electric grid is near its capacity. The two main drivers for widespread demand responsiveness are the prevention of future electricity crises and the reduction of electricity prices. Additional goals for price responsiveness include equity through cost of service pricing, and customer control of electricity usage and bills. The technology developed and evaluated in this report could be used to support numerous forms of DR programs and tariffs. For the purpose of this report, we have defined three levels of Demand Response automation. Manual Demand Response involves manually turning off lights or equipment; this can be a labor-intensive approach. Semi-Automated Response involves the use of building energy management control systems for load shedding, where a preprogrammed load shedding strategy is initiated by facilities staff. Fully-Automated Demand Response is initiated at a building or facility through receipt of an external communications signal--facility staff set up a pre-programmed load shedding strategy which is automatically initiated by the system without the need for human intervention. We have defined this approach to be Auto-DR. An important concept in Auto-DR is that a facility manager is able to ''opt out'' or ''override'' an individual DR event if it occurs at a time when the reduction in end-use services is not desirable. This project sought to improve the feasibility and nature of Auto-DR strategies in large facilities. The research focused on technology development, testing

  4. Healthy Libraries Develop Healthy Communities: Public Libraries and their Tremendous Efforts to Support the Affordable Care Act.

    Science.gov (United States)

    Collins, Lydia N

    This article is about the dedication of public library staff and my role as the Consumer Health Coordinator for the National Network of Libraries of Medicine, Middle Atlantic Region (NN/LM MAR) to support outreach efforts for health insurance enrollment under the Patient Protection and Affordable Care Act (ACA). ACA was created in order to ensure that all Americans have access to affordable health care. What we didn't know is that public libraries across the nation would play such an integral role in the health insurance enrollment process. The National Network of Libraries of Medicine (NN/LM) worked closely with public libraries in order to assist with this new role. As we approach the second enrollment and re-enrollment periods, public libraries are gearing up once again to assist with ACA.

  5. Policy efforts used to develop awareness aimed at increased students' scientific literacy and career choices in mathematics, science and engineering

    Science.gov (United States)

    Whitfield, Frank Albert

    The lack of an adequate supply of human resources in science and engineering has been well documented. Efforts from a number of agencies, such as the National Science Foundation, have been implemented to alleviate this national problem. However, it is unclear what concerted efforts state agencies are taking to increase the number of African American students' scientific literacy, and career choices in science and engineering. The purpose of this study was to select a talent pool of African American students who are academically able to pursue a career in a math-based major. The selection of this talent pool lead to the recommendation of an encouragement process model to be used by the Tennessee Board of Regents (TBR) system to encourage the selectees of this talent pool to enter math-based programs at TBR universities. An integrated literature review was conducted. This review includes perspectives on national, state, and local educational policy decisions which affect educational purposes, institutional governance and secondary-postsecondary linkages. Existing TBR system data were analyzed and tabulated. This tabulated data along with the recommended model will be offered to the TBR system for possible adoption. The results of these data support the methodological notion that there are an appreciable number of potential TBR system African American students academically able to enter math related majors who, however, may be reluctant to choose a career direction in a math-based career field. Implications of this study and suggestions for further research are discussed. On an applied level, the study might suggest to other states ways in which to deal with similar problems.

  6. The Relationship between the Development of Time and Effort Management and Experiences of the Teaching-Learning Environment in a University Context

    Science.gov (United States)

    Parpala, Anna; Asikainen, Henna; Ruohoniemi, Mirja; Lindblom-Ylänne, Sari

    2017-01-01

    Time and effort management skills have proved to be very important in studying, as they provide a foundation for both study success and engagement in university studies across the world. The paper focuses on how these skills develop during university studies in veterinary medicine, and examines possible changes in relation to students' experiences…

  7. The LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2003-01-01

    The availability of isotope grade, Highly Enriched Uranium (HEU), from the United States for use in the manufacture of targets for molybdenum-99 production in AECL's NRU research reactor has been a key factor to enable MDS Nordion to develop a reliable, secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets is a proven and established method that has reliably produced medical isotopes for several decades. The HEU process provides predictable, consistent yields for our high-volume, molybdenum-99 production. Other medical isotopes such as I-131 and Xe-133, which play an important role in nuclear medicine applications, are also produced from irradiated HEU targets as a by-product of the molybdenum-99 process. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the commissioning of two MAPLE reactors and an associated isotope processing facility (the New Processing Facility). The new MAPLE facilities, which will be dedicated exclusively to medical isotope production, will provide an essential contribution to a secure, robust global healthcare system. Design and construction of these facilities has been based on a life cycle management philosophy for the isotope production process. This includes target irradiation, isotope extraction and waste management. The MAPLE reactors will operate with Low Enriched Uranium (LEU) fuel, a significant contribution to the objectives of the RERTR program. The design of the isotope production process in the MAPLE facilities is based on an established process - extraction of isotopes from HEU target material. This is a proven technology that has been demonstrated over more than three decades of operation. However, in support of the RERTR program and in compliance with U.S. legislation, MDS Nordion has undertaken a LEU Target Development and Conversion Program for the MAPLE facilities. This paper will provide an

  8. Development of a free-electron laser user facility for the extreme ultraviolet

    International Nuclear Information System (INIS)

    Newnam, B.E.

    1987-01-01

    A free-electron laser user facility for scientific experimentation in the extreme ultraviolet is being developed at Los Alamos. A series of laser oscillators and amplifiers, driven by a single, rf linear accelerator, will generate broadly tunable, picosecond-pulse, coherent radiation from 1 nm to 400 nm. The design and output parameters of this facility are described, comparison with synchrotron radiation sources is made, and recent progress in developing the three primary components (electron beam, undulator, and resonator mirrors) is reviewed, and various categories of scientific applications are indicated

  9. Development programs on decommissioning technology for reactors and fuel cycle facilities in Japan

    International Nuclear Information System (INIS)

    Fujiki, K.

    1992-01-01

    The Science and Technology Agency (STA) of Japan is promoting technology development for decommissioning of nuclear facilities by entrusting various research programs to concerned research organisations: JAERI, PNC and RANDEC, including first full scale reactor decommissioning of JPDR. According to the results of these programs, significant improvement on dismantling techniques, decontamination, measurement etc. has been achieved. Further development of advanced decommissioning technology has been started in order to achieve reduction of duration of decommissioning work and occupational exposures in consideration of the decommissioning of reactors and fuel cycle facilities. (author) 5 refs.; 7 figs.; 1 tab

  10. Safety report content and development for test loop facility on MARIA reactor

    International Nuclear Information System (INIS)

    Konechko, A.; Shumskij, A.M.; Mikul'ahin, V.E.

    1982-01-01

    A 600 kW test loop facility for investigatin.o safety problems is realized on MARIA reactor in Poland together with USSR organizations. Safety reports have been developed in two steps at the designstage. The 1st report being essentially a preliminary safety analysis was developed within the scope of the feasibility study. At the engineering design stage the preliminary test loop facility safety report had been prepared considering measures excluding the possibility of the MARIA reactor damage. The test loop facility safety report is fulfilled for normal, transient and emergency operation regimes. Separate safety basing for each group of experiments will be prepared. The report presents the test loop facility safety criteria coordinated by the nuclear safety comission. They contains the preliminary reports on the test loop facility safety. At the final stage of construction and at thecommitioning stage the start-up safety report will be developed which after required correction and adding up the putting into operation data will turn into operation safety report [ru

  11. Safeguards systems analysis research and development and the practice of safeguards at DOE facilities

    International Nuclear Information System (INIS)

    Zack, N.R.; Thomas, K.E.; Markin, J.T.; Tape, J.W.

    1991-01-01

    Los Alamos Safeguards Systems Group personnel interact with Department of Energy (DOE) nuclear materials processing facilities in a number of ways. Among them are training courses, formal technical assistance such as developing information management or data analysis software, and informal ad hoc assistance especially in reviewing and commenting on existing facility safeguards technology and procedures. These activities are supported by the DOE Office of Safeguards and Security, DOE Operations Offices, and contractor organizations. Because of the relationships with the Operations Office and facility personnel, the Safeguards Systems Group research and development (R and D) staff have developed an understanding of the needs of the entire complex. Improved safeguards are needed in areas such as materials control activities, accountability procedures and techniques, systems analysis and evaluation methods, and material handling procedures. This paper surveys the generic needs for efficient and cost effective enhancements in safeguards technologies and procedures at DOE facilities, identifies areas where existing safeguards R and D products are being applied or could be applied, and sets a direction for future systems analysis R and D to address practical facility safeguards needs

  12. Power systems development facility. Quarterly technical progress report, July 1, 1994--September 30, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: (1) Carbonizer/Pressurized Circulating Fluidized Bed Gas Source. (2) Hot Gas Cleanup Units to mate to all gas streams. (3) Combustion Gas Turbine. (4) Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF).

  13. 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

  14. 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

  15. Development and use of a master health facility list: Haiti's experience during the 2010 earthquake response.

    Science.gov (United States)

    Rose-Wood, Alyson; Heard, Nathan; Thermidor, Roody; Chan, Jessica; Joseph, Fanor; Lerebours, Gerald; Zugaldia, Antonio; Konkel, Kimberly; Edwards, Michael; Lang, Bill; Torres, Carmen-Rosa

    2014-08-01

    Master health facility lists (MHFLs) are gaining attention as a standards-based means to uniquely identify health facilities and to link facility-level data. The ability to reliably communicate information about specific health facilities can support an array of health system functions, such as routine reporting and emergency response operations. MHFLs support the alignment of donor-supported health information systems with county-owned systems. Recent World Health Organization draft guidance promotes the utility of MHFLs and outlines a process for list development and governance. Although the potential benefits of MHFLs are numerous and may seem obvious, there are few documented cases of MHFL construction and use. The international response to the 2010 Haiti earthquake provides an example of how governments, nongovernmental organizations, and others can collaborate within a framework of standards to build a more complete and accurate list of health facilities. Prior to the earthquake, the Haitian Ministry of Health (Ministère de la Santé Publique et de la Population [MSPP]) maintained a list of public-sector health facilities but lacked information on privately managed facilities. Following the earthquake, the MSPP worked with a multinational group to expand the completeness and accuracy of the list of health facilities, including information on post-quake operational status. This list later proved useful in the response to the cholera epidemic and is now incorporated into the MSPP's routine health information system. Haiti's experience demonstrates the utility of MHFL formation and use in crisis as well as in the routine function of the health information system.

  16. Power systems development facility. Quarterly technical progress report, July 1--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This quarterly technical progress report summarizes work completed during the Second Quarter of the Second Budget Period, July 1 through September 30, 1993, under the Department of Energy (DOE) Cooperative Agreement No. DE-FC21-90MC25140 entitled ``Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.`` The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scaleup of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the existing Transport Reactor gas source and Hot Gas Cleanup Units: Carbonizer/Pressurized Circulating Fluidized Bed Gas Source. Hot Gas Cleanup Units to mate to all gas streams; Combustion Gas Turbine; and Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the facility.

  17. Research and development of power reactor technology supporting work, 3; Development of utility facility operation management technique

    Energy Technology Data Exchange (ETDEWEB)

    1990-03-01

    Demands on utility facilities for nuclear technology development are increasingly sophisticated and diversified. It is important to meet requirements of securing the reliability of utility supply and ensuring the safety of facility operation and maintenance by means of technical supporting, data supply and quick contingency responses. A New computer system to make practicable man-machine interface, real-time data acquisition and operation data centralization has been developed based on the knowledge. Obtained from data base information and operation experience for the purpose of operation efficiency and labor saving. (author).

  18. Investigation of development and management of treatment planning systems for BNCT at foreign facilities

    International Nuclear Information System (INIS)

    2001-03-01

    A new computational dosimetry system for BNCT: JCDS is developed by JAERI in order to carry out BNCT with epithermal neutron beam at present. The development and management situation of computational dosimetry system, which are developed and are used in BNCT facilities in foreign countries, were investigated in order to accurately grasp functions necessary for preparation of the treatment planning and its future subjects. In present state, 'SERA', which are developed by Idaho National Engineering and Environmental Laboratory (INEEL), is used in many BNCT facilities. Followings are necessary for development and management of the treatment planning system. (1) Reliability confirmation of system performance by verification as comparison examination of calculated value with actual experimental measured value. (2) Confirmation systems such as periodic maintenance for retention of the system quality. (3) The improvement system, which always considered relative merits and demerits with other computational dosimetry system. (4) The development of integrated system with patient setting. (author)

  19. Study on application of radiation and radioisotopes -Development of the radioisotope production facilities for the HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ji Bok; Woo, Jong Sub; Kang, Byung Woi; Baek, Sam Tae; Jeong, Un Soo; Park, Yong Chul; Jeon, Young Keon; Chang, Chun Ik; Lee, Bong Jae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-08-01

    Development and construction of the lead hot cell for radioisotope production and related facility. 1. Fabrication and installation of the lead H/C system. 2. Development and installation of the hydraulic transfer system. 3. Development of the radiation monitoring system. 4. Fabrication and installation of the fire extinguishing system in the H/C. 5. Fabrication and installation of the fume hood. 4 tabs.,10 figs. (Author).

  20. Thermal-hydraulic tests with out-of-pile test facility for BOCA development

    International Nuclear Information System (INIS)

    Kitagishi, Shigeru; Aoyama, Masashi; Tobita, Masahiro; Inaba, Yoshitomo; Yamaura, Takayuki

    2012-01-01

    The fuel transient test facility was prepared for power ramping tests of light-water-reactor (LWR) fuels in the Japan Materials Testing Reactor (JMTR) under a contract project with the Nuclear Industrial Safety Agent (NISA) of the Ministry of Economy, Trade and Industry (METI). It is necessary to develop high accuracy analysis procedure for power ramping tests after restart of the JMTR. The out-of-pile test facility to simulate thermal-hydraulic conditions of the fuel transient test facility was therefore developed. Applicability of the analysis code ACE-3D was examined for thermal-hydraulic analysis of power ramping tests for 10x10 BWR fuels by the fuel transient test facility. As the results, the calculated temperature was 304°C in comparison with measured value of 304.9-317.4°C in the condition of 600 W/cm. There is a bright prospect of high accuracy power ramping tests by the fuel transient test facility in JMTR. (author)

  1. Development of cancer therapy facility of HANARO and medical research in BNCT; development of the technique for boron concentration analysis

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hee Dong; Byun, Soo Hyun; Sun, Gwang Min; Kim, Suk Kwon; Kim, In Jung; Park, Chang Su [Seoul National University, Seoul (Korea)

    2002-03-01

    Objective and Necessity of the Project- Development of a boron concentration analysis facility used for BNCT. - Development of the technique for boron concentration analysis. Contents and Scopes of the Project - Construction of the boron concentration analysis facility based on PGAA. Estimation of the neutron beam characteristics. -Establishment of the technique for the boron concentration analysis. - Estimation of the reliability for the boron analysis. Results of the Project -Installation of the boron concentration analysis facility at Hanaro. - Neutron beam characteristics are the sample position (neutron flux : 7.9 x 10{sup 7} n/cm{sup 2}s, Cd-ratio : 266) Technique for the boron concentration analysis. - Boron detection sensitivity and limit (detection sensitivity : 2, 131 cps/mg-B, detection limit : 67 ng for 10,000 sec). 63 refs., 37 figs., 13 tabs. (Author)

  2. No Pending National Elections, Who Cares? What Newspaper Publications Reveal about Local Efforts Towards Millennium Development Goal 3

    Science.gov (United States)

    Arku, Frank S.; Arku, Cynthia

    2013-01-01

    The Millennium Development Goals (MDGs) has become a catch phrase in development discourse. This study is an assessment of the MDG 3: to promote gender equality at all levels of education in Ghana. The Daily Graphic (a newspaper in Ghana) which is Ghana's prominent newspaper was reviewed from 2000 to 2011 to determine the frequency of articles…

  3. Development of the irradiation facilities for silicon neutron doping in France

    International Nuclear Information System (INIS)

    Breant, P.; Cherruau, F.; Genthon, J.P.

    1980-08-01

    Irradiation facilities for silicon irradiations in France may be classified in two categories: on the one hand the devices directly implemented in the light water of α swimming-pool reactor and on the other hand the devices implemented in a neutronic medium -heavy water here- providing a high value of the thermal to fast neutron flux ratio. The tools used in France for silicon neutron doping are recapitulated according to this classification in tables, with their main characteristics; in addition it is specified that all existing facilities are instrumented with ingot rotation, flux monitoring, automatic time integration and are associated with handling, storage, cleaning, decontamination and activity control equipment. Finally, concerning the irradiation capacities given in these tables, it is pointed out that they are realistic and present capacities, for presently running devices and according to the way they are used on an average; that is to say that they take into account the real average dimensions of the ingot supplied and not the maximum possible loading with the maximum diameters. Further extensions of capacity are possible if need be by the installation of supplementary standard irradiation modules in the pools. Particular attention will given to the new developments: -new irradiaton facilities with a high Oth/Or ratio being developed in the new research reactor ORPHEE: - developments in the OSIRIS H 2 O reactor. In particular and in connection with the facilities developped in OSIRIS, neutronic problems typical and swimming-pool reactors will be contemplated and the adopted solutions given

  4. Developing a user-perception assessment tool for health facilities in South Africa

    CSIR Research Space (South Africa)

    Saidi, M

    2007-06-01

    Full Text Available . The broader tool is envisaged to assess the performance of health facilities in areas of functionality, impact, and building durability and quality. The process will involve developing and testing the tool at a pilot hospital in the country...

  5. Development of Probabilistic Design Basis Earthquake (DBE) Parameters for Moderate and High Hazard Facilities at INEEL

    International Nuclear Information System (INIS)

    Payne, S. M.; Gorman, V. W.; Jensen, S. A.; Nitzel, M. E.; Russell, M. J.; Smith, R. P.

    2000-01-01

    Design Basis Earthquake (DBE) horizontal and vertical response spectra are developed for moderate and high hazard facilities or Performance Categories (PC) 3 and 4, respectively, at the Idaho National Engineering and Environmental Laboratory (INEEL). The probabilistic DBE response spectra will replace the deterministic DBE response spectra currently in the U.S. Department of Energy Idaho Operations Office (DOE-ID) Architectural Engineering Standards that govern seismic design criteria for several facility areas at the INEEL. Probabilistic DBE response spectra are recommended to DOE Naval Reactors for use at the Naval Reactor Facility at INEEL. The site-specific Uniform Hazard Spectra (UHS) developed by URS Greiner Woodward Clyde Federal Services are used as the basis for developing the DBE response spectra. In 1999, the UHS for all INEEL facility areas were recomputed using more appropriate attenuation relationships for the Basin and Range province. The revised UHS have lower ground motions than those produced in the 1996 INEEL site-wide probabilistic ground motion study. The DBE response spectra were developed by incorporating smoothed broadened regions of the peak accelerations, velocities, and displacements defined by the site-specific UHS. Portions of the DBE response spectra were adjusted to ensure conservatism for the structural design process

  6. DEVELOPMENT OF THE U.S. EPA'S METAL FINISHING FACILITY POLLUTION PREVENTION TOOL

    Science.gov (United States)

    Metal finishing processes are a type of chemical processes and can be modeled using Computer Aided Process Engineering (CAPE). Currently, the U.S. EPA is developing the Metal Finishing Facility Pollution Prevention Tool (MFFP2T), a pollution prevention software tool for the meta...

  7. Guidelines for the development of natural phenomena hazards design criteria for surface facilities

    International Nuclear Information System (INIS)

    Nelson, T.A.; Hossain, Q.A.; Murray, R.C.

    1992-01-01

    This paper discusses the rationale behind the guidelines, criteria, and methodologies that are currently used for natural phenomena hazard design and evaluation of DOE nuclear and non-nuclear facilities. The bases for the performance goals and usage categories specified in UCRL-15910 are examined, and the sources of intentional conservatism in the analyses, design, and evaluation methods and criteria are identified. Outlines of recent developments/changes in DOE Orders related to Natural Phenomena hazard mitigation are also presented. Finally, the authors recommend the use of DOE methodologies as embodied in UCRL-15910 for design and evaluation of surface facilities of the high level nuclear waste repository site

  8. Study on the development of safeguards information treatment system at the facility level

    Energy Technology Data Exchange (ETDEWEB)

    Lee, B. D.; Song, D. Y.; So, D. S.; Kwak, E. H. [KAERI, Taejon (Korea, Republic of)

    2000-05-01

    Safeguards Information Treatment System(SITS) at the facility level is required to implement efficiently the obligations under the Korea-IAEA Safeguards Agreement, bilateral agreements with other countries and domestic law. In this paper, the requirements and major functions of SITS were considered, and the error checking methods and the relationships of safeguards information were reviewed. SITS will be developed to cover the different accounting procedures and methods applied at the various facilities under IAEA safeguards. Also, the resolved result of the Y2K problem in the existing nuclear material accounting program was described.

  9. Technology developments for ACIGA high power test facility for advanced interferometry

    Energy Technology Data Exchange (ETDEWEB)

    Barriga, P [School of Physics, University of Western Australia, Perth, WA 6009 (Australia); Barton, M [California Institute of Technology, LIGO Project, Pasadena, CA 91125 (United States); Blair, D G [School of Physics, University of Western Australia, Perth, WA 6009 (Australia)] [and others

    2005-05-21

    The High Optical Power Test Facility for Advanced Interferometry has been built by the Australian Consortium for Interferometric Gravitational Astronomy north of Perth in Western Australia. An 80 m suspended cavity has been prepared in collaboration with LIGO, where a set of experiments to test suspension control and thermal compensation will soon take place. Future experiments will investigate radiation pressure instabilities and optical spring effects in a high power optical cavity with {approx}200 kW circulating power. The facility combines research and development undertaken by all consortium members, whose latest results are presented.

  10. Technology developments for ACIGA high power test facility for advanced interferometry

    International Nuclear Information System (INIS)

    Barriga, P; Barton, M; Blair, D G

    2005-01-01

    The High Optical Power Test Facility for Advanced Interferometry has been built by the Australian Consortium for Interferometric Gravitational Astronomy north of Perth in Western Australia. An 80 m suspended cavity has been prepared in collaboration with LIGO, where a set of experiments to test suspension control and thermal compensation will soon take place. Future experiments will investigate radiation pressure instabilities and optical spring effects in a high power optical cavity with ∼200 kW circulating power. The facility combines research and development undertaken by all consortium members, whose latest results are presented

  11. Development of the Ukrainian power sector taking into account the environmental impact of power facilities

    International Nuclear Information System (INIS)

    Dyakova, E.; Krymskaya, L.

    1997-01-01

    This paper concentrates on the following problems: Evaluation of total environmental impacts from all kinds of power plants on the whole territory of Ukraine; evaluation of environmental impacts in selected regions due to uneven power facilities distribution. Analysis of the environmental situation in Ukraine was conducted using the IMPACTS module of the ENPEP package with account to the Ukrainian energy requirements in perspective. Some recommendations concerning the development of power facilities and reduction of air emissions are also given. (author). 7 figs, 5 tabs

  12. Development of the Ukrainian power sector taking into account the environmental impact of power facilities

    Energy Technology Data Exchange (ETDEWEB)

    Dyakova, E; Krymskaya, L [Institute for Nuclear Research, National Academy of Science, Kiev (Ukraine)

    1997-09-01

    This paper concentrates on the following problems: Evaluation of total environmental impacts from all kinds of power plants on the whole territory of Ukraine; evaluation of environmental impacts in selected regions due to uneven power facilities distribution. Analysis of the environmental situation in Ukraine was conducted using the IMPACTS module of the ENPEP package with account to the Ukrainian energy requirements in perspective. Some recommendations concerning the development of power facilities and reduction of air emissions are also given. (author). 7 figs, 5 tabs.

  13. PRELIMINARY STUDY TO PRIMARY EDUCATION FACILITIES (A Comparison Study between Indonesia and Developed Countries

    Directory of Open Access Journals (Sweden)

    Lucy Yosita

    2006-01-01

    Full Text Available This writing is a preliminary study to condition of primary education facilities in Indonesia, and then comparing these with theories as well as various relevant cases aimed to know the problem more obviously. Basically, there is difference between primary education facilities in Indonesia with those in developed countries. Meanwhile on the other hand, the condition as well as the completion of education facility is actually as the main factor contributes to address the purpose of learning process. If building design, interior and also site plan were dynamic in form, space, colour and tools, those would be probably more stimulate activity and influence into the growth of students. However, lastly, it is still required further analysis, as an example analysis to student's behaviour in spaces of learning environment, more detail and within enough time, not only at indoor but also at outdoor.

  14. Design and development of semi-automatic radiation test and calibration facility

    International Nuclear Information System (INIS)

    Yadav, Ashok Kumar; Chouhan, V.K.; Narayan, Pradeep

    2008-01-01

    Semi-automatic gamma radiation test and calibration facility have been designed, developed and commissioned at Defence Laboratory Jodhpur (DLJ). The facility comprises of medium and high dose rate range setup using 30 Ci Cobalt-60 source, in a portable remotely operated Techops camera and a 15000 Ci 60 Co source in a Tele-therapy machine. The radiation instruments can be positioned at any desired position using a computer controlled positioner having three translational and one rotational motion. User friendly software helps in positioning the Device Under Test (DUT) at any desired dose rate or distance and acquire the data automatically. The servo and stepper motor controlled positioner helps in achieving the required precision and accuracy for the radiation calibration of the instruments. This paper describes the semi-automatic radiation test and calibration facility commissioned at DLJ. (author)

  15. Cold neutron PGAA facility developments at university research reactors in the USA

    International Nuclear Information System (INIS)

    Uenlue, K.; Rios-Martinez, C.

    2005-01-01

    The PGAA applications can be enhanced by using subthermal neutrons, cold neutrons at university research reactors. Only two cold neutron beam facilities were developed at the U.S. university research reactors, namely at Cornell University and the University of Texas at Austin. Both facilities used mesitylene moderator. The mesitylene moderator in the Cornell Cold Neutron Beam Facility (CNBF) was cooled by a helium cryorefrigerator via copper cold fingers to maintain the moderator below 30 K at full power reactor operation. Texas Cold Neutron Source (TCNS) also uses mesitylene moderator that is cooled by a cryorefrigerator via a neon thermosiphon. The operation of the TCNS is based on a helium cryorefrigerator, which liquefies neon gas in a 3-m long thermosiphon. The thermosiphon cools and maintains mesitylene moderator at about 30 K in a chamber. Neutrons streaming through the mesitylene chamber are moderated and thus reduce their energy to produce a cold neutron distribution. (author)

  16. Development of a low-energy radioactive ion beam facility for the MARA separator

    Energy Technology Data Exchange (ETDEWEB)

    Papadakis, Philippos, E-mail: philippos.papadakis@jyu.fi; Moore, Iain; Pohjalainen, Ilkka; Sarén, Jan; Uusitalo, Juha [University of Jyväskylä, Department of Physics (Finland)

    2016-12-15

    A low-energy radioactive ion beam facility for the production and study of nuclei produced close to the proton drip line is under development at the Accelerator Laboratory of the University of Jyväskylä, Finland. The facility will take advantage of the mass selectivity of the recently commissioned MARA vacuum-mode mass separator. The ions selected by MARA will be stopped and thermalised in a small-volume gas cell prior to extraction and further mass separation. The gas cell design allows for resonance laser ionisation/spectroscopy both in-gas-cell and in-gas-jet. The facility will include experimental setups allowing ion counting, mass measurement and decay spectroscopy.

  17. Development of moderated neutron calibration fields simulating workplaces of MOX fuel facilities

    International Nuclear Information System (INIS)

    Tsujimura, Norio; Yoshida, Tadayoshi; Takada, Chie

    2005-01-01

    It is important for the MOX fuel facilities to control neutrons produced by the spontaneous fission of plutonium isotopes and those from (α,n) reactions between 18 O and α particles emitted by 238 Pu. Neutron dose meters should be calibrated for measuring these neutrons. We have developed moderated-neutron calibration fields employing a 252 Cf neutron source and moderators mainly for the characteristics evaluation and the calibration of neutron detectors used in MOX fuel facilities. Neutron energy spectrum can be adjusted by changing the position of the 252 Cf neutron source and combining different moderators to simulate the neutron field of the MOX fuel facility. This performance is realized owing to using an existing neutron irradiation room. (K. Yoshida)

  18. Development of operation control expert system for off-site facilities

    Energy Technology Data Exchange (ETDEWEB)

    Takeuchi, Masaaki

    1988-09-01

    Concerning off-site facilities of oil refinary, changes of facilities and equipment are frequently made in order to cope flexibly with the market trends and changes of the social environment. In addition, it is desirable to introduce computerization into control and manipulation of off-site facilities for its fast, safe and sure operation. In order to achieve the above, against the existing exclusively control-oriented system, it is necessary to add the processing and generating functions to combinations between valves to be shut and piping as well as equipment to be used along the whole extent of the oil flow in the system and to add the function which makes verification of the above functions easy through a dialogue between users and the system. In order to realize the above, Cosmo Oil and Yokokawa Denki developed jointly an operation control expert system for off-site facilities and the system started its actual operation from October 1986. This article is an outline of the system. The result of its actual operation for one and a half years since its inception showed that the system was operated only by the staff responsible for the operation of the facilities, the workload was reduced to 1/3-1/4 of the workload before the adoption of the system and absolutely no omission of work nor mistake was experienced. (2 figs)

  19. Impact assessment of the forest fires on Oarai Research and Development Center Waste Treatment Facility

    International Nuclear Information System (INIS)

    Shimomura, Yusuke; Kitamura, Ryoichi; Hanari, Akira; Sato, Isamu

    2016-03-01

    In response to new standards for regulating waste treatment facility ('new regulatory standards'; December 18, 2013 enforcement), it was carried out impact assessment of forest fires on the Waste Treatment Facility existed in Oarai Research and Development Center of Japan Atomic Energy Agency. At first, a fire spread scenario of forest fires was assumed. The intensity of forest fires was evaluated from field surveys, forest fire evaluation models and so on. As models of forest fire intensity evaluation, Rothermel Model and Canadian Forest Fire Behavior Prediction (FBP) System were used. Impact assessment of radiant heat to the facility was carried out, and temperature change of outer walls for the assumed forest fires was estimated. The outer wall temperature of facility was estimated around 160degC at the maximum, it was revealed that it doesn't reach allowable temperature limit. Consequently, it doesn't influence the strength of concrete. In addition, a probability of fire breach was estimated to be about 20%. This report illustrates an example of evaluation of forest fires for the new regulatory standards through impact assessment of the forest fires on the Waste Treatment Facility. (author)

  20. Development of turbopump cavitation performance test facility and the test of inducer performance

    International Nuclear Information System (INIS)

    Sohn, Dong Kee; Kim, Chun Tak; Yoon, Min Soo; Cha, Bong Jun; Kim, Jin Han; Yang, Soo Seok

    2001-01-01

    A performance test facility for turbopump inducer cavitation was developed and the inducer cavitation performance tests were performed. Major components of the performance test facility are driving unit, test section, piping, water tank, and data acquisition and control system. The maximum of testing capability of this facility are as follows: flow rate - 30kg/s; pressure - 13 bar, rotational speed - 10,000rpm. This cavitation test facility is characterized by the booster pump installed at the outlet of the pump that extends the flow rate range, and by the pressure control system that makes the line pressure down to vapor pressure. The vacuum pump is used for removing the dissolved air in the water as well as the line pressure. Performance tests were carried out and preliminary data of test model inducer were obtained. The cavitation performance test and cavitation bubble flow visualization were also made. This facility is originally designed for turbopump inducer performance test and cavitation test. However it can be applied to the pump impeller performance test in the future with little modification

  1. Development of partitioning method : cold experiment with partitioning test facility in NUCEF (I)

    International Nuclear Information System (INIS)

    Yamaguchi, Isoo; Morita, Yasuji; Kondo, Yasuo

    1996-03-01

    A test facility in which about 1.85 x 10 14 Bq of high-level liquid waste can be treated has been completed in 1994 at Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) for research and development of Partitioning Method. The outline of the partitioning test facility and support equipments for it which were design terms, constructions, arrangements, functions and inspections were given in JAERI-Tech 94-030. The present report describes the results of the water transfer test and partitioning tests, which are methods of precipitation by denitration, oxalate precipitation, solvent extraction, and adsorption with inorganic ion exchanger, using nitric acid to master operation method of the test facility. As often as issues related to equipments occurred during the tests, they were improved. As to issues related to processes such as being stopped up of columns, their measures of solution were found by testing in laboratories. They were reflected in operation of the Partitioning Test Facility. Their particulars and improving points were described in this report. (author)

  2. Design and development of a 3 axis magnetic field measurement facility using Hall probe

    International Nuclear Information System (INIS)

    Sahoo, Shantonu; Bhattacharyya, Sumantra; Chaddha, Niraj; Mishra, Santosh Kr.; Nandy, Partha P.; Nandi, Chinmay; Bhole, Rajendra B.; Pal, Sarbajit; Pal, Gautam

    2015-01-01

    A 3-axis drive system has been designed and developed in-house to measure the magnetic field with positional accuracy of 0.2 mm in a volume of 1.5 x 1.3 x 0.15 cubic-meter. Hall sensor based magnetometer is used to measure the magnetic field with a precision of 100 μT(1 Gauss). The drive of each axis has linear guide and zero backlash ball screw combination to achieve accurate movement of the hall probe with positional repeatability of +/- 0.2 micron per 50 mm. The hardware and software, also developed in-house, facilitate precise probe positioning and sophisticated visualization of field map. Dedicated microcontroller based motor controllers and encoder read-out cards for each axis have been developed. The facility is integrated with a rich touch-screen based intelligent GUI for automated scanning and data acquisition. This facility can be used for accurate magnetic field mapping of big dipole magnets, solenoids, etc. The facility has been tested successfully to characterize a Dipole Magnet designed for Radioactive Ion Beam (RIB) facility. (author)

  3. The complex nature of mixed farming systems requires multidimensional actions supported by integrative research and development efforts

    DEFF Research Database (Denmark)

    González-García, E; Gourdine, J L; Alexandre, G

    2012-01-01

    the requirement for a change in research strategies and initiatives through the development of a complex but necessary multi-/inter-/trans-disciplinary teamwork spirit. We stress as essential the collaboration and active participation of local and regional actors, stakeholders and end-users in the identification...

  4. Sustainable Development Policies as Indicators and Pre-Conditions for Sustainability Efforts at Universities: Fact or Fiction?

    Science.gov (United States)

    Leal Filho, Walter; Brandli, Luciana Londero; Becker, Deisi; Skanavis, Constantina; Kounani, Aristea; Sardi, Chrysoula; Papaioannidou, Dimitra; Paço, Arminda; Azeiteiro, Ulisses; de Sousa, Luiza Olim; Raath, Schalk; Pretorius, Rudi Wessel; Shiel, Christine; Vargas, Valeria; Trencher, Gregory; Marans, Robert W.

    2018-01-01

    Purpose: There is a widely held belief that sustainable development (SD) policies are essential for universities to successfully engage in matters related to sustainability, and are an indicator of the extent to which they are active in this field. This paper aims to examine the evidence which currently exists to support this assumption. It…

  5. Professional Development for Early Childhood Educators: Efforts to Improve Math and Science Learning Opportunities in Early Childhood Classrooms

    Science.gov (United States)

    Piasta, Shayne B.; Logan, Jessica A. R.; Pelatti, Christina Yeager; Capps, Janet L.; Petrill, Stephen A.

    2015-01-01

    Because recent initiatives highlight the need to better support preschool-aged children's math and science learning, the present study investigated the impact of professional development in these domains for early childhood educators. Sixty-five educators were randomly assigned to experience 10.5 days (64 hr) of training on math and science or on…

  6. The complex nature of mixed farming systems requires multidimensional actions supported by integrative research and development efforts.

    Science.gov (United States)

    González-García, E; Gourdine, J L; Alexandre, G; Archimède, H; Vaarst, M

    2012-05-01

    Mixed farming systems (MFS) have demonstrated some success by focusing on the use of integrative and holistic mechanisms, and rationally building on and using the natural and local resource base without exhausting it, while enhancing biodiversity, optimizing complementarities between crops and animal systems and finally increasing opportunities in rural livelihoods. Focusing our analysis and discussion on field experiences and empirical knowledge in the Caribbean islands, this paper discusses the opportunities for a change needed in current MFS research-development philosophy. The importance of shifting from fragile/specialized production systems to MFS under current global conditions is argued with an emphasis on the case of Small Islands Developing States (SIDS) and the Caribbean. Particular vulnerable characteristics as well as the potential and constraints of SIDS and their agricultural sectors are described, while revealing the opportunities for the 'richness' of the natural and local resources to support authentic and less dependent production system strategies. Examples are provided of the use of natural grasses, legumes, crop residues and agro-industrial by-products. We analyse the requirement for a change in research strategies and initiatives through the development of a complex but necessary multi-/inter-/trans-disciplinary teamwork spirit. We stress as essential the collaboration and active participation of local and regional actors, stakeholders and end-users in the identification of research priorities, as well as the generation, exchange and dissemination of knowledge and technology innovations, while strengthening the leadership roles in the conduct of integrative and participative research and development projects.

  7. Regional Cooperation Efforts in the Mekong River Basin: Mitigating river-related security threats and promoting regional development

    Directory of Open Access Journals (Sweden)

    Susanne Schmeier

    2009-01-01

    Full Text Available The development of international rivers is often perceived as leading to conflicts or even water wars. However, as the development of the Mekong River shows, cooperation has not only prevailed in the last decades, but River Basin Organizations (RBOs, established to mitigate river-related conflicts and/or develop the river basin, have also contributed to the emergence of more general cooperation structures, mainly by creating spill-over effects in other issue-areas, bringing cooperation to policy fields beyond the river itself. This article assesses the contribution of the Mekong River Commission (MRC and the Greater Mekong Sub-Region (GMS to the sustainable development of the Mekong Region as well as to the promotion of regional cooperation in mainland South-East Asia in general. --- Die Entwicklung grenzüberschreitender Flüsse wird oft mit Konflikten oder gar Kriegen um Wasser assoziiert. Wie jedoch die Entwicklung im Mekong-Becken zeigt, waren die vergangenen Jahrzehnte nicht nur von Kooperation gezeichnet, sondern Flussbeckenorganisationen konnten außerdem dazu beitragen, weitreichendere Kooperationsstrukturen zu entwickeln, die sich auf andere Politikfelder ausdehnen. Dieser Artikel beschäftigt sich mit dem Beitrag der Mekong River Commission (MRC und der Greater Mekong Sub-Region (GMS zur nachhaltigen Entwicklung in der Mekong Region sowie zur Förderung allgemeiner regionaler Kooperation im Festländischen Südostasien.

  8. Lessons learned from designing and commissioning a versatile data acquisiting system for an accelerator development facility

    International Nuclear Information System (INIS)

    Langlais, C.E.; Watkins, L.M.; Caissie, L.P.; Wachsmann, W.J.; Andison, C.E.

    1977-01-01

    Achieving reliable operation of digital equipment under extreme noise conditions presents special challenges to system designers. Experience with the design and operation of a data acquisition and control system for an accelerator development facility at the Chalk River Nuclear Laboratories is reviewed. It is concluded that, by adhering to a few rules in developing both the hardware and the software, satisfactory performance can be guaranteed. Methods of producing a reliable design are presented

  9. Use of Pilot Plants for Developing Used Nuclear Fuel Recycling Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, Chris; Arm, Stuart [EnergySolutions LLC (United States); Banfield, Zara; Jeapes, Andrew; Taylor, Richard [National Nuclear Laboratory (United Kingdom)

    2009-06-15

    EnergySolutions and its teaming partners are working with the US Department of Energy (DOE) to develop processes, equipment and facilities for recycling used nuclear fuel (UNF). Recycling significantly reduces the volume of wastes that ultimately will be consigned to the National Geologic Repository, enables the re-use in new fuel of the valuable uranium and plutonium in the UNF, and allows the long-lived minor actinides to be treated separately so they do not become long term heat emitters in the Repository. A major requirement of any new UNF recycling facility is that pure plutonium is not separated anywhere in the process, so as to reduce the nuclear proliferation attractiveness of the facility. EnergySolutions and its team partner the UK National Nuclear Laboratory (NNL) have developed the NUEX process to achieve this and to handle appropriately the treatment of other species such as krypton, tritium, neptunium and technetium. NUEX is based on existing successful commercial UNF recycling processes deployed in the UK, France and imminently in Japan, but with a range of modifications to the flowsheet to keep some uranium with the plutonium at all times and to minimize aerial and liquid radioactive discharges. NNL's long-term experience in developing the recycling and associated facilities at the Sellafield site in the UK, and its current duties to support technically the operation of the Thermal Oxide Reprocessing Plant (THORP) at Sellafield provides essential input to the design of the US NUEX-based facility. Development work for THORP and other first-of-kind nuclear plants employed miniature scale fully radioactive through large scale inactive pilot plants. The sequence of development work that we have found most successful is to (i) perform initial process development at small (typically 1/5000) scale in gloveboxes using trace active materials, (ii) demonstrate the processes at the same small scale with actual irradiated fuel in hot cells and (iii

  10. Efforts in Bologna on quasiparticle level density systematics and on comparison and development of different approaches to preequilibrium reaction mechanism

    International Nuclear Information System (INIS)

    Herman, M.; Reffo, G.; Weidenmueller, H.A.; Lenske, H.; Wolter, H.H.; Giardina, G.; Italiano, A.; Rosetti, M.

    1991-01-01

    We present a summary of activities carried out at ENEA in Bologna on the development of the preequilibrium emission models. We start with the first application of the Multistep Compound Model in the Heidelberg formulation, which is followed by the Multistep Direct calculations. Next, the comparison between the exciton and Multistep Compound model by Feshbach, Kerman, and Koonin is presented. Finally we discuss energy and isotope dependence of the average single particle level spacing. (author). Refs, 9 figs

  11. Application of demography to energy facility development projects. Working Paper No. 39

    International Nuclear Information System (INIS)

    Krannich, R.S.; Stanfield, G.G.

    1977-01-01

    The emergence of concern regarding socioeconomic consequences of large-scale development projects has resulted in a growing literature directed as estimating the types and levels of various impact dimensions which can be expected to result in human communities experiencing such development. Among these dimensions, a focus on population change has been prevalent. Accurate demographic predictions may be viewed as critical for the adequate comprehension of and preparation for impacts deriving from projects such as energy facility developments. Unfortunately, the state of the art in projecting demographic consequences of energy projects has been generally inadequate. Several of the more influential prior methods for estimating local demographic effects of developing energy facilities are critiqued, although their specific prediction figures are not summarized. The studies reviewed were found to be of dubious practical utility, probably due in part to the failure of basic demography to provide a base of support for applied demographic research. This report sets forth recommendations for the development of a theoretical perspective which would more adequately serve the needs of practitioners attempting to predict local demographic effects of energy facility development

  12. Beyond the Initiatives: Developing instructional leadership in school principals as a system-wide effort to improve the quality of classroom instruction.

    OpenAIRE

    Aguilera, Sondra Denise

    2016-01-01

    This design research effort implemented a series of intervention activities designed to support a small group of elementary school principals improve their instructional leadership practices. The purpose of this research was to improve the skills of principals to lead instructional improvements identified through classroom observations, work with their school-level Instructional Leadership Team (ILT) to create teacher professional development that addresses the instructional improvement, and ...

  13. Swedish nuclear waste efforts

    International Nuclear Information System (INIS)

    Rydberg, J.

    1981-09-01

    After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981

  14. Waste Facilities

    Data.gov (United States)

    Vermont Center for Geographic Information — This dataset was developed from the Vermont DEC's list of certified solid waste facilities. It includes facility name, contact information, and the materials...

  15. Development of a mixed waste management facility at the Nevada Test Site

    International Nuclear Information System (INIS)

    Dodge, R.L.; Brich, R.F.

    1988-01-01

    The U.S. Department of Energy (DOE) produces radioactive low-level wastes (LLW) which contain hazardous components as identified by 40 Code of Federal Regulations (CFR) 261. Management of those mixed wastes (MW) requires compliance with U.S.Environmental Protection Agency (EPA) regulations for hazardous wastes and DOE regulations for LLW. In 1988, DOE's Nevada Operations Office (NV) began disposing of MW at the Nevada Test Site (NTS) under interim status as authorized by the state of Nevada. MW disposal is limited to Pit 3 while operating under interim status. This paper discusses how preparations for operation of a separate mixed waste management facility (MWMF) are underway. Those preparations include revising the NTS Part B Permit application, developing a MW certification program, developing and operating a vadose zone monitoring system, preparing an Environmental Assessment (EA), developing protocols for analysis of MW, and facility design and construction

  16. Development and implementation of the waste diversion program at MDS Nordion's Cobalt Operations Facility

    International Nuclear Information System (INIS)

    Wasiak, T.

    2004-01-01

    Historically, the MDS Nordion (MDSN) Cobalt Operations Facility sent solid waste for disposal to Atomic Energy of Canada Ltd.'s Chalk River Laboratories (AECL-CRL). A large portion of this waste was not contaminated. Because this non-contaminated waste originated in the 'active area' of the MDSN facility, it was routinely disposed of as low-level active waste. In 2002, MDSN undertook an initiative to develop and implement a more sophisticated and more economical waste management program. The Waste Diversion Program (WDP) ensures continued environmental and public protection, and reduces the demand on Canada's limited capacity for storage of radioactive material and the associated operating costs. The goal of the WDP is to reduce the volume of waste currently being shipped to AECL-CRL's Waste Management Operation as low-level active waste. The presentation discusses key elements of both the development and the implementation of WDP. It focuses on the following areas: the regulatory environment surrounding the waste disposal issues in Canada and abroad. Methods used by MDSN for determination of radionuclides, which could be present in the facility. Choice of equipment and calculation of individual alarm levels for each identified radionuclide. Key elements of the practical implementation of the program. CNSC Regulatory approval process. The bottom line - dollars and cents. The primary objective of the WDP is to ensure that only waste, which meets regulatory requirements, is diverted from the solid active waste stream. This has been successfully accomplished in MDSN's Cobalt Operations Facility. The objective of the presentation is to share the knowledge and experience obtained in the development process, and thus provide a guideline for other nuclear facilities interested in establishing similar proactive and cost effective programs. (author)

  17. Development and testing of a novel survey to assess Stakeholder-driven Community Diffusion of childhood obesity prevention efforts.

    Science.gov (United States)

    Korn, Ariella R; Hennessy, Erin; Hammond, Ross A; Allender, Steven; Gillman, Matthew W; Kasman, Matt; McGlashan, Jaimie; Millar, Lynne; Owen, Brynle; Pachucki, Mark C; Swinburn, Boyd; Tovar, Alison; Economos, Christina D

    2018-05-31

    Involving groups of community stakeholders (e.g., steering committees) to lead community-wide health interventions appears to support multiple outcomes ranging from policy and systems change to individual biology. While numerous tools are available to measure stakeholder characteristics, many lack detail on reliability and validity, are not context specific, and may not be sensitive enough to capture change over time. This study describes the development and reliability of a novel survey to measure Stakeholder-driven Community Diffusion via assessment of stakeholders' social networks, knowledge, and engagement about childhood obesity prevention. This study was completed in three phases. Phase 1 included conceptualization and online survey development through literature reviews and expert input. Phase 2 included a retrospective study with stakeholders from two completed whole-of-community interventions. Between May-October 2015, 21 stakeholders from the Shape Up Somerville and Romp & Chomp interventions recalled their social networks, knowledge, and engagement pre-post intervention. We also assessed one-week test-retest reliability of knowledge and engagement survey modules among Shape Up Somerville respondents. Phase 3 included survey modifications and a second prospective reliability assessment. Test-retest reliability was assessed in May 2016 among 13 stakeholders involved in ongoing interventions in Victoria, Australia. In Phase 1, we developed a survey with 7, 20 and 50 items for the social networks, knowledge, and engagement survey modules, respectively. In the Phase 2 retrospective study, Shape Up Somerville and Romp & Chomp networks included 99 and 54 individuals. Pre-post Shape Up Somerville and Romp & Chomp mean knowledge scores increased by 3.5 points (95% CI: 0.35-6.72) and (- 0.42-7.42). Engagement scores did not change significantly (Shape Up Somerville: 1.1 points (- 0.55-2.73); Romp & Chomp: 0.7 points (- 0.43-1.73)). Intraclass correlation

  18. IMPROVING THE BIDS EVALUATION CRITERIA AND REDUCING TIME AND EFFORT OF THE ASSESSMENT BY DEVELOPING A SOFTWARE PROGRAM

    Directory of Open Access Journals (Sweden)

    Muaid A. Shhatha

    2018-05-01

    Full Text Available A number of studies have been conducted to specify the most effecting factors on the success of projects. Those studies titled the most influencing factor, which is the bid selection criterion. By this criterion, the most qualified bidder/contractor could be chosen where the contractor has a considerable impact upon projects successes. Moreover, the published studies helped a lot in correcting the improper adopted criterion in selecting the best bid, which is the lowest price bid. Awarding the bid depending on the lowest price bid ended many projects in failure. Therefore, this study aimed to revise the popular mistaken selection criterion, recommend an evaluation criterion, and develop a computer program that works on finding the best bid according to the recommended criterion. The suggested criterion was followed in selecting one of the contractors to construct some projects in Iraq. That projects were felicitously finished; the projects were completed on time and budget.

  19. Animal facilities

    International Nuclear Information System (INIS)

    Fritz, T.E.; Angerman, J.M.; Keenan, W.G.; Linsley, J.G.; Poole, C.M.; Sallese, A.; Simkins, R.C.; Tolle, D.

    1981-01-01

    The animal facilities in the Division are described. They consist of kennels, animal rooms, service areas, and technical areas (examining rooms, operating rooms, pathology labs, x-ray rooms, and 60 Co exposure facilities). The computer support facility is also described. The advent of the Conversational Monitor System at Argonne has launched a new effort to set up conversational computing and graphics software for users. The existing LS-11 data acquisition systems have been further enhanced and expanded. The divisional radiation facilities include a number of gamma, neutron, and x-ray radiation sources with accompanying areas for related equipment. There are five 60 Co irradiation facilities; a research reactor, Janus, is a source for fission-spectrum neutrons; two other neutron sources in the Chicago area are also available to the staff for cell biology studies. The electron microscope facilities are also described

  20. Contaminated Sediment Management in Dam Removals and River Restoration Efforts: Critical Need for Research and Policy Development

    Science.gov (United States)

    Evans, J. E.

    2015-12-01

    Over 1,000 U.S. dams have been removed (1975-2015) for reasons including obsolescence, liability concerns, water quality upgrades, fisheries, or ecosystem enhancements. Contaminated sediment can significantly complicate the approval process, cost, and timeline of a dam removal, or stop it entirely. In a dam removal, reservoir sediment changes from a sink to a source of contaminants. Recently, the Sierra Club sued to stop the removal of a large dam in Ohio because of the potential impact of phosphate releases on toxic algal blooms in Lake Erie. Heavy metals, PCBs, PAHs, pesticides, and petroleum hydrocarbons can be present in reservoir sediments. In a non-dam removal scenario, reservoir management tools range from "no action" to dredging, dewatering and removal, or sediment capping. But it is not clear how these reservoir management techniques apply to dam removals. Case studies show typically >80% of the reservoir sediment is eventually eroded, precluding sediment capping as a containment option. However, the released contaminants are diluted by mixing with "clean" sediment and are transported to different physio-chemical environments which may immobilize or biodegrade the contaminants. Poorly understood options include phased drawdown/reseeding the former reservoir to contain sediments, diking contaminant "hot spots," and addressing contaminant stratigraphy (where historical use created "hot layers" in the reservoir sediment). Research and policy development needs include: (1) assessment methods based on synergistic effects of multiple contaminants being present; (2) ways to translate the pre-removal contaminant concentrations to post-removal health risks downstream; (3) evaluation of management practices for contaminant "hot spots" and "hot layers;" (4) tools to forecast the presence of contaminated sediment using easily accessible information; and (5) ways to limit liability risk for organizations participating in dam removals involving contaminated sediment.

  1. NASA Data Acquisition System Software Development for Rocket Propulsion Test Facilities

    Science.gov (United States)

    Herbert, Phillip W., Sr.; Elliot, Alex C.; Graves, Andrew R.

    2015-01-01

    Current NASA propulsion test facilities include Stennis Space Center in Mississippi, Marshall Space Flight Center in Alabama, Plum Brook Station in Ohio, and White Sands Test Facility in New Mexico. Within and across these centers, a diverse set of data acquisition systems exist with different hardware and software platforms. The NASA Data Acquisition System (NDAS) is a software suite designed to operate and control many critical aspects of rocket engine testing. The software suite combines real-time data visualization, data recording to a variety formats, short-term and long-term acquisition system calibration capabilities, test stand configuration control, and a variety of data post-processing capabilities. Additionally, data stream conversion functions exist to translate test facility data streams to and from downstream systems, including engine customer systems. The primary design goals for NDAS are flexibility, extensibility, and modularity. Providing a common user interface for a variety of hardware platforms helps drive consistency and error reduction during testing. In addition, with an understanding that test facilities have different requirements and setups, the software is designed to be modular. One engine program may require real-time displays and data recording; others may require more complex data stream conversion, measurement filtering, or test stand configuration management. The NDAS suite allows test facilities to choose which components to use based on their specific needs. The NDAS code is primarily written in LabVIEW, a graphical, data-flow driven language. Although LabVIEW is a general-purpose programming language; large-scale software development in the language is relatively rare compared to more commonly used languages. The NDAS software suite also makes extensive use of a new, advanced development framework called the Actor Framework. The Actor Framework provides a level of code reuse and extensibility that has previously been difficult

  2. Experimental facility for development of high-temperature reactor technology: instrumentation needs and challenges

    Directory of Open Access Journals (Sweden)

    Sabharwall Piyush

    2015-01-01

    Full Text Available A high-temperature, multi-fluid, multi-loop test facility is under development at the Idaho National Laboratory for support of thermal hydraulic materials, and system integration research for high-temperature reactors. The experimental facility includes a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The three loops will be thermally coupled through an intermediate heat exchanger (IHX and a secondary heat exchanger (SHX. Research topics to be addressed include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuit heat exchangers (PCHEs at prototypical operating conditions. Each loop will also include an interchangeable high-temperature test section that can be customized to address specific research issues associated with each working fluid. This paper also discusses needs and challenges associated with advanced instrumentation for the multi-loop facility, which could be further applied to advanced high-temperature reactors. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integral System Test (ARTIST facility. A preliminary design configuration of the ARTIST facility will be presented with the required design and operating characteristics of the various components. The initial configuration will include a high-temperature (750 °C, high-pressure (7 MPa helium loop thermally integrated with a molten fluoride salt (KF-ZrF4 flow loop operating at low pressure (0.2 MPa, at a temperature of ∼450 °C. The salt loop will be thermally integrated with the steam/water loop operating at PWR conditions. Experiment design challenges include identifying suitable materials and components that will withstand the required loop operating conditions. The instrumentation needs to be highly accurate (negligible drift in measuring operational data for extended periods of times, as data collected will be

  3. Experimental facility for development of high-temperature reactor technology: instrumentation needs and challenges - 15066

    International Nuclear Information System (INIS)

    Sabharwall, P.; O'Brien, J.E.; Yoon, S.J.; Sun, X.

    2015-01-01

    A high-temperature, multi-fluid, multi-loop test facility is under development at the Idaho National Laboratory for support of thermal hydraulic, materials, and system integration research for high-temperature reactors. The experimental facility includes a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The 3 loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). Research topics to be addressed include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuits heat exchangers (PCHEs) at prototypical operating conditions. Each loop will also include an interchangeable high-temperature test section that can be customized to address specific research issues associated with each working fluid. This paper also discusses needs and challenges associated with advanced instrumentation for the multi-loop facility, which could be further applied to advanced high-temperature reactors. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integrated System Test (ARTIST) facility. A preliminary design configuration of the ARTIST facility will be presented with the required design and operating characteristics of the various components. The initial configuration will include a high-temperature (750 C. degrees), high-pressure (7 MPa) helium loop thermally integrated with a molten fluoride salt (KF-ZrF 4 ) flow loop operating at low pressure (0.2 MPa), at a temperature of ∼ 450 C. degrees. The salt loop will be thermally integrated with the steam/water loop operating at PWR conditions. Experiment design challenges include identifying suitable materials and components that will withstand the required loop operating conditions. The instrumentation needs to be highly accurate (negligible drift) in measuring operational data for extended periods of times, as data collected will be

  4. Requirements for facilities and measurement techniques to support CFD development for hypersonic aircraft

    Science.gov (United States)

    Sellers, William L., III; Dwoyer, Douglas L.

    1992-01-01

    The design of a hypersonic aircraft poses unique challenges to the engineering community. Problems with duplicating flight conditions in ground based facilities have made performance predictions risky. Computational fluid dynamics (CFD) has been proposed as an additional means of providing design data. At the present time, CFD codes are being validated based on sparse experimental data and then used to predict performance at flight conditions with generally unknown levels of uncertainty. This paper will discuss the facility and measurement techniques that are required to support CFD development for the design of hypersonic aircraft. Illustrations are given of recent success in combining experimental and direct numerical simulation in CFD model development and validation for hypersonic perfect gas flows.

  5. Developing guidance in the nuclear criticality safety assessment for fuel cycle facilities

    International Nuclear Information System (INIS)

    Galet, C.; Evo, S.

    2012-01-01

    In this poster IRSN (Institute for radiation protection and nuclear safety) presents its safety guides whose purpose is to transmit the safety assessment know-how to any 'junior' staff or even to give a view of the safety approach on the overall risks to any staff member. IRSN has written a first version of such a safety guide for fuel cycle facilities and laboratories. It is organized into several chapters: some refer to types of assessments, others concern the types of risks. Currently, this guide contains 13 chapters and each chapter consists of three parts. In parallel to the development of criticality chapter of this guide, the IRSN criticality department has developed a nuclear criticality safety guide. It follows the structure of the three parts fore-mentioned, but it presents a more detailed first part and integrates, in the third part, the experience feedback collected on nuclear facilities. The nuclear criticality safety guide is online on the IRSN's web site

  6. Development of decommissioning management system for nuclear fuel cycle facilities (DECMAN)

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichirou; Ishijima, Noboru; Tanimoto, Ken-ichi [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-04-01

    In making a plan of decommissioning of nuclear fuel facilities, it is important to optimize the plan on the standpoint of a few viewpoints, that is, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost (they are called evaluation indexes). In the midst of decommissioning, the decommissioning plan would be modified suitably to optimize the evaluation indexes adjusting to progress of the decommissioning. The decommissioning management code (DECMAN), that is support system on computer, has been developed to assist the decommissioning planning. The system calculates the evaluation indexes quantitatively. The system consists of three fundamental codes, facility information database code, technical know-how database code and index evaluation code, they are composed using Oracle' database and 'G2' expert system. The functions of the system are as follows. (1) Facility information database code. Information of decommissioning facility and its rooms, machines and pipes in the code. (2) Technical know-how database code. Technical Information of tools to use in decommissioning work, cutting, dose measure, and decontamination are there. (3) Index evaluation code. User build decommissioning program using above two database codes. The code evaluates five indexes, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost, on planning decommissioning program. Results of calculation are shown in table, chart, and etc. (author)

  7. Evolution of facility layout requirements and CAD [computer-aided design] system development

    International Nuclear Information System (INIS)

    Jones, M.

    1990-06-01

    The overall configuration of the Superconducting Super Collider (SSC) including the infrastructure and land boundary requirements were developed using a computer-aided design (CAD) system. The evolution of the facility layout requirements and the use of the CAD system are discussed. The emphasis has been on minimizing the amount of input required and maximizing the speed by which the output may be obtained. The computer system used to store the data is also described

  8. Development of a charged particle detector array in Pelletron-LINAC facility

    International Nuclear Information System (INIS)

    John, Bency; Inkar, A.L.; Saxena, A.; Vind, R.P.; Gupta, Y.K.; Biswas, D.C.; Nayak, B.K.; Thomas, R.G.; Danu, L.S.; Choudhury, R.K.; Kailas, S.; Topkar, A.; Venkatramanan, S.; Kumar, Manish; Sunilkumar, S.

    2010-01-01

    A charged particle detector array consisting of 50 Si-CsI detector telescopes for study of heavy-ion reactions is under construction in BARC-TIFR Pelletron-LINAC facility. Developmental work carried out for the detector modules, front-end and pulse shape discrimination electronics, scattering chamber and other mechanical parts are summarized. Some new ideas developed during the course of work are pointed out. (author)

  9. Development and demonstration of sodium fire mitigation system in the SAPFIRE facility

    International Nuclear Information System (INIS)

    Himeno, Y.; Miyahara, S.; Morii, T.; Sasaki, K.

    1989-01-01

    Flow pattern of a realistic sodium leak from the sodium piping equipped with jackets and thermal insulator was experimentally investigated. Then, based on this result, the fire mitigation system consisting of an inclined liner, a drain piping, and a smothering tank has been developed. The performance of the system was, in final, validated in the large-scale sodium leak and fire test in the SAPFIRE facility. (author)

  10. Surrogate Final Technical Report for "Solar: A Photovoltaic Manufacturing Development Facility"

    Energy Technology Data Exchange (ETDEWEB)

    Farrar, Paul [State University of New York Research Foundation, Albany, NY (United States)

    2014-06-27

    The project goal to create a first-of-a-kind crystalline Silicon (c-Si) photovoltaic (PV) Manufacturing & Technology Development Facility (MDF) that will support the growth and maturation of a strong domestic PV manufacturing industry, based on innovative and differentiated technology, by ensuring industry participants can, in a timely and cost-effective manner, access cutting-edge manufacturing equipment and production expertise needed to accelerate the transition of innovative technologies from R&D into manufacturing.

  11. The partnership approach to siting and developing radioactive waste management facilities

    International Nuclear Information System (INIS)

    2010-03-01

    History shows that the search for sites for radioactive waste management facilities has been marred by conflicts and delays. Affected communities have often objected that their concerns and interests were not addressed. In response, institutions have progressively turned away from the traditional 'decide, announce and defend' model, and are learning to 'engage, interact and co-operate'. This shift has fostered the emergence of partnerships between the proponent of the facility and the potential host community. Working in partnership with potential host communities enables pertinent issues and concerns to be raised and addressed, and creates an opportunity for developing a relationship of mutual understanding and mutual learning, as well as for developing solutions that will add value to the host community and region. Key elements of the partnership approach are being incorporated into waste management strategies, leading increasingly to positive outcomes. National radioactive waste management programmes are in various phases of siting facilities and rely on different technical approaches for the various categories of waste. In all cases, it is necessary for institutional actors and the potential or actual host community to build a meaningful, workable relationship. Partnership approaches are effective in achieving a desirable combination of licensable site and management concept while meeting the sometimes competing requirements of fair representation and competent participation. Partnership arrangements facilitate reaching agreement on measures for local control, financial support and future development

  12. Development of remote handling technology for nuclear fuel cycle facilities in Japan

    International Nuclear Information System (INIS)

    Maekawa, Hiromichi; Sakai, Akira; Miura, Noriaki; Kozaka, Tetsuo; Hamada, Takashi

    2015-01-01

    Remote handling technology has been systematically developed for nuclear fuel cycle facilities in Japan since 1970s, primarily in parallel with the development of reprocessing and HLLW (High Level Liquid Waste) vitrification process. In case of reprocessing and vitrification process to handle highly radioactive and hazardous materials, the most of components are installed in the radiation shielded hot cells and operators are not allowed to enter the work area in the cells for operation and maintenance. Therefore, a completely remote handling system is adopted for the cells to reduce radiation doses of operators and increase the availability of the facility. The hot cells are generally designed considering the scale of components (laboratory, demonstration, or full-scale), the function of the systems (chemical process, material handling, dismantling, decontamination, or chemical analysis), and the environmental conditions (radiation dose rate, airborne concentration, surface contamination, or fume/mist/dust). Throughout our domestic development work for remote handling technology, the concept of the large scale integrated cell has been adopted rather than a number of small scale separated cells, for the reasons to reduce the total installation space and the number of remote handling equipment required for the each cell as much as possible. In our domestic remote maintenance design, several new concepts have been developed, tested, and demonstrated in the Tokai Virtrification Facility (TVF) and the Rokkasho HLLW Vitrification and Storage Facility (K-facility). Layout in the hot cells, the performance of remote handling equipment, and the structure of the in-cell components are important factors for remote maintenance design. In case of TVF (hot tests started in 1995), piping and vessels are prefabricated in the rack modules and installed in two lines on both sides of the cell. These modules are designed to be remotely replaced in the whole rack. Two overhead cranes

  13. The National Carbon Capture Center at the Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2014-12-30

    The National Carbon Capture Center (NCCC) at the Power Systems Development Facility supports the Department of Energy (DOE) goal of promoting the United States’ energy security through reliable, clean, and affordable energy produced from coal. Work at the NCCC supports the development of new power technologies and the continued operation of conventional power plants under CO2 emission constraints. The NCCC includes adaptable slipstreams that allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity and accelerate their development path to commercialization. During its first contract period, from October 1, 2008, through December 30, 2014, the NCCC designed, constructed, and began operation of the Post-Combustion Carbon Capture Center (PC4). Testing of CO2 capture technologies commenced in 2011, and through the end of the contract period, more than 25,000 hours of testing had been achieved, supporting a variety of technology developers. Technologies tested included advanced solvents, enzymes, membranes, sorbents, and associated systems. The NCCC continued operation of the existing gasification facilities, which have been in operation since 1996, to support the advancement of technologies for next-generation gasification processes and pre-combustion CO2 capture. The gasification process operated for 13 test runs, supporting over 30,000 hours combined of both gasification and pre-combustion technology developer testing. Throughout the contract period, the NCCC incorporated numerous modifications to the facilities to accommodate technology developers and increase test capabilities. Preparations for further testing were ongoing to continue advancement of the most promising technologies for

  14. On exposure of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The Law for Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1988 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the exposure of workers was below the permissible exposure dose in 1988 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of Japan Atomic Energy Research Institute and Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

  15. Comprehensive development plans for the low- and intermediate-level radioactive waste disposal facility in Korea and preliminary safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Kang Il; Kim, Jin Hyeong; Kwon, Mi Jin; Jeong, Mi Seon; Hong, Sung Wook; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2016-12-15

    The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.

  16. An Overview of Facilities and Capabilities to Support the Development of Nuclear Thermal Propulsion

    Energy Technology Data Exchange (ETDEWEB)

    James Werner; Sam Bhattacharyya; Mike Houts

    2011-02-01

    Abstract. The future of American space exploration depends on the ability to rapidly and economically access locations of interest throughout the solar system. There is a large body of work (both in the US and the Former Soviet Union) that show that Nuclear Thermal Propulsion (NTP) is the most technically mature, advanced propulsion system that can enable this rapid and economical access by its ability to provide a step increase above what is a feasible using a traditional chemical rocket system. For an NTP system to be deployed, the earlier measurements and recent predictions of the performance of the fuel and the reactor system need to be confirmed experimentally prior to launch. Major fuel and reactor system issues to be addressed include fuel performance at temperature, hydrogen compatibility, fission product retention, and restart capability. The prime issue to be addressed for reactor system performance testing involves finding an affordable and environmentally acceptable method to test a range of engine sizes using a combination of nuclear and non-nuclear test facilities. This paper provides an assessment of some of the capabilities and facilities that are available or will be needed to develop and test the nuclear fuel, and reactor components. It will also address briefly options to take advantage of the greatly improvement in computation/simulation and materials processing capabilities that would contribute to making the development of an NTP system more affordable. Keywords: Nuclear Thermal Propulsion (NTP), Fuel fabrication, nuclear testing, test facilities.

  17. Development of training system to prevent accidents during decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, Kwanseong; Moon, Jeikwon; Choi, Byungseon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, Geunho; Seo, Jaeseok

    2014-01-01

    Decommissioning workers need familiarization with working environments because working environment is under high radioactivity and work difficulty during decommissioning of nuclear facilities. On-the-job training of decommissioning works could effectively train decommissioning workers but this training approach could consume much costs and poor modifications of scenarios. The efficiency of virtual training system could be much better than that of physical training system. This paper was intended to develop the training system to prevent accidents for decommissioning of nuclear facilities. The requirements for the training system were drawn. The data management modules for the training system were designed. The training system of decommissioning workers was developed on the basis of virtual reality which is flexibly modified. The visualization and measurement in the training system were real-time done according as changes of the decommissioning scenario. It can be concluded that this training system enables the subject to improve his familiarization about working environments and to prevent accidents during decommissioning of nuclear facilities

  18. Development of a vacuum leak test method for large-scale superconducting magnet test facilities

    International Nuclear Information System (INIS)

    Kawano, Katsumi; Hamada, Kazuya; Okuno, Kiyoshi; Kato, Takashi

    2006-01-01

    Japan Atomic Energy Agency (JAEA) has developed leak detection technology for liquid helium temperature experiments in large-scale superconducting magnet test facilities. In JAEA, a cryosorption pump that uses an absorbent cooled by liquid nitrogen with a conventional helium leak detector, is used to detect helium gas that is leaking from pressurized welded joints of pipes and valves in a vacuum chamber. The cryosorption pump plays the role of decreasing aerial components, such as water, nitrogen and oxygen, to increase the sensitivity of helium leak detection. The established detection sensitivity for helium leak testing is 10 -10 to 10 -9 Pam 3 /s. A total of 850 welded and mechanical joints inside the cryogenic test facility for the ITER Central Solenoid Model Coil (CSMC) experiments have been tested. In the test facility, 73 units of glass fiber-reinforced plastic (GFRP) insulation break are used. The amount of helium permeation through the GFRP was recorded during helium leak testing. To distinguish helium leaks from insulation-break permeation, the helium permeation characteristic of the GFRP part was measured as a function of the time of helium charging. Helium permeation was absorbed at 6 h after helium charging, and the detected permeation is around 10 -7 Pam 3 /s. Using the helium leak test method developed, CSMC experiments have been successfully completed. (author)

  19. Technical developments for an upgrade of the LEBIT Penning trap mass spectrometry facility for rare isotopes

    Science.gov (United States)

    Redshaw, M.; Barquest, B. R.; Bollen, G.; Bustabad, S. E.; Campbell, C. M.; Ferrer, R.; Gehring, A.; Kwiatkowski, A. A.; Lincoln, D. L.; Morrissey, D. J.; Pang, G. K.; Ringle, R.; Schwarz, S.

    2011-07-01

    The LEBIT (Low Energy Beam and Ion Trap) facility is the only Penning trap mass spectrometry (PTMS) facility to utilize rare isotopes produced via fast-beam fragmentation. This technique allows access to practically all elements lighter than uranium, and in particular enables the production of isotopes that are not available or that are difficult to obtain at isotope separation on-line facilities. The preparation of the high-energy rare-isotope beam produced by projectile fragmentation for low-energy PTMS experiments is achieved by gas stopping to slow down and thermalize the fast-beam ions, along with an rf quadrupole cooler and buncher and rf quadrupole ion guides to deliver the beam to the Penning trap. During its first phase of operation LEBIT has been very successful, and new developments are now underway to access rare isotopes even farther from stability, which requires dealing with extremely short lifetimes and low production rates. These developments aim at increasing delivery efficiency, minimizing delivery and measurement time, and maximizing use of available beam time. They include an upgrade to the gas-stopping station, active magnetic field monitoring and stabilization by employing a miniature Penning trap as a magnetometer, the use of stored waveform inverse Fourier transform (SWIFT) to most effectively remove unwanted ions, and charge breeding.

  20. Technical developments for an upgrade of the LEBIT Penning trap mass spectrometry facility for rare isotopes

    International Nuclear Information System (INIS)

    Redshaw, M.; Barquest, B. R.; Bollen, G.; Bustabad, S. E.; Campbell, C. M.; Ferrer, R.; Gehring, A.; Kwiatkowski, A. A.; Lincoln, D. L.; Morrissey, D. J.; Pang, G. K.; Ringle, R.; Schwarz, S.

    2011-01-01

    The LEBIT (Low Energy Beam and Ion Trap) facility is the only Penning trap mass spectrometry (PTMS) facility to utilize rare isotopes produced via fast-beam fragmentation. This technique allows access to practically all elements lighter than uranium, and in particular enables the production of isotopes that are not available or that are difficult to obtain at isotope separation on-line facilities. The preparation of the high-energy rare-isotope beam produced by projectile fragmentation for low-energy PTMS experiments is achieved by gas stopping to slow down and thermalize the fast-beam ions, along with an rf quadrupole cooler and buncher and rf quadrupole ion guides to deliver the beam to the Penning trap. During its first phase of operation LEBIT has been very successful, and new developments are now underway to access rare isotopes even farther from stability, which requires dealing with extremely short lifetimes and low production rates. These developments aim at increasing delivery efficiency, minimizing delivery and measurement time, and maximizing use of available beam time. They include an upgrade to the gas-stopping station, active magnetic field monitoring and stabilization by employing a miniature Penning trap as a magnetometer, the use of stored waveform inverse Fourier transform (SWIFT) to most effectively remove unwanted ions, and charge breeding.

  1. Canadian development program for off-gas management in nuclear facilities

    International Nuclear Information System (INIS)

    Sridhar, T.S.

    1983-01-01

    The Canadian program for the development and evaluation of processes and technology for the separation and containment of radioactive species in off-gases is directed towards the following specific aspects: 1) assessment of available treatment technology and evaluation of future clean-up requirements; 2) development and engineering evaluation, under realistic conditions, of promising new processes that would be inherently simpler and safer; and 3) specification of off-gas emission control systems for future nuclear facilities based on the most favourable technology. The program is being carried out by Atomic Energy of Canada Limited in collaboration with the electrical utility, Ontario Hydro, and selected Canadian universities. A brief description is presented of methods for removing tritium and carbon-14 from the moderator systems of CANDU power reactors, methods for removing iodine from the off-gases of a molybdenum-99 production facility at the Chalk River Nuclear Laboratories, and procedures for monitoring the off-gas effluent composition in the Thorium Fuel Reprocessing Experiment (TFRE) facility at the Whiteshell Nuclear Research Establishment

  2. Development of training system to prevent accidents during decommissioning of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwanseong; Moon, Jeikwon; Choi, Byungseon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, Geunho; Seo, Jaeseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Decommissioning workers need familiarization with working environments because working environment is under high radioactivity and work difficulty during decommissioning of nuclear facilities. On-the-job training of decommissioning works could effectively train decommissioning workers but this training approach could consume much costs and poor modifications of scenarios. The efficiency of virtual training system could be much better than that of physical training system. This paper was intended to develop the training system to prevent accidents for decommissioning of nuclear facilities. The requirements for the training system were drawn. The data management modules for the training system were designed. The training system of decommissioning workers was developed on the basis of virtual reality which is flexibly modified. The visualization and measurement in the training system were real-time done according as changes of the decommissioning scenario. It can be concluded that this training system enables the subject to improve his familiarization about working environments and to prevent accidents during decommissioning of nuclear facilities.

  3. Development of temperamental effortful control mediates the relationship between maturation of the prefrontal cortex and psychopathology during adolescence: A 4-year longitudinal study

    Directory of Open Access Journals (Sweden)

    Nandita Vijayakumar

    2014-07-01

    Full Text Available This study investigated the relationship between the development of effortful control (EC, a temperamental measure of self-regulation, and concurrent development of three regions of the prefrontal cortex (anterior cingulate cortex, ACC; dorsolateral prefrontal cortex, dlPFC; ventrolateral prefrontal cortex, vlPFC between early- and mid-adolescence. It also examined whether development of EC mediated the relationship between cortical maturation and emotional and behavioral symptoms. Ninety-two adolescents underwent baseline assessments when they were approximately 12 years old and follow-up assessments approximately 4 years later. At each assessment, participants had MRI scans and completed the Early Adolescent Temperament Questionnaire-Revised, as well as measures of depressive and anxious symptoms, and aggressive and risk taking behavior. Cortical thicknesses of the ACC, dlPFC and vlPFC, estimated using the FreeSurfer software, were found to decrease over time. EC also decreased over time in females. Greater thinning of the left ACC was associated with less reduction in EC. Furthermore, change in effortful control mediated the relationship between greater thinning of the left ACC and improvements in socioemotional functioning, including reductions in psychopathological symptoms. These findings highlight the dynamic association between EC and the maturation of the anterior cingulate cortex, and the importance of this relationship for socioemotional functioning during adolescence.

  4. Research and Development of a PEM Fuel Cell, Hydrogen Reformer, and Vehicle Refueling Facility

    Energy Technology Data Exchange (ETDEWEB)

    Edward F. Kiczek

    2007-08-31

    Air Products and Chemicals, Inc. has teamed with Plug Power, Inc. of Latham, NY, and the City of Las Vegas, NV, to develop, design, procure, install and operate an on-site hydrogen generation system, an alternative vehicle refueling system, and a stationary hydrogen fuel cell power plant, located in Las Vegas. The facility will become the benchmark for validating new natural gas-based hydrogen systems, PEM fuel cell power generation systems, and numerous new technologies for the safe and reliable delivery of hydrogen as a fuel to vehicles. Most important, this facility will serve as a demonstration of hydrogen as a safe and clean energy alternative. Las Vegas provides an excellent real-world performance and durability testing environment.

  5. Radiation facilities for fusion-reactor first-wall and blanket structural-materials development

    International Nuclear Information System (INIS)

    Klueh, R.L.; Bloom, E.E.

    1981-12-01

    Present and future irradiation facilities for the study of fusion reactor irradiation damage are reviewed. Present studies are centered on irradiation in accelerator-based neutron sources, fast- and mixed-spectrum fission reactors, and ion accelerators. The accelerator-based neutron sources are used to demonstrate damage equivalence between high-energy neutrons and fission reactor neutrons. Once equivalence is demonstrated, the large volume of test space available in fission reactors can be used to study displacement damage, and in some instances, the effects of high-helium concentrations and the interaction of displacement damage and helium on properties. Ion bombardment can be used to study the mechanisms of damage evolution and the interaction of displacement damage and helium. These techniques are reviewed, and typical results obtained from such studies are examined. Finally, future techniques and facilities for developing damage levels that more closely approach those expected in an operating fusion reactor are discussed

  6. Development and use of interactive displays in real-time ground support research facilities

    Science.gov (United States)

    Rhea, Donald C.; Hammons, Kvin R.; Malone, Jacqueline C.; Nesel, Michael C.

    1989-01-01

    The NASA Western Aeronautical Test Range (WATR) is one of the world's most advanced aeronautical research flight test support facilities. A variety of advanced and often unique real-time interactive displays has been developed for use in the mission control centers (MCC) to support research flight and ground testing. These dispalys consist of applications operating on systems described as real-time interactive graphics super workstations and real-time interactive PC/AT compatible workstations. This paper reviews these two types of workstations and the specific applications operating on each display system. The applications provide examples that demonstrate overall system capability applicable for use in other ground-based real-time research/test facilities.

  7. Development of the computer code to monitor gamma radiation in the nuclear facility environment

    International Nuclear Information System (INIS)

    Akhmad, Y. R.; Pudjiyanto, M.S.

    1998-01-01

    Computer codes for gamma radiation monitoring in the vicinity of nuclear facility which have been developed could be introduced to the commercial potable gamma analyzer. The crucial stage of the first year activity was succeeded ; that is the codes have been tested to transfer data file (pulse high distribution) from Micro NOMAD gamma spectrometer (ORTEC product) and the convert them into dosimetry and physics quantities. Those computer codes are called as GABATAN (Gamma Analyzer of Batan) and NAGABAT (Natural Gamma Analyzer of Batan). GABATAN code can isable to used at various nuclear facilities for analyzing gamma field up to 9 MeV, while NAGABAT could be used for analyzing the contribution of natural gamma rays to the exposure rate in the certain location

  8. Neutron and meson sources on the base of high-current cyclotron facilities (prospects of development)

    International Nuclear Information System (INIS)

    Dmitrievskij, V.P.

    1985-01-01

    A brief review is given and possible ways of development of neutron and meson generators on the basis of accelerating facilities are shown. The following conclusions are made: to combine two types of generators (neutron, meson) in one accelerated beam the deuteron beam for the energy 800-1000 MeV/nucleon should be accepted as the optimal one; accelerated beam energy distribution between mesocatalytic and emission branches of neutron generation is determined by the choice of mesocatalytic reactor target parameters; efficiency is the determining parameter of the accelerating facility (complex) when it is u sed for neutron or meson generators; a combination of linear and superconducting cyclic accelerators is the most perspective co mplex as to the efficiency

  9. National Low-Temperature Neutron Irradiation Facility (NLTNIF). The status of development

    International Nuclear Information System (INIS)

    Coltman, R.R. Jr.; Kerchner, H.R.; Klabunde, C.E.; Young, F.W. Jr.

    1985-12-01

    In May 1983, the Department of Energy authorized the establishment of a National Low-Temperature Neutron Irradiation Facility (NLTNIF) at ORNL's Bulk Shielding Reactor (BSR). The NLTNIF, which will be available for qualified experiments at no cost to users, will provide a combination of high radiation intensities and special environmental and testing conditions that have not been previously available in the US. Since the DOE authorization, work has proceeded on the design and construction of the new facility without interruption. This report describes the present status of the development of the NLTNIF and the anticipated schedule for completion and performance testing. There is a table of the major specifications and capabilities and a schematic layout of the irradiation cryostate for design and dimensioning of test and experiment assemblies

  10. Low Prevalence of Chronic Beryllium Disease Among Workers at aNuclearWeaponsResearchandDevelopmentFacility

    Science.gov (United States)

    Arjomandi, Mehrdad; Seward, James; Gotway, Michael B.; Nishimura, Stephen; Fulton, George P.; Thundiyil, Josef; King, Talmadge E.; Harber, Philip; Balmes, John R.

    2012-01-01

    Objective To study the prevalence of beryllium sensitization (BeS) and chronic beryllium disease (CBD) in a cohort of workers from a nuclear weapons research and development facility. Methods We evaluated 50 workers with BeS with medical and occupational histories, physical examination, chest imaging with high-resolution computed tomography (N = 49), and pulmonary function testing. Forty of these workers also underwent bronchoscopy for bronchoalveolar lavage and transbronchial biopsies. Results The mean duration of employment at the facility was 18 years and the mean latency (from first possible exposure) to time of evaluation was 32 years. Five of the workers had CBD at the time of evaluation (based on histology or high-resolution computed tomography); three others had evidence of probable CBD. Conclusions These workers with BeS, characterized by a long duration of potential Be exposure and a long latency, had a low prevalence of CBD. PMID:20523233

  11. Low Prevalence of Chronic Beryllium Disease among Workers at a Nuclear Weapons Research and Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Arjomandi, M; Seward, J P; Gotway, M B; Nishimura, S; Fulton, G P; Thundiyil, J; King, T E; Harber, P; Balmes, J R

    2010-01-11

    To study the prevalence of beryllium sensitization (BeS) and chronic beryllium disease (CBD) in a cohort of workers from a nuclear weapons research and development facility. We evaluated 50 workers with BeS with medical and occupational histories, physical examination, chest imaging with HRCT (N=49), and pulmonary function testing. Forty of these workers also underwent bronchoscopy for bronchoalveolar lavage (BAL) and transbronchial biopsies. The mean duration of employment at the facility was 18 yrs and the mean latency (from first possible exposure) to time of evaluation was 32 yrs. Five of the workers had CBD at the time of evaluation (based on histology or HRCT); three others had evidence of probable CBD. These workers with BeS, characterized by a long duration of potential Be exposure and a long latency, had a low prevalence of CBD.

  12. Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

    International Nuclear Information System (INIS)

    1978-01-01

    This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years

  13. Development of technical design for waste processing and storage facilities for Novi Han repository

    International Nuclear Information System (INIS)

    Canizares, J.; Benitez, J.C.; Asuar, O.; Yordanova, O.; Demireva, E.; Stefanova, I.

    2005-01-01

    Empresarion Agrupados Internacional S.A. (Spain) and ENPRO Consult Ltd. (Bulgaria) were awarded a contract by the Central Finance and Contracts Unit to develop the technical design of the waste processing and storage facilities at the Novi Han repository. At present conceptual design phase is finished. This conceptual design covers the definition of the basic design requirements to be applied to the installations defined above, following both European and Bulgarian legislation. In this paper the following items are considered: 1) Basic criteria for the layout and sizing of buildings; 2) Processing of radioactive waste, including: treatment and conditioning of disused sealed sources; treatment of liquid radioactive wastes; treatment of solid radioactive waste; conditioning of liquid and solid radioactive waste; 3) Control of waste packages and 4) Storage of radioactive waste, including storage facility and waste packages. An analysis of inventories of stored and estimated future wastes and its subsequent processes is also presented and the waste streams are illustrated

  14. Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-29

    This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years.

  15. Development status of oxygen solid electrolyte sensors in HLMC in respect to monoblock reactor facilities

    International Nuclear Information System (INIS)

    Martynov, P.N.; Askhadullin, R.Sh.; Storozhenko, A.N.; Shelemet'ev, V.M.; Sadovnichij, R.P.; Ivanov, I.I.

    2014-01-01

    The results of developing sensors on the base of solid electrolytes to control oxygen in lead and lead-bismuth coolants are considered. It is found out that ceramic detecting elements on the base of solid electrolytes from oxide ceramics are able to work a long time in conditions of high temperatures and thermal shocks in molten metals (in gases). They show stable conducting and mechanical properties, thermal resistance, low gas permeability. Using considered detecting elements different sensors, including ones for monoblock reactors and facilities, are developed and manufactured. The given sensors can be used for both continuous and periodical oxygen control in heavy liquid metal coolants [ru

  16. Development of a prototype gamma camera (Aladin) for use in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Imbard, G.; Carcreff, H.

    1995-01-01

    Mapping the gamma activity of irradiating zones is often an important prerequisite in dismantling nuclear facilities. This operation is necessary to define a suitable decommissioning strategy before any work begins; it is also required during the procedure to measure the residual activity wherever dose rates are too high to allow human intervention. This paper summarizes the work carried out develop a prototype imaging system designed to display radioactive sources superimposed in real time over a visible light image on a video monitor. This project was developed from an earlier off-line system. (authors). 8 refs., 7 figs., 3 tabs

  17. The LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2002-01-01

    Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). A reliable supply of HEU metal from the United States used in the manufacture of targets for the NRU research reactor has been a key factor to enable MDS Nordion to develop a secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets provides predictable, consistent yields for our high-volume molybdenum production process. Each link of the isotope supply chain, from isotope production to ultimate use by the physician, has been established using this proven and established method of HEU target irradiation and processing to extract molybdenum-99. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the construction of two MAPLE reactors and a New Processing Facility. The design of the MAPLE facilities was based on an established process developed by Atomic Energy of Canada Ltd. (AECL) - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a three phase LEU Target Development and Conversion Program for the MAPLE facilities. Phase 1, the Initial Feasibility Study, which identified the technical issues to convert the MAPLE reactor targets from HEU to LEU for large scale commercial production was reported on at the RERTR- 2000 conference. The second phase of the LEU Target Development and Conversion Program was developed with extensive consultation and involvement of experts knowledgeable in target development, process system design, enriched uranium conversion chemistry and commercial scale reactor operations and molybdenum production. This paper will provide an overview of the Phase 2 Conversion Development Program, report on progress to date, and further

  18. Developing an expert system to control a beam line at the Los Alamos Meson Physics Facility

    International Nuclear Information System (INIS)

    Clearwater, S.H.; Papcun, G.; Clark, D.A.

    1985-01-01

    High energy particle experiments require an accelerator as a source of high energy particles. To increase the productivity of an accelerator facility, we wish to develop an expert system to control beam lines. Expert Systems are a branch of Artificial Intelligence where a computer program performs tasks requiring human expertise. Unlike most expert systems we have a physical model underlying our beam line and this model can be used with the expert system to improve performance. The development of the expert system will lead to an increased understanding of the beam line as well as the possibility of state-of-the-art expert system building

  19. CENER/NREL Collaboration in Testing Facility and Code Development: Cooperative Research and Development Final Report, CRADA Number CRD-06-207

    Energy Technology Data Exchange (ETDEWEB)

    Moriarty, P.

    2014-11-01

    Under the funds-in CRADA agreement, NREL and CENER will collaborate in the areas of blade and drivetrain testing facility development and code development. The project shall include NREL assisting in the review and instruction necessary to assist in commissioning the new CENER blade test and drivetrain test facilities. In addition, training will be provided by allowing CENER testing staff to observe testing and operating procedures at the NREL blade test and drivetrain test facilities. CENER and NREL will exchange blade and drivetrain facility and equipment design and performance information. The project shall also include exchanging expertise in code development and data to validate numerous computational codes.

  20. Achievement report for fiscal 2000 on development of technology to evaluate reliability of petroleum refining facilities; 2000 nendo sekiyu seisei setsubi shinraisei hyoka nado gijutsu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    This paper reports the achievements in fiscal 2000 in development of a technology to evaluate reliability of petroleum refining facilities. The development efforts were made mainly on analyses by simulation and neural net (NN) that utilize computers. In the high-temperature system facilities, the creep damage generation is governed by different factors including impurities. The evaluation on joint life requires simultaneous use of low temperature zone long-time test. Verification was made on application of non-destructive inspection, such as use of ultrasonic waves in the accelerated creep zone. Defect detecting capability was identified when an ultrasonic wave flaw detection model is used for buried piping. In the pulse eddy current flaw detection, a coil most superb in totality was selected by means of simulation, by which corrosion and wall thickness of piping and devices were detected from outside the sheathing materials. Development was made on a technology to diagnose and evaluate corrosion of tank in operation by using the AE method. The remaining life of transformers is determined by how seriously the coil insulating paper has been deteriorated, and furfural in the oil was found effective for the parameters. Particularly, application of the NN was revealed to be effective in estimating electric motor deterioration. A high-temperature sulfide corrosion rate estimating model was developed from the operation and measurement data of the facilities by applying the NN and TCBM. (NEDO)

  1. Development of the international Chornobyl center in Slavutych its role in nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    Nosovskij, A.

    2002-01-01

    ChNPP site should be actively used for development and realizing the efforts on RBMK reactors decommissioning technologies, as well as Unit 'Shelter' transformation into ecologically safe system. Those technologies and methods will be required in future both in Ukraine and abroad. So, it is wise to employ another direction of ChNPP site utilization as a polygon for development and implementing new technologies associated with decommissioning. Besides, it could be used for exercising the methods and technologies of large-scale man-caused accidents elimination

  2. On exposure management of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1993

    International Nuclear Information System (INIS)

    1994-01-01

    The Law of Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1993 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the the exposure of workers was below the permissible exposure dose in 1993 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of JAERI and PNC. (J.P.N.)

  3. A conversion development program to LEU targets for medical isotope production in the MAPLE Facilities

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2000-01-01

    Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). The molybdenum extraction process from the HEU targets provided predictable, consistent yields for our high-volume molybdenum production process. A reliable supply of HEU for the NRU research reactor targets has enabled MDS Nordion to develop a secure chain of medical isotope supply for the international nuclear medicine community. Each link of the isotope supply chain, from isotope production to patient application, has been established on a proven method of HEU target irradiation and processing. To ensure a continued reliable and timely supply of medical isotopes, the design of the MAPLE facilities was based on our established process - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a program to convert the MAPLE facilities to LEU targets. An initial feasibility study was initiated to identify the technical issues to convert the MAPLE targets from HEU to LEU. This paper will present the results of the feasibility study. It will also describe future challenges and opportunities in converting the MAPLE facilities to LEU targets for large scale, commercial medical isotope production. (author)

  4. Development of likelihood estimation method for criticality accidents of mixed oxide fuel fabrication facilities

    International Nuclear Information System (INIS)

    Tamaki, Hitoshi; Yoshida, Kazuo; Kimoto, Tatsuya; Hamaguchi, Yoshikane

    2010-01-01

    A criticality accident in a MOX fuel fabrication facility may occur depending on several parameters, such as mass inventory and plutonium enrichment. MOX handling units in the facility are designed and operated based on the double contingency principle to prevent criticality accidents. Control failures of at least two parameters are needed for the occurrence of criticality accident. To evaluate the probability of such control failures, the criticality conditions of each parameter for a specific handling unit are necessary for accident scenario analysis to be clarified quantitatively with a criticality analysis computer code. In addition to this issue, a computer-based control system for mass inventory is planned to be installed into MOX handling equipment in a commercial MOX fuel fabrication plant. The reliability analysis is another important issue in evaluating the likelihood of control failure caused by software malfunction. A likelihood estimation method for criticality accident has been developed with these issues been taken into consideration. In this paper, an example of analysis with the proposed method and the applicability of the method are also shown through a trial application to a model MOX fabrication facility. (author)

  5. Coal-fired MHD test progress at the Component Development and Integration Facility

    International Nuclear Information System (INIS)

    Hart, A.T.; Rivers, T.J.; Alsberg, C.M.; Filius, K.D.

    1992-01-01

    The Component Development and Integration Facility (CDIF) is a Department of Energy test facility operated by MSE, Inc. In the fall of 1984, a 50-MW t , pressurized, slag rejecting coal-fired combustor (CFC) replaced the oil-fired combustor in the test train. In the spring of 1989, a coal-fired precombustor was added to the test hardware, and current controls were installed in the spring of 1990. In the fall of 1990, the slag rejector was installed. MSE test hardware activities included installing the final workhorse channel and modifying the coalfired combustor by installing improved design and proof-of-concept (POC) test pieces. This paper discusses the involvement of this hardware in test progress during the past year. Testing during the last year emphasized the final workhorse hardware testing. This testing will be discussed. Facility modifications and system upgrades for improved operation and duration testing will be discussed. In addition, this paper will address long-term testing plans

  6. Design and development of a neutron tomography facility at the IPEN-CNEN/SP, Brazil

    International Nuclear Information System (INIS)

    Schoueri, Roberto Mauro

    2016-01-01

    In the work reported in this dissertation, a facility for neutron tomography was developed and installed at the irradiation channel 14 of the IEA-R1 nuclear research reactor of IPEN-CNEN/SP. Several selected objects were inspected, and the obtained images demonstrate the main characteristic of the present technique that is its capability to visualize hydrogenous rich substances. In such facility, a tomography can be obtained in 400 s with a spatial resolution of 205 μm, and the obtained images have sufficient quality to allow qualitative and quantitative analysis. These characteristics are very similar to the ones of the top facilities around the world, and the quality of the provided images are sufficient to allow qualitative and quantitative analysis of the inspected object. The implementation of the neutron tomography technique opens up the possibility of new research as it provides a new tool for inspection of objects, which provides a view of its internal structure, which is not always possible for two-dimensional imaging methods. (author)

  7. Development and Commissioning of an External Beam Facility in the Union College Ion Beam Analysis Laboratory

    Science.gov (United States)

    Yoskowitz, Joshua; Clark, Morgan; Labrake, Scott; Vineyard, Michael

    2015-10-01

    We have developed an external beam facility for the 1.1-MV tandem Pelletron accelerator in the Union College Ion Beam Analysis Laboratory. The beam is extracted from an aluminum pipe through a 1 / 4 ' ' diameter window with a 7.5- μm thick Kapton foil. This external beam facility allows us to perform ion beam analysis on samples that cannot be put under vacuum, including wet samples and samples too large to fit into the scattering chamber. We have commissioned the new facility by performing proton induced X-ray emission (PIXE) analysis of several samples of environmental interest. These include samples of artificial turf, running tracks, and a human tooth with an amalgam filling. A 1.7-MeV external proton beam was incident on the samples positioned 2 cm from the window. The resulting X-rays were measured using a silicon drift detector and were analyzed using GUPIX software to determine the concentrations of elements in the samples. The results on the human tooth indicate that while significant concentrations of Hg, Ag, and Sn are present in the amalgam filling, only trace amounts of Hg appear to have leached into the tooth. The artificial turf and running tracks show rather large concentrations of a broad range of elements and trace amounts of Pb in the turf infill.

  8. Development and validation of fall risk screening tools for use in residential aged care facilities.

    Science.gov (United States)

    Delbaere, Kim; Close, Jacqueline C T; Menz, Hylton B; Cumming, Robert G; Cameron, Ian D; Sambrook, Philip N; March, Lyn M; Lord, Stephen R

    2008-08-18

    To develop screening tools for predicting falls in nursing home and intermediate-care hostel residents who can and cannot stand unaided. Prospective cohort study in residential aged care facilities in northern Sydney, New South Wales, June 1999-June 2003. 2005 people aged 65-104 years (mean +/- SD, 85.7+/-7.1 years). Demographic, health, and physical function assessment measures; number of falls over a 6-month period; validity of the screening models. Ability to stand unaided was identified as a significant event modifier for falls. In people who could stand unaided, having either poor balance or two of three other risk factors (previous falls, nursing home residence, and urinary incontinence) increased the risk of falling in the next 6 months threefold (sensitivity, 73%; specificity, 55%). In people who could not stand unaided, having any one of three risk factors (previous falls, hostel residence, and using nine or more medications) increased the risk of falling twofold (sensitivity, 87%; specificity, 29%). These two screening models are useful for identifying older people living in residential aged care facilities who are at increased risk of falls. The screens are easy to administer and contain items that are routinely collected in residential aged care facilities in Australia.

  9. Development of a collinear laser spectrometer facility at VECC: First test result

    Science.gov (United States)

    Ali, Md Sabir; Ray, Ayan; Raja, Waseem; Bandyopadhyay, Arup; Naik, Vaishali; Polley, Asish; Chakrabarti, Alok

    2018-04-01

    We report here the development of collinear laser spectroscopy (CLS) system at VECC for the study of hyperfine spectrum and isotopic shift of stable and unstable isotopes. The facility is first of its kind in the country allowing measurement of hyperfine splitting of atomic levels using atomic beams. The CLS system is installed downstream of the focal plane of the existing isotope separator online (ISOL) facility at VECC and is recently commissioned by successfully resolving the fluorescence spectrum of the hyperfine levels in ^{85,87}Rb. The atomic beams of Rb were produced by charge exchange of 8 keV Rb ion beam which were produced, extracted and transported to the charge exchange cell using the ion sources, extractor and the beam-line magnets of the ISOL facility. The laser propagating opposite to the ion / atom beam direction was allowed to interact with the atom beam and fluorescence spectrum was recorded. The experimental set-up and the experiment conducted are reported in detail. The measures needed to be carried out for improving the sensitivity to a level necessary for studying short-lived exotic nuclei have also been discussed.

  10. Developing the Biomolecular Screening Facility at the EPFL into the Chemical Biology Screening Platform for Switzerland.

    Science.gov (United States)

    Turcatti, Gerardo

    2014-05-01

    The Biomolecular Screening Facility (BSF) is a multidisciplinary laboratory created in 2006 at the Ecole Polytechnique Federale de Lausanne (EPFL) to perform medium and high throughput screening in life sciences-related projects. The BSF was conceived and developed to meet the needs of a wide range of researchers, without privileging a particular biological discipline or therapeutic area. The facility has the necessary infrastructure, multidisciplinary expertise and flexibility to perform large screening programs using small interfering RNAs (siRNAs) and chemical collections in the areas of chemical biology, systems biology and drug discovery. In the framework of the National Centres of Competence in Research (NCCR) Chemical Biology, the BSF is hosting 'ACCESS', the Academic Chemical Screening Platform of Switzerland that provides the scientific community with chemical diversity, screening facilities and know-how in chemical genetics. In addition, the BSF started its own applied research axes that are driven by innovation in thematic areas related to preclinical drug discovery and discovery of bioactive probes.

  11. A complete fuel development facility utilizing a dual core TRIGA reactor system

    Energy Technology Data Exchange (ETDEWEB)

    Middleton, A; Law, G C [General Atomic Co., San Diego, CA (United States)

    1974-07-01

    A TRIGA Dual Core Reactor System has been chosen by the Romanian Government as the heart of a new fuel development facility which will be operated by the Romanian Institute for Nuclear Technologies. The Facility, which will be operational in 1976, is an integral part of the Romanian National Program for Power Reactor Development, with particular emphasis being placed on fuel development. The unique combination of a new 14 MW steady state TRIGA reactor, and the well-proven TRIGA Annular Core Pulsing Reactor (ACPR) in one below-ground reactor pool resulted in a substantial construction cost savings and gives the facility remarkable experimental flexibility. The inherent safety of the TRIGA fuel elements in both reactor cores means that a secondary containment building is not necessary, resulting in further construction cost savings. The 14 MW steady state reactor gives acceptably high neutron fluxes for long- term testing of various prototype fuel-cladding-coolant combinations; and the TRIGA ACPR high pulse capability allows transient testing of fuel specimens, which is so important for accurate prediction of the performance of power reactor fuel elements under postulated failure conditions. The 14 MW steady state reactor has one large and three small in-core irradiation loop positions, two large irradiation loop positions adjacent to the core face, and twenty small holes in the beryllium reflector for small capsule irradiation. The power level of 14 MW will yield peak unperturbed thermal neutron fluxes in the central experiment position approaching 3.0 x 10{sup 14} n/cm{sup 2}-sec. The ACPR has one large dry central experimental cavity which can be loaded at pool level through a shielded offset loading tube; a small diameter in-core flux trap; and an in-core pneumatically-operated capsule irradiation position. A peak pulse of 15,000 MW will yield a peak fast neutron flux in the central experimental cavity of about 1.5 x 10{sup 17} n/cm{sup 2}-sec. The pulse width at

  12. 7 CFR Appendix D to Subpart E of... - Alcohol Production Facilities Planning, Performing, Development and Project Control

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 14 2010-01-01 2009-01-01 true Alcohol Production Facilities Planning, Performing... of Part 1980—Alcohol Production Facilities Planning, Performing, Development and Project Control (I..., without recourse to the Government, for the settlement and satisfaction of all contractual and...

  13. 25 CFR 170.807 - What must BIA include when it develops an IRR Transportation Facilities Maintenance Management...

    Science.gov (United States)

    2010-04-01

    ... Transportation Facilities Maintenance Management System? 170.807 Section 170.807 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR LAND AND WATER INDIAN RESERVATION ROADS PROGRAM BIA Road Maintenance § 170.807 What must BIA include when it develops an IRR Transportation Facilities Maintenance Management System...

  14. Development and oviposition preference of house flies and stable flies (Diptera: Muscidae) in six substrates from Florida equine facilities

    Science.gov (United States)

    House flies, Musca domestica L., and stable flies, Stomoxys calcitrans (L.), (Diptera: Muscidae), common pests on equine facilities, were studied in the laboratory to determine their oviposition preferences and larval development on six substrates commonly found on equine facilities. The substrates...

  15. Scratch to state-of-the-art: setting up a new robotic facility in a developing country.

    Science.gov (United States)

    Bora, G S; Mavuduru, R S; Devana, S K; Singh, S K; Mandal, A K

    2018-03-01

    The potential challenges encountered for setting up a robotic assisted surgical facility in developing country like India are many. We describe the initial hurdles and troubleshooting in establishing a facility of such kind. This experience might help to decrease initial hiccups in setting up such an innovative technology at other institutes.

  16. Development of a mixed waste management facility at the Nevada Test Site

    International Nuclear Information System (INIS)

    Dolenc, M.R.; Kendall, E.W.

    1989-01-01

    The US Department of Energy (DOE) produces some radioactive low-level wastes (LLW) which contain hazardous components. By definition, the management of those mixed wastes (MW) at the Nevada Test Site (NTS) requires compliance with US Environmental Protection Agency (EPA) and state of Nevada regulations for hazardous wastes, and DOE regulations for LLW. Preparations for operation of a separate Mixed Waste Management Unit (MWMU) in the 1990s are underway. The 167-acre MWMU will be a part of the 732-acre Area 5 Radioactive Waste Management Site (RWMS). The MWMU is being developed in response to a DOE Office of Defense Waste and Transporation Management need to provide enhanced capabilities and facilities for safe, secure, and efficient disposal of defense-related MW in accordance with DOE, EPA, and state of Nevada requirements. Planned activities relating to the development of the MWMU include completing National Environmental Policy Act (NEPA) requirements; responding to any notices of deficiencies (NODs) on the NTS Part B Permit application; conducting generator audits as part of the NTS MW certification program; optimizing the design and operation of the vadose zone monitoring system; developing protocols for the sampling and analysis of MW, and facility construction. This paper describes the permitting and regulatory environment, the specific application of the permit process to the NTS, and the phased development of an MWMU at the NTS

  17. Nuclear safety and radiation protection consideration in the design of research and development facility

    International Nuclear Information System (INIS)

    Akbar, M.R.

    2010-01-01

    Nuclear safety is a critically important aspect that must be considered in the design of a nuclear facility in order to ensure the protection of the workers, public and environment. This paper looks at the methodology, approach and incorporation of this aspect, specifically into the design of a research and development facility. The Health, Safety and Environmental Basis of Design is an initial analysis of nuclear safety and radiation protection considerations that is performed during the conceptual design phase and sets the baseline for what the design of the facility must conform to. It consists of general nuclear safety design principles, such as defence in depth and optimisation considerations, and a hazard management strategy. Following the Health, Safety and Environmental Basis of Design, a Preliminary Safety Assessment Report is generated during the basic design phase in conjunction with various analyses in order to assess the impact of hazards on the workers and members of the public. This assessment follows a hazard graded approach where the depth of the analysis will be determined by the impact of the worst case accident scenario in the facility. The assessment also includes a waste management strategy which is an essential aspect to be considered in the design in order to minimize the generation of waste. The safety assessment also demonstrates compliance to dose limits and risk criteria for the workers and members of the public set by the regulatory body and supported by a legal framework. Measures are taken to keep risk as low as reasonably achievable and prevent transgression of the risk and dose limits. However, a balance needs to be maintained between 5 reducing these doses further and the cost of such a reduction, which is known as optimization. It is therefore imperative to have nuclear safety specialists analyse the design in order to protect the worker and member of the public from unwarranted exposure to nuclear radiation. (author)

  18. Space Infrared Telescope Facility (SIRTF) - Operations concept. [decreasing development and operations cost

    Science.gov (United States)

    Miller, Richard B.

    1992-01-01

    The development and operations costs of the Space IR Telescope Facility (SIRTF) are discussed in the light of minimizing total outlays and optimizing efficiency. The development phase cannot extend into the post-launch segment which is planned to only support system verification and calibration followed by operations with a 70-percent efficiency goal. The importance of reducing the ground-support staff is demonstrated, and the value of the highly sensitive observations to the general astronomical community is described. The Failure Protection Algorithm for the SIRTF is designed for the 5-yr lifetime and the continuous venting of cryogen, and a science driven ground/operations system is described. Attention is given to balancing cost and performance, prototyping during the development phase, incremental development, the utilization of standards, and the integration of ground system/operations with flight system integration and test.

  19. The Management System for the Development of Disposal Facilities for Radioactive Waste

    International Nuclear Information System (INIS)

    2011-01-01

    Currently, many Member States are safely operating near surface disposal facilities and some are in the initial or advanced stages of planning geological repositories. As for other nuclear facilities and their operational phase, all activities associated with the disposal of radioactive waste need to be carefully planned and systematic actions undertaken in order to maintain adequate confidence that disposal systems will meet performance as well as prescribed safety requirements and objectives. The effective development and application of a management system (integrating requirements for safety, protection of health and the environment, security, quality and economics into one coherent system) which addresses every stage of repository development is essential. It provides assurance that the objectives for repository performance and safety, as well as environmental and quality criteria, will be met. For near surface repositories, a management system also provides the opportunity to re-evaluate existing disposal systems with respect to new safety, environmental or societal requirements which could arise during the operational period of a facility. The topic of waste management and disposal continues to generate public interest and scrutiny. Implementation of a formal management system provides documentation, transparency and accountability for the various activities and processes associated with radioactive waste disposal. This information can contribute to building public confidence and acceptance of disposal facilities. The objective of this report is to provide Member States with practical guidance and relevant information on management system principles and expectations for management systems that can serve as a basis for developing and implementing a management system for three important stages; the design, construction/upgrading and operation of disposal facilities. To facilitate the understanding of management system implementation at the different stages of a

  20. Recent developments in IFE safety and tritium research and considerations for future nuclear fusion facilities

    International Nuclear Information System (INIS)

    Reyes, Susana; Anklam, Tom; Meier, Wayne; Campbell, Patrick; Babineau, Dave; Becnel, James; Taylor, Craig; Coons, Jim

    2016-01-01

    Highlights: • The safety characteristics and at risk inventories in an IFE facility are discussed. • The primary nuclear hazard is the potential exposure of workers and/or the public to tritium and/or neutronically activated products. • Recent technology developments in tritium processing are key for minimization of inventories. • Initial safety studies indicate that hazards associated to the use of liquid lithium can be appropriately managed. • Simulation of worst-case scenarios indicate that the accident consequences are limited and below the limit for public evacuation. - Abstract: Over the past five years, the fusion energy group at Lawrence Livermore National Laboratory (LLNL) has made significant progress in the area of safety and tritium research for Inertial Fusion Energy (IFE). Focus has been driven towards the minimization of inventories, accident safety, development of safety guidelines and licensing considerations. Recent technology developments in tritium processing and target fill have had a major impact on reduction of tritium inventories in the facility. A safety advantage of inertial fusion energy using indirect-drive targets is that the structural materials surrounding the fusion reactions can be protected from target emissions by a low-pressure chamber fill gas, therefore eliminating plasma-material erosion as a source of activated dust production. An important inherent safety advantage of IFE when compared to other magnetic fusion energy (MFE) concepts that have been proposed to-date (including ITER), is that loss of plasma control events with the potential to damage the first wall, such as disruptions, are non-conceivable, therefore eliminating a number of potential accident initiators and radioactive in-vessel source term generation. In this paper, we present an overview of the safety assessments performed to-date, comparing results to the US DOE Fusion Safety Standards guidelines and the recent lessons-learnt from ITER safety and