WorldWideScience

Sample records for facility development experiment

  1. 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.

  2. 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

  3. 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

  4. 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

  5. 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.

  6. Experiences in the development of an emergency response facility (ERF) system for a nuclear power plant

    International Nuclear Information System (INIS)

    Seisdedos, A.; Sanchez-Fornie, M.A.

    1985-01-01

    The TMI-2 accident gave rise to a series of new requirements with which Nuclear Power Plants must comply and amongst which the implementation of emergency response facilities, particularly the SPDS, has received special attention. This paper covers the experience and problems encountered in the developing of the engineering necessary for the detailed definition of the ERF in a Nuclear Power Plant in the commercial operation phase. Also, a real example is provided for the case of a plant in the last phase of construction and installation. This will serve to illustrate each of the topics covered. (author)

  7. Gas-grain simulation experiment module conceptual design and gas-grain simulation facility breadboard development

    Science.gov (United States)

    Zamel, James M.; Petach, Michael; Gat, Nahum; Kropp, Jack; Luong, Christina; Wolff, Michael

    1993-12-01

    This report delineates the Option portion of the Phase A Gas-Grain Simulation Facility study. The conceptual design of a Gas-Grain Simulation Experiment Module (GGSEM) for Space Shuttle Middeck is discussed. In addition, a laboratory breadboard was developed during this study to develop a key function for the GGSEM and the GGSF, specifically, a solid particle cloud generating device. The breadboard design and test results are discussed and recommendations for further studies are included. The GGSEM is intended to fly on board a low earth orbit (LEO), manned platform. It will be used to perform a subset of the experiments planned for the GGSF for Space Station Freedom, as it can partially accommodate a number of the science experiments. The outcome of the experiments performed will provide an increased understanding of the operational requirements for the GGSF. The GGSEM will also act as a platform to accomplish technology development and proof-of-principle experiments for GGSF hardware, and to verify concepts and designs of hardware for GGSF. The GGSEM will allow assembled subsystems to be tested to verify facility level operation. The technology development that can be accommodated by the GGSEM includes: GGSF sample generation techniques, GGSF on-line diagnostics techniques, sample collection techniques, performance of various types of sensors for environmental monitoring, and some off-line diagnostics. Advantages and disadvantages of several LEO platforms available for GGSEM applications are identified and discussed. Several of the anticipated GGSF experiments require the de-agglomeration and dispensing of dry solid particles into an experiment chamber. During the GGSF Phase A study, various techniques and devices available for the solid particle aerosol generator were reviewed. As a result of this review, solid particle de-agglomeration and dispensing were identified as key undeveloped technologies in the GGSF design. A laboratory breadboard version of a solid

  8. Development and Operation of Experiment Course using Research Reactor and Associated Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Shin, B. C.; Hwang, I. A.; Won, J. Y.; Ju, Y. C.; Nam, J. S.; Seo, K. W.; Kim, H. N.

    2013-05-15

    The purpose of present research is to offer a specialized educational opportunity by developing specific curriculum for potential users, mainly university students majoring in related with nuclear engineering and radiation field, on site at KAERI, exploiting the diverse offering of HANARO and ancillary facilities. The specific items of this research accomplished are: First, Development of various curricula for specific research using HANARO and continuous operation of the developed curricula to provided university students with opportunities to use HANARO. Second, Continuous operation of research reactor related experimental training programs for university students in nuclear field to make contribution to cultivating specialists. Third, through the site experimental training for new coming nuclear engineering students, support future potential users to the nuclear research fields, as well as enlarge or broaden the base. Finally, it is hoped that these experiments broadens public awareness and acceptance of the present and potential future contribution of the reactor technology, there by bring positive impacts to policy making. As a whole, 108 students offered and 88 students from 6 universities have completed the course of the programs developed by this project. Also, 1 textbook and 1 teaching aid, a questionnaire have been developed to support the program.

  9. 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)

  10. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume IV

    International Nuclear Information System (INIS)

    Abdou, M.

    1984-10-01

    This volume contains the following chapters (1) neutronics tests, (2) fluence considerations, (3) instrumentation and test matrix, (4) non-neutron test stands, (5) accelerator-based point neutron sources, (6) utilization of fission reactors, (7) tandem mirror test facilities, (8) tokamak fusion test facilities, (9) reliability development testing impacts on fusion reactor availability, and (10) fusion development scenarios. In addition, the following appendices are included: (1) evaluation of experience from fast breeder reactors, (2) observations of experts from the fission field, (3) evaluation of experience from the aerospace industry, (4) characterization of fusion nuclear systems operating environment, (5) modelling of MFTF-α+T high gamma mode performance, and (6) small-scale, multiple effects testing at US/DOE breeder reactor in-pile facilities

  11. Los Alamos Critical Experiments Facility

    International Nuclear Information System (INIS)

    Malenfant, R.E.

    1991-01-01

    The Critical Experiments Facility of the Los Alamos National Laboratory has been in existence for 45 years. In that period of time, thousands of measurements have been made on assemblies containing every fissionable material in various configurations that included bare metal and compounds of the nitrate, sulfate, fluoride, carbide, and oxide. Techniques developed or applied include Rossi-α, source-jerk, rod oscillator, and replacement measurements. Many of the original measurements of delay neutrons were performed at the site, and a replica of the Hiroshima weapon was operated at steady state to assist in evaluating the relative biological effectiveness (RBE) of neutrons. Solid, liquid, and gas fissioning systems were run at critical. Operation of this original critical facility has demonstrated the margin of safety that can be obtained through remote operation. Eight accidental excursions have occurred on the site, ranging from 1.5 x 10 16 to 1.2 x 10 17 fissions, with no significant exposure to personnel or damage to the facility beyond the machines themselves -- and in only one case was the machine damaged beyond further use. The present status of the facility, operating procedures, and complement of machines will be described in the context of programmatic activity. New programs will focus on training, validation of criticality alarm systems, experimental safety assessment of process applications, and dosimetry. Special emphasis will be placed on the incorporation of experience from 45 years of operation into present procedures and programs. 3 refs

  12. 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.

  13. Shielding experiments for accelerator facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nakashima, Hiroshi; Tanaka, Susumu; Sakamoto, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    2000-06-01

    A series of shielding experiments was carried out by using AVF cyclotron accelerator of TIARA at JAERI in order to validate shielding design methods for accelerator facilities in intermediate energy region. In this paper neutron transmission experiment through thick shields and radiation streaming experiment through a labyrinth are reported. (author)

  14. Shielding experiments for accelerator facilities

    International Nuclear Information System (INIS)

    Nakashima, Hiroshi; Tanaka, Susumu; Sakamoto, Yukio

    2000-01-01

    A series of shielding experiments was carried out by using AVF cyclotron accelerator of TIARA at JAERI in order to validate shielding design methods for accelerator facilities in intermediate energy region. In this paper neutron transmission experiment through thick shields and radiation streaming experiment through a labyrinth are reported. (author)

  15. 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

  16. Operating experience of gas bearing helium circulators in HTGR development facility

    International Nuclear Information System (INIS)

    Shimomura, H.; Kawaji, S.; Fujisaki, K.; Ihizuka, T.

    1988-01-01

    The large scale helium gas test facility (HENDEL) has been constructed and operated since March 1982 at the Japan Atomic Energy Research Institute to develop HTGR components. The five electric driven gas circulators with dynamic gas bearings are used to circulate the helium gas of 4MPa and 400 deg. C in loops for their compactness, gas tightness, easy maintenance and free from gas contamination. All of these circulators are variable speed types of 3,000 to 12,000 rpm and have the same gas bearings and electric motors. The four machines among them are equipped with centrifugal impeller and one other machine has regenerative type, and the weight of both type rotors are nearly the same. After the troubles and repairing, both type of circulators were tested and the vibration characteristics were measured as preventing maintenance. From the test and measurements of the circulators, it was presumed that the first trouble on regenerative type was caused from excess unbalance force by falling off of a small pin from the rotating part and the second severe trouble on it was caused by the whipping in gas bearing. The static load on tilting pads indicated close relations to occurrence of the whirling through the measurements. It is recognized that fine balancing of the rotors and delicate clearance adjustment of the bearings are very important for the rotor stability and that the mechanism should be designed and machined so precise as to be adjustable. As the gas bearing would be damaged in an instantaneously short time, the monitoring technique for it should be so fast and predictive as to prevent serious damage. Through the tests, the vibration spectrum monitoring method seems to be predictive and useful for early detection of the shaft instability. It will be concluded that the gas bearing machine is an excellent system in its design philosophy, however, it also needs highly precise machining and delicate maintenance technique. 4 refs, 10 figs, 1 tab

  17. Large scale and low latency analysis facilities for the CMS experiment: development and operational aspects

    CERN Document Server

    Riahi, Hassen

    2010-01-01

    While a majority of CMS data analysis activities rely on the distributed computing infrastructure on the WLCG Grid, dedicated local computing facilities have been deployed to address particular requirements in terms of latency and scale. The CMS CERN Analysis Facility (CAF) was primarily designed to host a large variety of latency-critical workfows. These break down into alignment and calibration, detector commissioning and diagnosis, and high-interest physics analysis requiring fast turnaround. In order to reach the goal for fast turnaround tasks, the Workload Management group has designed a CRABServer based system to fit with two main needs: to provide a simple, familiar interface to the user (as used in the CRAB Analysis Tool[7]) and to allow an easy transition to the Tier-0 system. While the CRABServer component had been initially designed for Grid analysis by CMS end-users, with a few modifications it turned out to be also a very powerful service to manage and monitor local submissions on the CAF. Tran...

  18. Drive development for an 10 Mbar Rayleigh-Taylor strength experiment on the National Ignition Facility

    Science.gov (United States)

    Prisbrey, Shon; Park, Hye-Sook; Huntington, Channing; McNaney, James; Smith, Raym; Wehrenberg, Christopher; Swift, Damian; Panas, Cynthia; Lord, Dawn; Arsenlis, Athanasios

    2017-10-01

    Strength can be inferred by the amount a Rayleigh-Taylor surface deviates from classical growth when subjected to acceleration. If the acceleration is great enough, even materials highly resistant to deformation will flow. We use the National Ignition Facility (NIF) to create an acceleration profile that will cause sample metals, such as Mo or Cu, to reach peak pressures of 10 Mbar without inducing shock melt. To create such a profile we shock release a stepped density reservoir across a large gap with the stagnation of the reservoir on the far side of the gap resulting in the desired pressure drive history. Low density steps (foams) are a necessary part of this design and have been studied in the last several years on the Omega and NIF facilities. We will present computational and experimental progress that has been made on the 10 Mbar drive designs - including recent drive shots carried out at the NIF. This work was performed under the auspices of the Lawrence Livermore National Security, LLC, (LLNS) under Contract No. DE-AC52-07NA27344. LLNL-ABS-734781.

  19. On-orbit technology experiment facility definition

    Science.gov (United States)

    Russell, Richard A.; Buchan, Robert W.; Gates, Richard M.

    1988-01-01

    A study was conducted to identify on-orbit integrated facility needs to support in-space technology experiments on the Space Station and associated free flyers. In particular, the first task was to examine the proposed technology development missions (TDMX's) from the model mission set and other proposed experimental facilities, both individually and by theme, to determine how and if the experiments might be combined, what equipment might be shared, what equipment might be used as generic equipment for continued experimentation, and what experiments will conflict with the conduct of other experiments or Space Station operations. Then using these results, to determine on-orbit facility needs to optimize the implementation of technology payloads. Finally, to develop one or more scenarios, design concepts, and outfitting requirements for implementation of onboard technology experiments.

  20. 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

  1. ARADISH - Development of a Standardized Plant Growth Chamber for Experiments in Gravitational Biology Using Ground Based Facilities

    Science.gov (United States)

    Schüler, Oliver; Krause, Lars; Görög, Mark; Hauslage, Jens; Kesseler, Leona; Böhmer, Maik; Hemmersbach, Ruth

    2016-06-01

    Plant development strongly relies on environmental conditions. Growth of plants in Biological Life Support Systems (BLSS), which are a necessity to allow human survival during long-term space exploration missions, poses a particular problem for plant growth, as in addition to the traditional environmental factors, microgravity (or reduced gravity such as on Moon or Mars) and limited gas exchange hamper plant growth. Studying the effects of reduced gravity on plants requires real or simulated microgravity experiments under highly standardized conditions, in order to avoid the influence of other environmental factors. Analysis of a large number of biological replicates, which is necessary for the detection of subtle phenotypical differences, can so far only be achieved in Ground Based Facilities (GBF). Besides different experimental conditions, the usage of a variety of different plant growth chambers was a major factor that led to a lack of reproducibility and comparability in previous studies. We have developed a flexible and customizable plant growth chamber, called ARAbidopsis DISH (ARADISH), which allows plant growth from seed to seedling, being realized in a hydroponic system or on Agar. By developing a special holder, the ARADISH can be used for experiments with Arabidopsis thaliana or a plant with a similar habitus on common GBF hardware, including 2D clinostats and Random Positioning Machines (RPM). The ARADISH growth chamber has a controlled illumination system of red and blue light emitting diodes (LED), which allows the user to apply defined light conditions. As a proof of concept we tested a prototype in a proteomic experiment in which plants were exposed to simulated microgravity or a 90° stimulus. We optimized the design and performed viability tests after several days of growth in the hardware that underline the utility of ARADISH in microgravity research.

  2. Researches at hadron experiment facility

    International Nuclear Information System (INIS)

    Sawada, Shinya

    2006-01-01

    Some of the nuclear, hadron and elementary particle experiments proposed to hadron experiment facility to use the extracted slow proton beam at J-PARC are overviewed. Characteristic feature of the facility is the secondary beam obtained from the intense proton beam. Nuclear hadron physics experiments and kaon rare decay experiments are presented here as the typical ones. Hypernuclear spectroscopy with S=-2 state is expected to be started as soon as the beam becomes available. The kaon bound systems not only with three nucleons like K-pnn but also more numerous like Li and Be are to be studied systematically. Bound states of two kaons using (K - , K + ) reaction will be challenged. Pentaquark will be searched for and its properties will be studied if it really exists. Nuclear structure studies from the view point of large Bjorken x are planned to be studied by irradiating hydrogen, deuteron or heavier targets with primary proton beam and analyzing generated muon pairs. Properties of vector mesons in nuclear matter are to be studied with the primary beam. Neutral kaon rare decay will be investigated to study CP nonconservation. Large progress of elementary particle physics is anticipated by using the intense proton beam at J-PARC. (S. Funahashi)

  3. Material Processing Facility - Skylab Experiment M512

    Science.gov (United States)

    1972-01-01

    This chart details Skylab's Materials Processing Facility experiment (M512). This facility, located in the Multiple Docking Adapter, was developed for Skylab and accommodated 14 different experiments that were carried out during the three marned missions. The abilities to melt and mix without the contaminating effects of containers, to suppress thermal convection and buoyancy in fluids, and to take advantage of electrostatic and magnetic forces and otherwise masked by gravitation opened the way to new knowledge of material properties and processes. This beginning would ultimately lead to the production of valuable new materials for use on Earth.

  4. Facility for electron cooling experiments

    International Nuclear Information System (INIS)

    Budker, G.I.; Dikanskij, N.S.; Kudelajnen, V.I.

    1982-01-01

    The NAP-M proton storage ring intended for electron cooling experiments is described. The NAP-M magnetic system comprises four bending magnets and eight correction elements. located at the ends of rectilinear gaps. An electron beam facility is located in one of the rectilinear gaps. An 1.5 MeV electrostatic accelerator is used as a proton injector. The NAP-M accelerating system includes a driving generator, a power amplifier and a resonator. The proton beam lifetime (at the RF-system switched-off) up to 7 s has been obtained at the NAP-N at the injection energy, and up to 600 s at 65 MeV and the proton current of 120 μA

  5. NTES laser facility for physics experiments

    International Nuclear Information System (INIS)

    Christie, D.J.; Foley, R.J.; Frank, D.N.

    1989-01-01

    This paper discusses the following topics on the NTES laser facility: Mission Statement and Project Description; Experiment Area; High-Energy, Double-Pass Laser; Facilities; Laser Control and Data Acquisition; and Auxiliary Lasers

  6. The Burning Plasma Experiment conventional facilities

    International Nuclear Information System (INIS)

    Commander, J.C.

    1991-01-01

    The Burning Program Plasma Experiment (BPX) is phased to start construction of conventional facilities in July 1994, in conjunction with the conclusion of the Tokamak Fusion Test Reactor (TFTR) project. This paper deals with the conceptual design of the BPX Conventional Facilities, for which Functional and Operational Requirements (F ampersand ORs) were developed. Existing TFTR buildings and utilities will be adapted and used to satisfy the BPX Project F ampersand ORs to the maximum extent possible. However, new conventional facilities will be required to support the BPX project. These facilities include: The BPX building; Site improvements and utilities; the Field Coil Power Conversion (FCPC) building; the TFTR modifications; the Motor Generation (MG) building; Liquid Nitrogen (LN 2 ) building; and the associated Instrumentation and Control (I ampersand C) systems. The BPX building will provide for safe and efficient shielding, housing, operation, handling, maintenance and decontamination of the BPX and its support systems. Site improvements and utilities will feature a utility tunnel which will provide a space for utility services--including pulse power duct banks and liquid nitrogen coolant lines. The FCPC building will house eight additional power supplied for the Toroidal Field (TF) coils. The MG building will house the two MG sets larger than the existing TFTR MG sets. This paper also addresses the conventional facility cost estimating methodology and the rationale for the construction schedule developed. 6 figs., 1 tab

  7. 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.

  8. 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

  9. 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.

  10. 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

  11. 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.

  12. LMFBR safety experiment facility planning and analysis

    International Nuclear Information System (INIS)

    Stevenson, M.G.; Scott, J.H.

    1976-01-01

    In the past two years considerable effort has been placed on the planning and design of new facilities for the resolution of LMFBR safety issues. The paper reviews the key issues, the experiments needed to resolve them, and the design aspects of proposed new facilities. In addition, it presents a decision theory approach to selecting an optimal combination of modified and new facilities

  13. Material science experiments on the Atlas Facility

    International Nuclear Information System (INIS)

    Keinigs, Rhonald K.; Atchison, Walter L.; Faehl, Rickey J.; Lindemuth, Irvin R.; Anderson, Wallace E.; Bartsch, Robert Richard; Flower-Maudlin, Elane C.; Hammerberg, James E.; Holtkamp, David B.; Jones, Michael E.; Kyrala, George A.; Oro, David M.; Parker, Jerald V.; Preston, Dean L.; Reinovsky, Robert E.; Scudder, David W.; Sheehey, Peter T.; Shlacter, Jack S.; Stokes, John L.; Taylor, Antoinette J.; Tonks, Davis L.; Turchi, Peter J.

    2001-01-01

    Three material properties experiments that are to be performed on the Atlas pulsed power facility are described; friction at sliding metal interfaces, spallation and damage in convergent geomety, and plastic flow at high strain and high strain rate. Construction of this facility has been completed and experiments in high energy density hydrodynamics and material dynamics will begin in 2001.

  14. Evaluation of advanced driver assistance system with the VEHIL test facility: experiences and future developments at TNO automotive

    NARCIS (Netherlands)

    Kusters, L.J.J.; Gietelink, O.J.; Hoof, J.F.A.M. van; Lemmen, P.P.M.

    2004-01-01

    This paper presents the working principle, functionality and the experience during the first operational period of the VEHIL laboratory, dedicated to the development and testing of advanced driver assistance systems. The position of VEHIL and its PC based full software variant PRESCAN is illustrated

  15. Thermal-Hydraulic Experiment Facility (THEF)

    International Nuclear Information System (INIS)

    Martinell, J.S.

    1982-01-01

    This paper provides an overview of the Thermal-Hydraulic Experiment Facility (THEF) at the Idaho National Engineering Laboratory (INEL). The overview describes the major test systems, measurements, and data acquisition system, and presents objectives, facility configuration, and results for major experimental projects recently conducted at the THEF. Plans for future projects are also discussed. The THEF is located in the Water Reactor Research Test Facility (WRRTF) area at the INEL

  16. Developing confidence in a coupled TH model based on the results of experiment by using engineering scale test facility, 'COUPLE'

    International Nuclear Information System (INIS)

    Fujisaki, Kiyoshi; Suzuki, Hideaki; Fujita, Tomoo

    2008-03-01

    It is necessary to understand quantitative changes of near-field conditions and processes over time and space for modeling the near-field evolution after emplacement of engineered barriers. However, the coupled phenomena in near-field are complicated because thermo-, hydro-, mechanical, chemical processes will interact each other. The question is, therefore, whether the applied model will represent the coupled behavior adequately or not. In order to develop confidence in the modeling, it is necessary to compare with results of coupled behavior experiments in laboratory or in site. In this report, we evaluated the applicability of a coupled T-H model under the conditions of simulated near-field for the results of coupled T-H experiment in laboratory. As a result, it has been shown that the fitting by the modeling with the measured data is reasonable under this condition. (author)

  17. Operating procedures: Fusion Experiments Analysis Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lerche, R.A.; Carey, R.W.

    1984-03-20

    The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility.

  18. Operating procedures: Fusion Experiments Analysis Facility

    International Nuclear Information System (INIS)

    Lerche, R.A.; Carey, R.W.

    1984-01-01

    The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility

  19. Tritium monitoring equipments for animal experiment facilities

    International Nuclear Information System (INIS)

    Sato, Hiroo

    1980-01-01

    Animal experiment facilities using tritium are described with reference to laws and regulations concerning radiological safety. Usual breeding facilities and surrounding conditions at non-radioactive animal experiments are summarized on feasible and effective designs of tritium monitors. Characteristics and desirable arrangements of various kinds of tritium monitors such as ionization chambers, proportional counters and liquid scintillation detectors are discussed from the standpoint of monitoring for room, glove-box, stack, liquid waste and personnel. (J.P.N.)

  20. Brookhaven Reactor Experiment Control Facility, a distributed function computer network

    International Nuclear Information System (INIS)

    Dimmler, D.G.; Greenlaw, N.; Kelley, M.A.; Potter, D.W.; Rankowitz, S.; Stubblefield, F.W.

    1975-11-01

    A computer network for real-time data acquisition, monitoring and control of a series of experiments at the Brookhaven High Flux Beam Reactor has been developed and has been set into routine operation. This reactor experiment control facility presently services nine neutron spectrometers and one x-ray diffractometer. Several additional experiment connections are in progress. The architecture of the facility is based on a distributed function network concept. A statement of implementation and results is presented

  1. Test facility for rewetting experiments at CDTN

    International Nuclear Information System (INIS)

    Rezende, Hugo C.; Mesquita, Amir Z.; Ladeira, Luiz C.D.; Santos, Andre A.C.

    2015-01-01

    One of the most important subjects in nuclear reactor safety analysis is the reactor core rewetting after a Loss-of-Coolant Accident (LOCA) in a Light Water Reactor LWR. Several codes for the prediction of the rewetting evolution are under development based on experimental results. In a Pressurized Water Reactor (PWR) the reflooding phase of a LOCA is when the fuel rods are rewetted from the bottom of the core to its top after having been totally uncovered and dried out. Out-of-pile reflooding experiments performed with electrical heated fuel rod simulators show different quench behavior depending the rods geometry. A test facility for rewetting experiments (ITR - Instalacao de Testes de Remolhamento) has been constructed at the Thermal Hydraulics Laboratory of the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), with the objective of performing investigations on basic phenomena that occur during the reflood phase of a LOCA in a PWR, using tubular and annular test sections. This paper presents the design aspects of the facility, and the current stage of the works. The mechanical aspects of the installation as its instrumentation are described. Two typical tests are presented and results compered with theoretical calculations using computer code. (author)

  2. Test facility for rewetting experiments at CDTN

    Energy Technology Data Exchange (ETDEWEB)

    Rezende, Hugo C.; Mesquita, Amir Z.; Ladeira, Luiz C.D.; Santos, Andre A.C., E-mail: hcr@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (SETRE/CDTN/CNEN-MG), Belo Horizonte, MG (Brazil). Servico de Tecnologia de Reatores

    2015-07-01

    One of the most important subjects in nuclear reactor safety analysis is the reactor core rewetting after a Loss-of-Coolant Accident (LOCA) in a Light Water Reactor LWR. Several codes for the prediction of the rewetting evolution are under development based on experimental results. In a Pressurized Water Reactor (PWR) the reflooding phase of a LOCA is when the fuel rods are rewetted from the bottom of the core to its top after having been totally uncovered and dried out. Out-of-pile reflooding experiments performed with electrical heated fuel rod simulators show different quench behavior depending the rods geometry. A test facility for rewetting experiments (ITR - Instalacao de Testes de Remolhamento) has been constructed at the Thermal Hydraulics Laboratory of the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), with the objective of performing investigations on basic phenomena that occur during the reflood phase of a LOCA in a PWR, using tubular and annular test sections. This paper presents the design aspects of the facility, and the current stage of the works. The mechanical aspects of the installation as its instrumentation are described. Two typical tests are presented and results compered with theoretical calculations using computer code. (author)

  3. YALINA-Thermal Facility Experiments

    International Nuclear Information System (INIS)

    Kiyavitskaya, H.; Bournos, V.; Fokov, Y.; Routkovskaya, C.; Sadovich, S.; Cintas, A.; Márquez Damián, J.I.; Lopasso, E.M.; Maiorino, J.R.; Carluccio, T.; Rossi, P.C.R.; Antunes, A.; Oliveira, F.L. de; Lee, S.M.; Xia, P.; Shi, Y.; Xia, H.; Zhu, Q.; Yu, T.; Wu, X.; Zhang, W.; Cao, J.; Luo, H.; Quan, Y.; Kulkarni, K.; Yadav, R.D.S.; Bajpai, A.; Degweker, S.B.; Modak, R.S.; Park, H.J.; Shim, H.J.; Kim, C.H.; Wojciechowski, A.; Zuta, M.; Pešić, M.; Avramović, I.; Beličev, P.; Gohar, Y.; Talamo, A.; Aliberti, G.

    2017-01-01

    This Section discussed the results obtained by the Member States participating in the IAEA coordinated research project on Analytical and Experimental Benchmark Analysis on Accelerator Driven Systems, and Low Enriched Uranium Fuel Utilization in Accelerator Driven Subcritical Assembly Systems for the YALINA Thermal facility. Member States used both Monte Carlo and deterministic computational tools to analyse the YALINA Thermal subcritical assembly, including: MCNP5, MCNPX, McCARD, PARTISN, and ERANOS computer programs. All calculations have been performed using the ENDF/B-VI (different modes) nuclear data libraries with the exception of Republic of Korea which used the ENDF/B-VII.0 nuclear data library. Generally, there is a good agreement between the results obtained by all the Member States. Deterministic codes perform space, energy, and angle discretization and materials homogenizations, which introduce approximations affecting the obtained results. In subcritical assemblies, the neutron multiplication and the detector counting rate depend strongly on the external neutron source. Cf and D-D sources provide similar results since they emit neutrons with similar average energy. D-T neutrons trigger (n,xn) reactions and have a longer mean free path, which increases the neutron leakage if the geometry dimensions of the assembly are small, as in the case of the YALINA-Thermal subcritical assembly. Close to criticality, the effect of the external neutron source diminishes since fission neutrons dominate the neutron population.

  4. Construction of STACY (Static Experiment Critical Facility)

    International Nuclear Information System (INIS)

    Murakami, Kiyonobu; Onodera, Seiji; Hirose, Hideyuki

    1998-08-01

    Two critical assemblies, STACY (Static Experiment Critical Facility) and TRACY (Transient Experiment Critical Facility), were constructed in NUCEF (Nuclear Fuel Cycle Safety Engineering Research Facility) to promote researches on the criticality safety at a reprocessing facility. STACY aims at providing critical data of uranium nitrate solution, plutonium nitrate solution and their mixture while varying concentration of solution fuel, core tank shape and size and neutron reflecting condition. STACY achieved first criticality in February 1995, and passed the licensing inspection by STA (Science and Technology Agency of Japan) in May. After that a series of critical experiments commenced with 10 w/o enriched uranium solution. This report describes the outline of STACY at the end of FY 1996. (author)

  5. Technical requirement of experiments and facilities for fusion nuclear technology

    International Nuclear Information System (INIS)

    Abdou, M.; Tillak, M.; Gierszwski, P.; Grover, J.; Puigh, R.; Sze, D.K.; Berwald, D.

    1986-06-01

    The technical issues and requirements of experiments and facilities for fusion nuclear technology (FNT) have been investigated. The nuclear subsystems addressed are: a) blanket, b) radiation shield, c) tritium processing system, and d) plasma interactive components. Emphasis has been placed on the important and complex development problems of the blanket. A technical planning process for FNT has been developed and applied, including four major elements: 1) characterization of issues, 2) quantification of testing requirements, 3) evaluation of facilities, and 4) development of a test plan to identify the role, timing, characteristics and costs of major experiments and facilities

  6. Nuclear astrophysics experiments with Pohang neutron facility

    International Nuclear Information System (INIS)

    Kim, Yeong Duk; Yoo, Gwang Ho

    1998-01-01

    Nuclear astrophysics experiments for fundamental understanding of Big Bang nucleosynthesis was performed at Pohang Neutron Facility. Laboratory experiments, inhomogeneous Big Bang nucleosynthesis and S-process were used for nucleosynthesis. For future study, more study on S-process for the desired data and nuclear network calculation are necessary

  7. Status of the low frequency facility experiment

    International Nuclear Information System (INIS)

    Bracci, L; Calamai, G; Cuoco, E; Dominici, P; Fabbroni, L; Guidi, G; Losurdo, G; Martelli, F; Mazzoni, M; Stanga, R; Vetrano, F; Porzio, A; Ricciardi, I; Solimeno, S; Ballardin, G; Braccini, S; Bradaschia, C; Casciano, C; Cavalieri, R; Cecchi, R; Cella, G; Dattilo, V; Virgilio, A Di; Fazzi, M; Ferrante, I; Fidecaro, F; Frasconi, F; Gennaro, G; Giazotto, A; Holloway, L; Penna, P La; Lomtadze, T; Nenci, F; Nicolosi, L; Lelli, F; Paoletti, F; Pasqualetti, A; Passaquieti, R; Passuello, D; Poggiani, R; Raffaelli, F; Taddei, R; Vicere, A; Zhang, Z; Frasca, S; Majorana, E; Palomba, C; Perciballi, M; Puppo, P; Rapagnani, P; Ricci, F

    2002-01-01

    The low frequency facility is a VIRGO R and D experiment having the goal of performing a direct measurement of the thermal noise of the VIRGO suspensions by means of a two-mirror Fabry-Perot cavity suspended to the last stage of the attenuating chain. The present status of advancement of this experiment is reported: the apparatus, including mechanical and optical parts, has been completely built and put into operation. Vacuum facilities and the first control loops are active. First measurements on the suspended cavity are in progress

  8. Status of the low frequency facility experiment

    Energy Technology Data Exchange (ETDEWEB)

    Bracci, L [Dipartimento di Fisica, Universita di Firenze, Florence (Italy); Calamai, G [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Cuoco, E [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Dominici, P [Dipartimento di Fisica, Universita di Firenze, Firenze (Italy); Fabbroni, L [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Guidi, G [Dipartimento di Fisica, Universita di Urbino, Urbino (Italy); Losurdo, G [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Martelli, F [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Mazzoni, M [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Stanga, R [Istituto Nazionale di Fisica Nucleare, Sez Firenze/Urbino (Italy); Vetrano, F [Dipartimento di Fisica, Universita di Urbino, Urbino (Italy); Porzio, A [Istituto Nazionale di Fisica Nucleare, Sez Naples (Italy); Ricciardi, I [Istituto Nazionale di Fisica Nucleare, Sez Naples (Italy); Solimeno, S [Istituto Nazionale di Fisica Nucleare, Sez Naples (Italy); Ballardin, G [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Braccini, S [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Bradaschia, C [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Casciano, C [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Cavalieri, R [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Cecchi, R [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Cella, G [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Dattilo, V [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Virgilio, A Di [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Fazzi, M [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Ferrante, I [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy); Fidecaro, F [Istituto Nazionale di Fisica Nucleare, Sez Pisa (Italy)] [and others

    2002-04-07

    The low frequency facility is a VIRGO R and D experiment having the goal of performing a direct measurement of the thermal noise of the VIRGO suspensions by means of a two-mirror Fabry-Perot cavity suspended to the last stage of the attenuating chain. The present status of advancement of this experiment is reported: the apparatus, including mechanical and optical parts, has been completely built and put into operation. Vacuum facilities and the first control loops are active. First measurements on the suspended cavity are in progress.

  9. Characterizing experiments of the PPOOLEX test facility

    Energy Technology Data Exchange (ETDEWEB)

    Puustinen, M.; Laine, J. (Lappeenranta Univ. of Technology, Nuclear Safety Research Unit (Finland))

    2008-07-15

    This report summarizes the results of the characterizing test series in 2007 with the scaled down PPOOLEX facility designed and constructed at Lappeenranta University of Technology. Air and steam/air mixture was blown into the dry well compartment and from there through a DN200 blowdown pipe to the condensation pool (wet well). Altogether eight air and four steam/air mixture experiments, each consisting of several blows (tests), were carried out. The main purpose of the experiment series was to study the general behavior of the facility and the performance of basic instrumentation. Proper operation of automation, control and safety systems was also tested. The test facility is a closed stainless steel vessel divided into two compartments, dry well and wet well. The facility is equipped with high frequency measurements for capturing different aspects of the investigated phenomena. The general behavior of the PPOOLEX facility differs significantly from that of the previous POOLEX facility because of the closed two-compartment structure of the test vessel. Heat-up by several tens of degrees due to compression in both compartments was the most obvious evidence of this. Temperatures also stratified. Condensation oscillations and chugging phenomenon were encountered in those tests where the fraction of non-condensables had time to decrease significantly. A radical change from smooth condensation behavior to oscillating one occurred quite abruptly when the air fraction of the blowdown pipe flow dropped close to zero. The experiments again demonstrated the strong diminishing effect that noncondensable gases have on dynamic unsteady loadings experienced by submerged pool structures. BWR containment like behavior related to the beginning of a postulated steam line break accident was observed in the PPOOLEX test facility during the steam/air mixture experiments. The most important task of the research project, to produce experimental data for code simulation purposes, can be

  10. 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.

  11. 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

  12. Safety Research Experiment Facility Project. Conceptual design report. Volume II. Building and facilities

    International Nuclear Information System (INIS)

    1975-12-01

    The conceptual design of Safety Research Experiment Facility (SAREF) site system includes a review and evaluation of previous geotechnical reports for the area where SAREF will be constructed and the conceptual design of access and in-plant roads, parking, experiment-transport-vehicle maneuvering areas, security fencing, drainage, borrow area development and restoration, and landscaping

  13. Overview - Defense Waste Processing Facility Operating Experience

    International Nuclear Information System (INIS)

    Norton, M.R.

    2002-01-01

    The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the world's largest radioactive waste vitrification facility. Radioactive operations began in March 1996 and over 1,000 canisters have been produced. This paper presents an overview of the DWPF process and a summary of recent facility operations and process improvements. These process improvements include efforts to extend the life of the DWPF melter, projects to increase facility throughput, initiatives to reduce the quantity of wastewater generated, improved remote decontamination capabilities, and improvements to remote canyon equipment to extend equipment life span. This paper also includes a review of a melt rate improvement program conducted by Savannah River Technology Center personnel. This program involved identifying the factors that impacted melt rate, conducting small scale testing of proposed process changes and developing a cost effective implementation plan

  14. 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

  15. FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume III

    Energy Technology Data Exchange (ETDEWEB)

    Abdou, M.

    1984-10-01

    This chapter deals with the analysis and engineering scaling of solid breeded blankets. The limits under which full component behavior can be achieved under changed test conditions are explored. The characterization of these test requirements for integrated testing contributes to the overall test matrix and test plan for the understanding and development of fusion nuclear technology. The second chapter covers the analysis and engineering scaling of liquid metal blankets. The testing goals for a complete blanket program are described. (MOW)

  16. Critical experiment study on uranyl nitrate solution experiment facility

    International Nuclear Information System (INIS)

    Zhu Qingfu; Shi Yongqian; Wang Jinrong

    2005-01-01

    The Uranyl Nitrate Solution Experiment Facility was constructed for the research on nuclear criticality safety. In this paper, the configuration of the facility is introduced; a series of critical experiments on uranyl nitrate solution is described later, which were performed for various uranium concentrations under different conditions, i.e. with or without neutron absorbers in the core and with or without water-reflector outside the core. Critical volume and the minimum 235U critical mass for different uranium concentrations are presented. Finally, theoretical analysis is made on the experimental results. (authors)

  17. Operating experience of steam generator test facility

    International Nuclear Information System (INIS)

    Sureshkumar, V.A.; Madhusoodhanan, G.; Noushad, I.B.; Ellappan, T.R.; Nashine, B.K.; Sylvia, J.I.; Rajan, K.K.; Kalyanasundaram, P.; Vaidyanathan, G.

    2006-01-01

    Steam Generator (SG) is the vital component of a Fast Reactor. It houses both water at high pressure and sodium at low pressure separated by a tube wall. Any damage to this barrier initiates sodium water reaction that could badly affect the plant availability. Steam Generator Test Facility (SGTF) has been set up in Indira Gandhi Centre for Atomic Research (IGCAR) to test sodium heated once through steam generator of 19 tubes similar to the PFBR SG dimension and operating conditions. The facility is also planned as a test bed to assess improved designs of the auxiliary equipments used in Fast Breeder Reactors (FBR). The maximum power of the facility is 5.7 MWt. This rating is arrived at based on techno economic consideration. This paper covers the performance of various equipments in the system such as Electro magnetic pumps, Centrifugal sodium pump, in-sodium hydrogen meters, immersion heaters, and instrumentation and control systems. Experience in the system operation, minor modifications, overall safety performance, and highlights of the experiments carried out etc. are also brought out. (author)

  18. 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.

  19. Material science experiments at the ATLAS facility

    CERN Document Server

    Keinigs, R K; Atchison, W L; Bartsch, R R; Faehl, R J; Flower-Maudlin, E C; Hammerberg, J E; Holtkamp, D B; Kyrala, G A; Oro, D M; Parker, J V; Preston, D L; Removsky, R E; Scudder, D W; Sheehey, P T; Shlachter, J S; Taylor, A J; Tonks, D L; Turchi, P J; Chandler, E A

    2001-01-01

    Summary form only given, as follows. Three experimental campaigns designed for fielding on the Atlas Pulsed Power Facility are discussed. The foci of these experiments are directed toward a better understanding of three material science issues; (1) strength at high strain and high strain rate, (2) friction at material interfaces moving at high relative velocities, and (3) material failure in convergent geometry. Atlas provides an environment for investigating these problems in parameter regimes and geometries that are inaccessible with standard techniques. For example, flow stress measurements of material strength using conventional Hopkinson bar experiments are limited to strain rates ~10/sup 4/ sec/sup -1/. Atlas will be capable of imploding metal shells to combined strains of 200% and strain rates >10/sup 6/ sec/sup -1/. Data obtained regimes is used to test different constitutive strength models used in several Los Alamos hydrocodes. Dynamic friction has been investigated for nearly 300 years, but a first...

  20. Operating manual for the critical experiments facility

    International Nuclear Information System (INIS)

    1986-01-01

    The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written

  1. Operating manual for the critical experiments facility

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written.

  2. 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

  3. UCN-VCN facility and experiments in Kyoto University Reactor

    International Nuclear Information System (INIS)

    Kawabata, Yuji; Okumura, Kiyoshi; Utsuro, Masahiko

    1993-01-01

    An ultracold and very cold neutron facility was installed in Kyoto University Reactor (KUR). The facility consists of a very cold neutron (VCN) guide tube, a VCN bender, a supermirror neutron turbine and experimental equipments with ultracold neutrons (UCN). The properties of each equipments are presented. UCN is generated by a supermirror neutron turbine combined with the cold neutron source operated with liquid deuterium, and the UCN output spectrum was measured by the time-of-flight method. A gravity analyzer for high resolution spectroscopy and a neutron bottle for decay experiments are now developing as the UCN research in KUR. (author)

  4. High temperature engineering research facilities and experiments in Russia

    International Nuclear Information System (INIS)

    Kodochigov, N.G.; Kuzavkov, N.G.; Sukharev, Y.P.; Chudin, A.G.

    1998-01-01

    An overview is given of the characteristics of the experimental facilities and experiments in the Russian Federation: the HTGR neutron-physical investigation facilities ASTRA and GROG; facilities for fuel, graphite and other elements irradiation; and thermal hydraulics experimental facilities. The overview is presented in the form of copies of overhead sheets

  5. Operational experience at the Sludge Treatment Facility

    International Nuclear Information System (INIS)

    Sy, D.J.

    1987-01-01

    The Sludge Treatment Facility (STF) at the Oak Ridge Gaseous Diffusion Plant has been in operation since April 1987. The facility was designed to encapsulate hazardous sludge wastes in a cement matrix. Fixation will allow the waste to meet or exceed applicable compressive strength and leachability requirements. Thus, the grout mixture complies with the Resource Conservation and Recovery Act (RCRA) guidelines as a nonhazardous waste. The grout mixture is based upon a recipe formulation developed after several years of waste stream characterization and formulation studies. The wastes to be treated at the STF are wastes impounded in two ponds. The ponds have a combined capacity of 4.5 million gallons of sludge. The sludge is transferred from the ponds to a 15,000-gallon capacity storage tank by the use of a dredge. The grout mixture recipe dictates the amount of sludge, cement, fly ash, and admixture required for weighing per batch. All ingredients are weighed and then transferred to a tilt or high energy mixer for mixing. The grout mixture is then transferred to 89- or 96-gallon steel drums. The drums are placed in a storage yard designed for a point source discharge from the yard

  6. Operational experience of gamma radiation processing facility

    International Nuclear Information System (INIS)

    Patel, Nilesh

    2014-01-01

    Universal lSO-MED is now proud to announce an extension of its irradiation service for low-dose applications specifically in agriculture commodities, food and healthcare applications with the start of Gujarat Agro Radiation Processing Facility at Village: Bavla, Ahmedabad (A Government Enterprise) Operated, Maintained and Managed by Universal Medicap Ltd. Availability of hygienic, safe and nutritious food commodities is essential for any sustainable human development. Food stability is an important element of economic stability and self-reliance of a nation. Though the need to preserve food has been felt by the mankind since the time immemorial, it is even stronger in today's context. The rising population and increasing gap between demand and supply, agro-climatic conditions, in adequate post-harvest practices, seasonal nature of produce and long distances between production and consumption centers underscore the need to device improved conservation and preservation strategies

  7. 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)

  8. Licensing of ''grandfather's'' facilities: Ukrainian experience

    International Nuclear Information System (INIS)

    Mikolaitchouk, H.; Bogdan, L.; Steinberg, N.

    1995-01-01

    In the former USSR, unlike most countries, radioactive waste management activities including waste disposal needed no license. But after the USSR breakdown the Ukrainian Parliament -- Verkhovna Rada -- invoked the revised Law on Business activities. According to Article 4 of the Law, in order to treat or to dispose radioactive waste every enterprise has to get a special permission or license. In compliance with the Law, the Cabinet of Ministers by its Ordinance of January 13, 1993, authorized the Ukrainian State Committee for Nuclear and Radiation Safety (UkrSCNRS) to issue special permissions or licenses for waste treatment and disposal. And that requirement was valid not only for future activities but also for existing facilities in operation. Taking into account the undergoing legislative process, SCNRS began to develop its licensing process without waiting for the special nuclear laws to be passed. On the basis of the legislation already in effect, first of all the Law on Enterprises (full responsibility of enterprises for their activities) and Law on Business activities (requirement to have a license for special types of activities), the newly formed national regulatory body had to identify all the enterprises that needed to be licensed, to establish relevant procedures, to develop related regulatory documents, to implement these procedures and documents at operating enterprises, and for each case to make a decision concerning feasibility of issuing a license, period of validity and license conditions

  9. Laser heated solenoid proof-of-concept experiment (PCX) facility

    International Nuclear Information System (INIS)

    DeHart, T.E.; Zumdieck, J.F.; Hoffman, A.L.; Lowenthal, D.D.; Crawford, E.A.; Parry, B.

    1977-01-01

    The total facility, including laser, magnet, focusing optics, instrumentation and control, its design problems, and its current performance are discussed. Preliminary results from plasma heating experiments are discussed

  10. Lessons learned from international siting experiences of LLW Disposal facilities

    International Nuclear Information System (INIS)

    McCabe, G.H.

    1990-01-01

    This paper reports that the United States can gain insight into successfully siting low-level radioactive waste (LLW) disposal facilities by studying the process in other nations. Siting experiences in France and Sweden are compared to experiences in the United States. Three factors appear to making siting of LLW disposal facilities easier in France and Sweden than in the United States. First, the level of public trust in the government and the entities responsible for siting, developing, and operating a LLW disposal facility is much greater in France and Sweden than in the United States. Second, France and Sweden are much more dependent on nuclear power than is the United States. Third, French and Swedish citizens do not have the same access to the siting process (i.e., legal means to intervene) as do U.S. citizens. To compensate for these three factors, public officials responsible for siting a facility may need to better listen to the concerns of public interest groups and citizen advisory committees and amend their siting process accordingly and better share power and control with the public. If these two techniques are implemented earnestly by the states, siting efforts may be increasingly more successful in the United States

  11. 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

  12. A PMT mass testing facility for the JUNO experiment

    Energy Technology Data Exchange (ETDEWEB)

    Tietzsch, Alexander; Alsheimer, Isabell; Blum, David; Lachenmaier, Tobias; Sterr, Tobias [Physikalisches Institut, Universitaet Tuebingen (Germany); Bein, Bosse; Bick, Daniel; Ebert, Joachim; Hagner, Caren; Rebber, Henning; Steppat, Lisa; Wonsak, Bjoern [Institut fuer Experimentalphysik, Universitaet Hamburg (Germany)

    2016-07-01

    The JUNO (Jiangmen Underground Neutrino Observatory) experiment will be one of the big neutrino oscillation experiments starting in the next years. The main goal of JUNO is the determination of the neutrino mass hierarchy. To detect the sub-dominant effects in the oscillation pattern which depend on the mass hierarchy, the JUNO detector is planned with almost 20 kt fiducial volume, high light yield and energy resolution of better than 3%. In order to reach this, roughly 17000 newly developed high QE PMTs for the central detector, and additionally 2000 for the veto will be used. Each PMT has to be tested and characterized before it will be mounted in the experiment. This talk gives an overview on our plans and strategy for the mass test of all PMTs, and on the current status of the experimental test setup and next steps. The testing facility is developed in a cooperation between the Physical Institutes in Tuebingen and Hamburg within the JUNO collaboration.

  13. Development, simulation and test of transition radiation detector prototypes for the compressed baryonic matter experiment at the facility for antiproton and ion research

    Energy Technology Data Exchange (ETDEWEB)

    Bergmann, Cyrano S.H.

    2014-07-01

    prototype materials were chosen with special focus on performance and mechanical stability. All eligible materials have been simulated in full radiator parameter space (γ, l{sub 1}, l{sub 2} and N{sub f}) to find optimal materials and parameters with respect to the TR-photon absorption characteristic of the chamber. The best candidates were built in small scales and the simulations were compared to measurements. It was found that the regular radiator model is sufficient to describe all measurements between 2 and 8 GeV/c, if extended by a material dependent constant scaling factor. At the same time, this model is inadequate in case of irregular radiators. The two best radiator candidates for CBM TRD are a micro-structured self-supporting POKALON foil radiator and a foam foil radiator, reaching the PID design goal with at least five to six detector hits per track. The chamber geometry was implemented in the simulation framework (CbmRoot) of the CBM experiment. The measured charge spectra for electrons including TR-photons were reproduced based on a regular radiator model for all tested prototypes, in order to provide a realistic input for the TRD in the simulation. For the first time the TRD simulation includes a realistic detector response simulation and clusterization. In summary, the new real-size TRD prototype providing electron/pion discrimination and tracking of charged particles in high counting rate environments was developed. It was demonstrated that they fulfill the requirements of the CBM experiment at the FAIR facility in terms of particle identification. A final test with respect to the performance in a high counting rate environment has still to be performed. The results encourage the further development of this new design principle for a TRD for the CBM experiment. Based on the prototype performance demonstrated in this thesis, a new generation of TRD prototypes has been developed and is currently under construction.

  14. Development, simulation and test of transition radiation detector prototypes for the compressed baryonic matter experiment at the facility for antiproton and ion research

    International Nuclear Information System (INIS)

    Bergmann, Cyrano S.H.

    2014-01-01

    special focus on performance and mechanical stability. All eligible materials have been simulated in full radiator parameter space (γ, l 1 , l 2 and N f ) to find optimal materials and parameters with respect to the TR-photon absorption characteristic of the chamber. The best candidates were built in small scales and the simulations were compared to measurements. It was found that the regular radiator model is sufficient to describe all measurements between 2 and 8 GeV/c, if extended by a material dependent constant scaling factor. At the same time, this model is inadequate in case of irregular radiators. The two best radiator candidates for CBM TRD are a micro-structured self-supporting POKALON foil radiator and a foam foil radiator, reaching the PID design goal with at least five to six detector hits per track. The chamber geometry was implemented in the simulation framework (CbmRoot) of the CBM experiment. The measured charge spectra for electrons including TR-photons were reproduced based on a regular radiator model for all tested prototypes, in order to provide a realistic input for the TRD in the simulation. For the first time the TRD simulation includes a realistic detector response simulation and clusterization. In summary, the new real-size TRD prototype providing electron/pion discrimination and tracking of charged particles in high counting rate environments was developed. It was demonstrated that they fulfill the requirements of the CBM experiment at the FAIR facility in terms of particle identification. A final test with respect to the performance in a high counting rate environment has still to be performed. The results encourage the further development of this new design principle for a TRD for the CBM experiment. Based on the prototype performance demonstrated in this thesis, a new generation of TRD prototypes has been developed and is currently under construction.

  15. Large scale FCI experiments in subassembly geometry. Test facility and model experiments

    International Nuclear Information System (INIS)

    Beutel, H.; Gast, K.

    A program is outlined for the study of fuel/coolant interaction under SNR conditions. The program consists of a) under water explosion experiments with full size models of the SNR-core, in which the fuel/coolant system is simulated by a pyrotechnic mixture. b) large scale fuel/coolant interaction experiments with up to 5kg of molten UO 2 interacting with liquid sodium at 300 deg C to 600 deg C in a highly instrumented test facility simulating an SNR subassembly. The experimental results will be compared to theoretical models under development at Karlsruhe. Commencement of the experiments is expected for the beginning of 1975

  16. Experiments with the HORUS-II test facility

    Energy Technology Data Exchange (ETDEWEB)

    Alt, S.; Lischke, W. [Univ. for Applied Sciences Zittau/Goerlitz, Zittau (Germany). Dept. of Nuclear Engineering

    1997-12-31

    Within the scope of the German reactor safety research the thermohydraulic computer code ATHLET which was developed for accident analyses of western nuclear power plants is more and more used for the accident analysis of VVER-plants particularly for VVER-440,V-213. The experiments with the HORUS-facilities and the analyses with the ATHLET-code have been realized at the Technical University Zittau/Goerlitz since 1991. The aim of the investigations was to improve and verify the condensation model particularly the correlations for the calculation of the heat transfer coefficients in the ATHLET-code for pure steam and steam-noncondensing gas mixtures in horizontal tubes. About 130 condensation experiments have been performed at the HORUS-II facility. The experiments have been carried out with pure steam as well as with noncondensing gas injections into the steam mass flow. The experimental simulations are characterized as accident simulation tests for SBLOCA for VVER-conditions. The simulation conditions had been adjusted correspondingly to the parameters of a postulated SBLOCA`s fourth phase at the original plant. 4 refs.

  17. Online remote monitoring facilities for the ATLAS experiment

    CERN Document Server

    Kolos, S; The ATLAS collaboration; Feng, E; Hauser, R; Yakovlev, A; Zaytsev, A

    2011-01-01

    ATLAS is one of the 4 LHC experiments which started to be operated in the collisions mode in 2010. The ATLAS apparatus itself as well as the Trigger and the DAQ system are extremely complex facilities which have been built up by the collaboration including 144 institutes from 33 countries. The effective running of the experiment is supported by a large number of experts distributed all over the world. This paper describes the online remote monitoring system which has been developed in the ATLAS Trigger and DAQ(TDAQ) community in order to support efficient participation of the experts from remote institutes in the exploitation of the experiment. The facilities provided by the remote monitoring system are ranging from the WEB based access to the general status and data quality for the ongoing data taking session to the scalable service providing real-time mirroring of the detailed monitoring data from the experimental area to the dedicated computers in the CERN public network, where this data is made available ...

  18. Online remote monitoring facilities for the ATLAS experiment

    CERN Document Server

    Kolos, S; The ATLAS collaboration; Feng, E; Hauser, R; Yakovlev, A; Zaytsev, A

    2010-01-01

    ATLAS is one of the 4 LHC experiments which started to be operated in the collisions mode in 2010. The ATLAS apparatus itself as well as the Trigger and the DAQ system are extremely complex facilities which have been built up by the collaboration including 144 institutes from 33 countries. The effective running of the experiment is supported by a large number of experts distributed all over the world. This paper describes the online remote monitoring system which has been developed in the ATLAS TDAQ community in order to support efficient participation of the experts from remote institutes in the exploitation of the experiment. The facilities provided by the remote monitoring system are ranging from the WEB based access to the general status and data quality for the ongoing data taking session to the scalable service providing real-time mirroring of the detailed monitoring data from the experimental area to the dedicated computers in the CERN public network, where this data is made available to remote users t...

  19. Experiments with the HORUS-II test facility

    Energy Technology Data Exchange (ETDEWEB)

    Alt, S; Lischke, W [Univ. for Applied Sciences Zittau/Goerlitz, Zittau (Germany). Dept. of Nuclear Engineering

    1998-12-31

    Within the scope of the German reactor safety research the thermohydraulic computer code ATHLET which was developed for accident analyses of western nuclear power plants is more and more used for the accident analysis of VVER-plants particularly for VVER-440,V-213. The experiments with the HORUS-facilities and the analyses with the ATHLET-code have been realized at the Technical University Zittau/Goerlitz since 1991. The aim of the investigations was to improve and verify the condensation model particularly the correlations for the calculation of the heat transfer coefficients in the ATHLET-code for pure steam and steam-noncondensing gas mixtures in horizontal tubes. About 130 condensation experiments have been performed at the HORUS-II facility. The experiments have been carried out with pure steam as well as with noncondensing gas injections into the steam mass flow. The experimental simulations are characterized as accident simulation tests for SBLOCA for VVER-conditions. The simulation conditions had been adjusted correspondingly to the parameters of a postulated SBLOCA`s fourth phase at the original plant. 4 refs.

  20. Experiments with the HORUS-II test facility

    International Nuclear Information System (INIS)

    Alt, S.; Lischke, W.

    1997-01-01

    Within the scope of the German reactor safety research the thermohydraulic computer code ATHLET which was developed for accident analyses of western nuclear power plants is more and more used for the accident analysis of VVER-plants particularly for VVER-440,V-213. The experiments with the HORUS-facilities and the analyses with the ATHLET-code have been realized at the Technical University Zittau/Goerlitz since 1991. The aim of the investigations was to improve and verify the condensation model particularly the correlations for the calculation of the heat transfer coefficients in the ATHLET-code for pure steam and steam-noncondensing gas mixtures in horizontal tubes. About 130 condensation experiments have been performed at the HORUS-II facility. The experiments have been carried out with pure steam as well as with noncondensing gas injections into the steam mass flow. The experimental simulations are characterized as accident simulation tests for SBLOCA for VVER-conditions. The simulation conditions had been adjusted correspondingly to the parameters of a postulated SBLOCA's fourth phase at the original plant

  1. 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

  2. Recent operational experiments at the LANSCE facility

    Energy Technology Data Exchange (ETDEWEB)

    Rybarcyk, Lawrence J [Los Alamos National Laboratory

    2010-09-15

    The Los Alamos Neutron Science Center (LANSCE) consists of a pulsed 800-MeV room-temperature linear accelerator and an 800-MeV accumulator ring. It simultaneously provides H{sup +} and H{sup -} beams to several user facilities that have their own distinctive requirements, e.g. intensity, chopping pattern, duty factor, etc.. This multibeam operation presents challenges both from the standpoint of meeting the individual requirements but also achieving good overall performance for the integrated operation. Various aspects of more recent operations including the some of these challenges will be discussed.

  3. 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

  4. Construction of new critical experiment facilities in JAERI

    International Nuclear Information System (INIS)

    Takeshita, Isao; Itahashi, Takayuki; Ogawa, Kazuhiko; Tonoike, Kotaro; Matsumura, Tatsuro; Miyoshi, Yoshinori; Nakajima, Ken; Izawa, Naoki

    1995-01-01

    Japan Atomic Energy Research Institute (JAERI) has promoted the experiment research program on criticality safety since early in 1980s and two types of new critical facilities, Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) were completed on 1994 in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) of JAERI Tokai Research Establishment. STACY was designed so as to obtain critical mass data of low enriched uranium and plutonium solution which is extensively handled in LWR fuel reprocessing plant. TRACY is the critical facility where critical accident phenomenon is demonstrated with low enriched uranium nitrate solution. For criticality safety experiments with both facilities, the Fuel Treatment System is attached to them, where composition and concentration of uranium and plutonium nitrate solutions are widely varied so as to obtain experiments data covering fuel solution conditions in reprocessing plant. Design performances of both critical facilities were confirmed through mock-up tests of important components and cold function tests. Hot function test has started since January of 1995 and some of the results on STACY are to be reported. (author)

  5. An overview of experiments at the Indiana University Cyclotron Facility

    International Nuclear Information System (INIS)

    Foster, C.C.

    1981-01-01

    The research program of the Indiana University Cyclotron Facility (IUCF) is a product of many factors. Among these factors are the properties of the beams of charged particles available from the cyclotrons, the facilities and personnel available to support experiments, the guidance of the Program Advisory Committee, the decisions of the directors and the ideas and work of the users of the facility. It is the author's purpose, in this brief overview paper, to provide a summary of features and properties of accelerator operation, beams, experimental facilities and the user interaction of interest to a perspective experimental user and a discussion of recent results of measurements made at IUCF

  6. Testing experience with fast flux test facility

    International Nuclear Information System (INIS)

    Noordhoff, B.H.; McGough, C.B.; Nolan, J.E.

    1975-01-01

    Early FFTF project planning emphasized partial and full-scale testing of major reactor and plant prototype components under expected environmental conditions, excluding radiation fields. Confirmation of component performance during FFTF service was considered essential before actual FFTF startup, to provide increased assurance against FFTF startup delays or operational difficulties and downtime. Several new sodium facilities were constructed, and confirmation tests on the prototype components are now in progress. Test conditions and results to date are reported for the primary pump, intermediate heat exchanger, sodium-to-air dump heat exchanger, large and small sodium valves, purification cold trap, in-vessel handling machine, instrument tree, core restraint, control rod system, low-level flux monitor, closed loop ex-vessel machine, refueling equipment, and selected maintenance equipment. The significance and contribution of these tests to the FFTF and Liquid Metal Fast Breeder Reactor (LMFBR) program are summarized. (U.S.)

  7. Electron beam facility for divertor target experiments

    International Nuclear Information System (INIS)

    Anisimov, A.; Gagen-Torn, V.; Giniyatulin, R.N.

    1994-01-01

    To test different concepts of divertor targets and bumpers an electron beam facility was assembled in Efremov Institute. It consists of a vacuum chamber (3m 3 ), vacuum pump, electron beam gun, manipulator to place and remove the samples, water loop and liquid metal loop. The following diagnostics of mock-ups is stipulated: (1) temperature distribution on the mock-up working surface (scanning pyrometer and infra-red imager); (2) temperature distribution over mocked-up thickness in 3 typical cross-sections (thermo-couples); (3) cracking dynamics during thermal cycling (acoustic-emission method), (4) defects in the mock-up before and after tests (ultra-sonic diagnostics, electron and optical microscopes). Carbon-based and beryllium mock-ups are made for experimental feasibility study of water and liquid-metal-cooled divertor/bumper concepts

  8. Nuclear engineering experiments at experimental facilities of JNC in graduate course of Tokyo Institute of Technology

    International Nuclear Information System (INIS)

    Hayashizaki, Noriyosu; Takahashi, Minoru; Aoyama, Takafumi; Onose, Shoji

    2005-01-01

    Nuclear engineering experiments using outside facilities of the campus have been offered for graduate students in the nuclear engineering course in Tokyo Institute of Technology (Tokyo Tech.). The experiments are managed with the collaboration of Japan Nuclear Cycle Development Institute (JNC), Japan Atomic Energy Research Institute (JAERI) and Research Reactor Institute, Kyoto University (KUR). This report presents the new curriculum of the nuclear engineering experiments at JNC since 2002. The change is due to the shutdown of Deuterium Criticality Assembly Facility (DCA) that was used as an experimental facility until 2001. Reactor physics experiment using the training simulator of the experimental fast reactor JOYO is continued from the previous curriculum with the addition of the criticality approach experiment and control rods calibration. A new experimental subject is an irradiated material experiment at the Material Monitoring Facility (MMF). As a result, both are acceptable as the student experiments on the fast reactor. (author)

  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. Information on the Advanced Plant Experiment (APEX) Test Facility

    International Nuclear Information System (INIS)

    Smith, Curtis Lee

    2015-01-01

    The purpose of this report provides information related to the design of the Oregon State University Advanced Plant Experiment (APEX) test facility. Information provided in this report have been pulled from the following information sources: Reference 1: R. Nourgaliev and et.al, 'Summary Report on NGSAC (Next-Generation Safety Analysis Code) Development and Testing,' Idaho National Laboratory, 2011. Note that this is report has not been released as an external report. Reference 2: O. Stevens, Characterization of the Advanced Plant Experiment (APEX) Passive Residual Heat Removal System Heat Exchanger, Master Thesis, June 1996. Reference 3: J. Reyes, Jr., Q. Wu, and J. King, Jr., Scaling Assessment for the Design of the OSU APEX-1000 Test Facility, OSU-APEX-03001 (Rev. 0), May 2003. Reference 4: J. Reyes et al, Final Report of the NRC AP600 Research Conducted at Oregon State University, NUREG/CR-6641, July 1999. Reference 5: K. Welter et al, APEX-1000 Confirmatory Testing to Support AP1000 Design Certification (non-proprietary), NUREG-1826, August 2005.

  13. 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.

  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. 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.

  16. Polar-Drive Experiments at the National Ignition Facility

    Science.gov (United States)

    Hohenberger, M.

    2014-10-01

    To support direct-drive inertial confinement fusion (ICF) experiments at the National Ignition Facility (NIF) in its indirect-drive beam configuration, the polar-drive (PD) concept has been proposed. It requires direct-drive-specific beam smoothing, phase plates, and repointing the NIF beams toward the equator to ensure symmetric target irradiation. First experiments testing the performance of ignition-relevant PD implosions at the NIF have been performed. The goal of these early experiments was to develop a stable, warm implosion platform to investigate laser deposition and laser-plasma instabilities at ignition-relevant plasma conditions, and to develop and validate ignition-relevant models of laser deposition and heat conduction. These experiments utilize the NIF in its current configuration, including beam geometry, phase plates, and beam smoothing. Warm, 2.2-mm-diam plastic shells were imploded with total drive energies ranging from ~ 350 to 750 kJ with peak powers of 60 to 180 TW and peak on-target intensities from 4 ×1014 to 1 . 2 ×1015 W/cm2. Results from these initial experiments are presented, including the level of hot-electron preheat, and implosion symmetry and shell trajectory inferred via self-emission imaging and backlighting. Experiments are simulated with the 2-D hydrodynamics code DRACO including a full 3-D ray trace to model oblique beams, and a model for cross-beam energy transfer (CBET). These simulations indicate that CBET affects the shell symmetry and leads to a loss of energy imparted onto the shell, consistent with the experimental data. This material is based upon work supported by the Department of Energy National Nuclear Security Administration under Award Number DE-NA0001944.

  17. 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

  18. ALPHA experiment facility and Prof. Jeffrey Hangst.

    CERN Multimedia

    Maximilien Brice

    2010-01-01

    Picture 01-07: General views of the ALPHA experiment Picture 5: Andrea Gutierrez, a PhD student from UBC, transfers liquid helium from a storage dewar into the cryostat containing the superconducting magnetic trap used by the ALPHA experiment.Picture 08-11: Jeffery Hangst, spokesperson for ALPHA Picture 12: The ALPHA silicon detector, which surrounds the trapping resion and is used for imaging antiproton annihilations (Credit University of Liverpool) Picture 13: Untrapped antihydrogen atoms annihilating on the inner surface of the ALPHA trap. These are measured by the ALPHA annihilation detector. The events are concentrated at the electrode radius of about 22.3 mm. The coordinates are defined in the Nature article, Figure 1b. Picture 14: The electrodes (gold) for the ALPHA Penning trap being inserted into the vacuum chamber and cryostat assembly. This is the trap used to combine or "mix" positrons and antiprotons to make antihydrogen. (Credit: Niels Madsen ALPHA/Swansea.) Picture 15: Top, a diagram of the...

  19. Experience with a servo-hydraulic mechanical testing machine installed in a new shielded active facility at Windscale Nuclear Power Development Laboratories

    International Nuclear Information System (INIS)

    Garlick, A.; Hindmarch, P.; Gravenor, J.G.; Rhodes, D.

    1982-03-01

    An Instron model 1273 servo-hydraulic machine has been installed within a lead-shielded cell at Windscale in order to provide a facility capable of performing a wide range of mechanical tests on nuclear reactor structural materials and fuel assembly components. This particular type of machine was chosen because it has design features associated with the load frame, location of the actuator and adjustment and clamping of the cross-head that are especially well suited to remote operation within a shielded cell. The design of the testing facility is described and the programmes of work that have been completed over the past 11/2 years of operation are reviewed. (author)

  20. SUPERCONDUCTING RADIO-FREQUENCY MODULES TEST FACILITY OPERATING EXPERIENCE

    International Nuclear Information System (INIS)

    Soyars, W.; Bossert, R.; Darve, C.; Degraff, B.; Klebaner, A.; Martinez, A.; Pei, L.; Theilacker, J.

    2008-01-01

    Fermilab is heavily engaged and making strong technical contributions to the superconducting radio-frequency research and development program (SRF R and D). Four major SRF test areas are being constructed to enable vertical and horizontal cavity testing, as well as cryomodule testing. The existing Fermilab cryogenic infrastructure has been modified to service the SRF R and D needs. The project's first stage has been successfully completed, which allows for distribution of cryogens for a single-cavity cryomodule using the existing Cryogenic Test Facility (CTF) that houses three Tevatron satellite refrigerators. The cooling capacity available for cryomodule testing at Meson Detector Building (MDB) results from the liquefaction capacity of the CTF cryogenic system. The cryogenic system for a single 9-cell cryomodule is currently operational. The paper describes the status, challenges and operational experience of the initial phase of the project

  1. 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

  2. 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.

  3. Critical experiments facility and criticality safety programs at JAERI

    International Nuclear Information System (INIS)

    Kobayashi, Iwao; Tachimori, Shoichi; Takeshita, Isao; Suzaki, Takenori; Miyoshi, Yoshinori; Nomura, Yasushi

    1985-10-01

    The nuclear criticality safety is becoming a key point in Japan in the safety considerations for nuclear installations outside reactors such as spent fuel reprocessing facilities, plutonium fuel fabrication facilities, large scale hot alboratories, and so on. Especially a large scale spent fuel reprocessing facility is being designed and would be constructed in near future, therefore extensive experimental studies are needed for compilation of our own technical standards and also for verification of safety in a potential criticality accident to obtain public acceptance. Japan Atomic Energy Research Institute is proceeding a construction program of a new criticality safety experimental facility where criticality data can be obtained for such solution fuels as mainly handled in a reprocessing facility and also chemical process experiments can be performed to investigate abnormal phenomena, e.g. plutonium behavior in solvent extraction process by using pulsed colums. In FY 1985 detail design of the facility will be completed and licensing review by the government would start in FY 1986. Experiments would start in FY 1990. Research subjects and main specifications of the facility are described. (author)

  4. Safety research experiment facilities, Idaho National Engineering Laboratory, Idaho. Final environmental impact statement

    International Nuclear Information System (INIS)

    Liverman, J.L.

    1977-09-01

    This environmental statement was prepared for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evaluation of some design options and in the assessment of the long-term potential risk associated with wide-acale deployment of the FBR

  5. Management Of Experiments And Data At The National Ignition Facility

    International Nuclear Information System (INIS)

    Azevedo, S.; Casey, A.; Beeler, R.; Bettenhausen, R.; Bond, E.; Chandrasekaran, H.; Foxworthy, C.; Hutton, M.; Krammen, J.; Liebman, J.; Marsh, A.; Pannell, T.; Rhodes, J.; Tappero, J.; Warrick, A.

    2011-01-01

    Experiments, or 'shots', conducted at the National Ignition Facility (NIF) are discrete events that occur over a very short time frame (tens of nanoseconds) separated by many hours. Each shot is part of a larger campaign of shots to advance scientific understanding in high-energy-density physics. In one campaign, scientists use energy from the 192-beam, 1.8-Megajoule pulsed laser in the NIF system to symmetrically implode a hydrogen-filled target, thereby creating conditions similar to the interior of stars in a demonstration of controlled fusion. Each NIF shot generates gigabytes of data from over 30 diagnostics that measure optical, x-ray, and nuclear phenomena from the imploding target. We have developed systems to manage all aspects of the shot cycle. Other papers will discuss the control of the lasers and targets, while this paper focuses on the setup and management of campaigns and diagnostics. Because of the low duty cycle of shots, and the thousands of adjustments for each shot (target type, composition, shape; laser beams used, their power profiles, pointing; diagnostic systems used, their configuration, calibration, settings) it is imperative that we accurately define all equipment prior to the shot. Following the shot, and capture of the data by the automatic control system, it is equally imperative that we archive, analyze and visualize the results within the required 30 minutes post-shot. Results must be securely archived, approved, web-visible and downloadable in order to facilitate subsequent publication. To-date NIF has successfully fired over 2,500 system shots, as well as thousands of test firings and dry-runs. We will present an overview of the highly-flexible and scalable campaign management systems and tools employed at NIF that control experiment configuration of the facility all the way through presentation of analyzed results.

  6. 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.

  7. 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.)

  8. Feedback experience from the decommissioning of Spanish nuclear facilities

    International Nuclear Information System (INIS)

    Santiago, J.L.

    2008-01-01

    The Spain has accumulated significant experience in the field of decommissioning of nuclear and radioactive facilities. Relevant projects include the remediation of uranium mills and mines, the decommissioning of research reactors and nuclear research facilities and the decommissioning of gas-graphite nuclear power plants. The decommissioning of nuclear facilities in Spain is undertaken by ENRESA, who is also responsible for the management of radioactive wastes. The two most notable projects are the decommissioning of the Vandellos I nuclear power plant and the decommissioning of the CIEMAT nuclear research centre. The Vandellos I power plant was decommissioned in about five years to what is known as level 2. During this period, the reactor vessel was confined, most plant systems and components were dismantled, the facility was prepared for a period of latency and a large part of the site was restored for subsequent release. In 2005 the facility entered into the phase of dormancy, with minimum operating requirements. Only surveillance and maintenance activities are performed, among which special mention should be made to the five-year check of the leak tightness of the reactor vessel. After the dormancy period (25 - 30 years), level 3 of decommissioning will be initiated including the total dismantling of the remaining parts of the plant and the release of the whole site for subsequent uses. The decommissioning of the CIEMAT Research Centre includes the dismantling of obsolete facilities such as the research reactor JEN-1, a pilot reprocessing plant, a fuel fabrication facility, a conditioning plant for liquid and a liquid waste storage facility which were shutdown in the early eighties. Dismantling works have started in 2006 and will be completed by 2009. On the basis of the experience gained in the above mentioned sites, this paper describes the approaches adopted by ENRESA for large decommissioning projects. (author)

  9. Calculations of the startup experiments at the Poolside Facility

    Energy Technology Data Exchange (ETDEWEB)

    Williams, M.L.; Maerker, R.E.

    1982-01-01

    Discrete ordinate calculations are made and the results compared with measurements performed in the startup experiment at the Poolside Facility. Because of the physical size of the simulated surveillance capsule used in this experiment, the analytic procedure is more complicated than one adopted in earlier calculations of the PCA-PVF and PSF. The comparisons indicate the pressure vessel fluences in the long-term irradiation experiments still presently going on at the PSF, and which are geometrically identical to the startup experiment, can only be predicted to within about 20%.

  10. Calculations of the startup experiments at the Poolside Facility

    International Nuclear Information System (INIS)

    Williams, M.L.; Maerker, R.E.

    1982-01-01

    Discrete ordinate calculations are made and the results compared with measurements performed in the startup experiment at the Poolside Facility. Because of the physical size of the simulated surveillance capsule used in this experiment, the analytic procedure is more complicated than one adopted in earlier calculations of the PCA-PVF and PSF. The comparisons indicate the pressure vessel fluences in the long-term irradiation experiments still presently going on at the PSF, and which are geometrically identical to the startup experiment, can only be predicted to within about 20%

  11. Microscope-Based Fluid Physics Experiments in the Fluids and Combustion Facility on ISS

    Science.gov (United States)

    Doherty, Michael P.; Motil, Susan M.; Snead, John H.; Malarik, Diane C.

    2000-01-01

    At the NASA Glenn Research Center, the Microgravity Science Program is planning to conduct a large number of experiments on the International Space Station in both the Fluid Physics and Combustion Science disciplines, and is developing flight experiment hardware for use within the International Space Station's Fluids and Combustion Facility. Four fluids physics experiments that require an optical microscope will be sequentially conducted within a subrack payload to the Fluids Integrated Rack of the Fluids and Combustion Facility called the Light Microscopy Module, which will provide the containment, changeout, and diagnostic capabilities to perform the experiments. The Light Microscopy Module is planned as a fully remotely controllable on-orbit microscope facility, allowing flexible scheduling and control of experiments within International Space Station resources. This paper will focus on the four microscope-based experiments, specifically, their objectives and the sample cell and instrument hardware to accommodate their requirements.

  12. Ohmically heated toroidal experiment (OHTE) mobile ignition test reactor facility concept study

    International Nuclear Information System (INIS)

    Masson, L.S.; Watts, K.D.; Piscitella, R.R.; Sekot, J.P.; Drexler, R.L.

    1983-02-01

    This report presents the results of a study to evaluate the use of an existing nuclear test complex at the Idaho National Engineering Laboratory (INEL) for the assembly, testing, and remote maintenance of the ohmically heated toroidal experiment (OHTE) compact reactor. The portable reactor concept is described and its application to OHTE testing and maintenance requirements is developed. Pertinent INEL facilities are described and several test system configurations that apply to these facilities are developed and evaluated

  13. Technical specifications for the Pajarito Site Critical Experiments Facility

    International Nuclear Information System (INIS)

    Malenfant, R.E.; Paxton, H.C.

    1980-12-01

    This document is to satisfy the requirement for technical specifications spelled out in DOE Manual Chapter 0540, Safety of DOE-Owned Reactors. Technical specifications are defined in Sec. 0540-048, and the requirement for them appears in Sec. 0540-015. The following technical specifications update the document, Technical Specifications for the Pajarito Site Critical Experiments Facility

  14. 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)

  15. 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.)

  16. EURATOM: Development, role, experience

    International Nuclear Information System (INIS)

    Tsalas, S.

    1998-01-01

    Besides description of the historical development of EURATOM and its role in safeguards the paper includes the implementation experience of EURATOM safeguards. Depending on the scope of inspection a set of measures is applied according to the following verification methods: accountancy audit, visual checks, counting and identification, non-destructive measurements, sampling and destructive analysis complemented by containment and surveillance measures. The present staff of the safeguards directorate comprises about 300 persons of which two thirds are inspectors. EURATOM has a solid legal basis for performing safeguards inspections and the necessary infrastructure for inspection support, information treatment and data evaluation. It is a full scope multinational regional safeguards system fulfilling its obligations under EURATOM Treaty and contributing to the successful implementation of the Non-proliferation treaty by satisfying its obligations in the framework of the safeguards agreements with the IAEA

  17. HLM fuel pin bundle experiments in the CIRCE pool facility

    Energy Technology Data Exchange (ETDEWEB)

    Martelli, Daniele, E-mail: daniele.martelli@ing.unipi.it [University of Pisa, Department of Civil and Industrial Engineering, Pisa (Italy); Forgione, Nicola [University of Pisa, Department of Civil and Industrial Engineering, Pisa (Italy); Di Piazza, Ivan; Tarantino, Mariano [Italian National Agency for New Technologies, Energy and Sustainable Economic Development, C.R. ENEA Brasimone (Italy)

    2015-10-15

    Highlights: • The experimental results represent the first set of values for LBE pool facility. • Heat transfer is investigated for a 37-pin electrical bundle cooled by LBE. • Experimental data are presented together with a detailed error analysis. • Nu is computed as a function of the Pe and compared with correlations. • Experimental Nu is about 25% lower than Nu derived from correlations. - Abstract: Since Lead-cooled Fast Reactors (LFR) have been conceptualized in the frame of GEN IV International Forum (GIF), great interest has focused on the development and testing of new technologies related to HLM nuclear reactors. In this frame the Integral Circulation Experiment (ICE) test section has been installed into the CIRCE pool facility and suitable experiments have been carried out aiming to fully investigate the heat transfer phenomena in grid spaced fuel pin bundles providing experimental data in support of European fast reactor development. In particular, the fuel pin bundle simulator (FPS) cooled by lead bismuth eutectic (LBE), has been conceived with a thermal power of about 1 MW and a uniform linear power up to 25 kW/m, relevant values for a LFR. It consists of 37 fuel pins (electrically simulated) placed on a hexagonal lattice with a pitch to diameter ratio of 1.8. The FPS was deeply instrumented by several thermocouples. In particular, two sections of the FPS were instrumented in order to evaluate the heat transfer coefficient along the bundle as well as the cladding temperature in different ranks of sub-channels. Nusselt number in the central sub-channel was therefore calculated as a function of the Peclet number and the obtained results were compared to Nusselt numbers obtained from convective heat transfer correlations available in literature on Heavy Liquid Metals (HLM). Results reported in the present work, represent the first set of experimental data concerning fuel pin bundle behaviour in a heavy liquid metal pool, both in forced and

  18. Gravity driven emergency core cooling experiments with the PACTEL facility

    International Nuclear Information System (INIS)

    Munther, R.; Kalli, H.; Kouhia, J.

    1996-01-01

    PACTEL (Parallel Channel Test Loop) is an experimental out-of-pile facility designed to simulated the major components and system behaviour of a commercial Pressurized Water Reactor (PWR) during different postulated LOCAs and transients. The reference reactor to the PACTEL facility is Loviisa type WWER-440. The recently made modifications enable experiments to be conducted also on the passive core cooling. In these experiments the passive core cooling system consisted of one core makeup tank (CMT) and pressure balancing lines from the pressurizer and from a cold leg connected to the top of the CMT in order to maintain the tank in pressure equilibrium with the primary system during ECC injection. The line from the pressurizer to the core makeup tank was normally open. The ECC flow was provided from the CMT located at a higher elevation than the main part of the primary system. A total number of nine experiments have been performed by now. 4 refs, 7 figs, 3 tabs

  19. Gravity driven emergency core cooling experiments with the PACTEL facility

    Energy Technology Data Exchange (ETDEWEB)

    Munther, R; Kalli, H [University of Technology, Lappeenranta (Finland); Kouhia, J [Technical Research Centre of Finland, Lappeenranta (Finland)

    1996-12-01

    PACTEL (Parallel Channel Test Loop) is an experimental out-of-pile facility designed to simulated the major components and system behaviour of a commercial Pressurized Water Reactor (PWR) during different postulated LOCAs and transients. The reference reactor to the PACTEL facility is Loviisa type WWER-440. The recently made modifications enable experiments to be conducted also on the passive core cooling. In these experiments the passive core cooling system consisted of one core makeup tank (CMT) and pressure balancing lines from the pressurizer and from a cold leg connected to the top of the CMT in order to maintain the tank in pressure equilibrium with the primary system during ECC injection. The line from the pressurizer to the core makeup tank was normally open. The ECC flow was provided from the CMT located at a higher elevation than the main part of the primary system. A total number of nine experiments have been performed by now. 4 refs, 7 figs, 3 tabs.

  20. Technical specifications for the Oak Ridge Critical Experiments Facility

    International Nuclear Information System (INIS)

    Stinnett, R.M.

    1986-01-01

    These Technical Specifications for the Oak Ridge Critical Experiments Facility (CEF) delineate limiting conditions of operation for the facility. The CEF is used primarily for testing the High Flux Isotope Reactor (HFIR) fuel assemblies. Specifically, the Criticality Testing Unit, Liquid (CTUL), located in the CEF, is used for the HFIR fuel assembly test. The test is performed to satisfy the surveillance requirements of the HFIR Technical Specifications. The test is used to determine the water-submerged shutdown margin for each fuel assembly. 11 refs

  1. Advanced Test Reactor (ATR) Facility 10CFR830 Safety Basis Related to Facility Experiments

    International Nuclear Information System (INIS)

    Tomberlin, T.A.

    2002-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) Advanced Test Reactor (ATR), a DOE Category A reactor, was designed to provide an irradiation test environment for conducting a variety of experiments. The ATR Safety Analysis Report, determined by DOE to meet the requirements of 10 CFR 830, Subpart B, provides versatility in types of experiments that may be conducted. This paper addresses two general types of experiments in the ATR facility and how safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore this type of experiment is addressed with more detail in the safety basis. This allows individual safety analyses for these experiments to be more routine and repetitive. The second type of experiment is less defined and is permitted under more general controls. Therefore, individual safety analyses for the second type of experiment tend to be more unique from experiment to experiment. Experiments are also discussed relative to ''major modifications'' and DOE-STD-1027-92. Application of the USQ process to ATR experiments is also discussed

  2. A ``Cyber Wind Facility'' for HPC Wind Turbine Field Experiments

    Science.gov (United States)

    Brasseur, James; Paterson, Eric; Schmitz, Sven; Campbell, Robert; Vijayakumar, Ganesh; Lavely, Adam; Jayaraman, Balaji; Nandi, Tarak; Jha, Pankaj; Dunbar, Alex; Motta-Mena, Javier; Craven, Brent; Haupt, Sue

    2013-03-01

    The Penn State ``Cyber Wind Facility'' (CWF) is a high-fidelity multi-scale high performance computing (HPC) environment in which ``cyber field experiments'' are designed and ``cyber data'' collected from wind turbines operating within the atmospheric boundary layer (ABL) environment. Conceptually the ``facility'' is akin to a high-tech wind tunnel with controlled physical environment, but unlike a wind tunnel it replicates commercial-scale wind turbines operating in the field and forced by true atmospheric turbulence with controlled stability state. The CWF is created from state-of-the-art high-accuracy technology geometry and grid design and numerical methods, and with high-resolution simulation strategies that blend unsteady RANS near the surface with high fidelity large-eddy simulation (LES) in separated boundary layer, blade and rotor wake regions, embedded within high-resolution LES of the ABL. CWF experiments complement physical field facility experiments that can capture wider ranges of meteorological events, but with minimal control over the environment and with very small numbers of sensors at low spatial resolution. I shall report on the first CWF experiments aimed at dynamical interactions between ABL turbulence and space-time wind turbine loadings. Supported by DOE and NSF.

  3. West Valley facility spent fuel handling, storage, and shipping experience

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1990-11-01

    The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New York Nuclear Service Center at West Valley, New York and operated by DOE. A subject of particular interest in the study was the behavior of corrosion product deposits (i.e., crud) deposits on spent LWR fuel after long-term pool storage; some evidence of crud loosening has been observed with fuel that was stored for extended periods at the West Valley facility and at other sites. Conclusions associated with the experience to date with old spent fuel that has been stored at the West Valley facility are presented. The conclusions are drawn from these subject areas: a general overview of the West Valley experience, handling of spent fuel, storing of spent fuel, rod consolidation, shipping of spent fuel, crud loosening, and visual inspection. A list of recommendations is provided. 61 refs., 4 figs., 5 tabs

  4. 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...

  5. Synchrotron light beam and a synchrotron light experiment facility

    International Nuclear Information System (INIS)

    Ando, Masami

    1980-01-01

    In the National Laboratory for High Energy Physics, about two years ago, the requirements of synchrotron light beam in respective measuring instruments were discussed. Then, also the arrangement (lattice) of a storage ring, the nature of synchrotron light beam, a synchrotron light experiment facility and the arrangement of the beam lines were studied. During the period of two years since then, due to the changes in the circumstances, the design of the lattice was altered. Accordingly, the arrangement of the beam lines and of measuring instruments were largely changed. At this point, the results of discussions in various meetings are described, though they may still be subject to future changes, with due consideration to beam, environment and beam lines required for the design of the measuring instruments: (1) storage ring and synchrotron light beam, (2) requirements on small beam size and beam stability, (3) a synchrotron light experiment facility. (J.P.N.)

  6. Commercial experience with facility deactivation to safe storage

    International Nuclear Information System (INIS)

    Sype, T.T.; Fischer, S.R.; Lee, J.H. Jr.; Sanchez, L.C.; Ottinger, C.A.; Pirtle, G.J.

    1995-09-01

    The Department of Energy (DOE) has shutdown many production reactors; the Department has begun a major effort to also shutdown a wide variety of other nuclear facilities. Because so many facilities are being closed, it is necessary to place many of them into a safe- storage status, i.e., deactivation, before conducting decommissioning- for perhaps as long as 20 years. The challenge is to achieve this safe-storage condition in a cost-effective manner while remaining in compliance with applicable regulations. The DOE Office of Environmental Management, Office of Transition and Management, commissioned a lessons-learned study of commercial experience with safe storage and decommissioning. Although the majority of the commercial experience has been with reactors, many of the lessons learned presented in this document can provide insight into transitioning challenges that Will be faced by the DOE weapons complex

  7. Commercial experience with facility deactivation to safe storage

    Energy Technology Data Exchange (ETDEWEB)

    Sype, T.T. [Sandia National Labs., Albuquerque, NM (United States); Fischer, S.R. [Los Alamos National Lab., NM (United States); Lee, J.H. Jr.; Sanchez, L.C.; Ottinger, C.A.; Pirtle, G.J. [Sandia National Labs., Albuquerque, NM (United States)

    1995-09-01

    The Department of Energy (DOE) has shutdown many production reactors; the Department has begun a major effort to also shutdown a wide variety of other nuclear facilities. Because so many facilities are being closed, it is necessary to place many of them into a safe- storage status, i.e., deactivation, before conducting decommissioning- for perhaps as long as 20 years. The challenge is to achieve this safe-storage condition in a cost-effective manner while remaining in compliance with applicable regulations. The DOE Office of Environmental Management, Office of Transition and Management, commissioned a lessons-learned study of commercial experience with safe storage and decommissioning. Although the majority of the commercial experience has been with reactors, many of the lessons learned presented in this document can provide insight into transitioning challenges that Will be faced by the DOE weapons complex.

  8. Artificial climate experiment facility in Institute for Environmental Sciences

    Energy Technology Data Exchange (ETDEWEB)

    Hisamatsu, Shunichi [Department of Radioecology, Institute for Environmental Sciences, Rokkasho, Aomori (Japan)

    1999-03-01

    The Institute for Environmental Sciences is now constructing the artificial climate experiment facility (ACEF) to research the effect of climate on movement of elements in the various environments. The ACEF will have one large, and five small artificial climate experiment chambers. The large chamber is designed to simulate climate conditions in all Japan. It will equip systems to simulate sunshine, rainfall (including acid rain), snowfall and fog (including acid fog). `Yamase` condition will also be reproduced in it. Yamase is a Japanese term describing the characteristic weather condition occurring mainly on the Pacific Ocean side at the northern Japan. While the small chamber will not have rainfall, snowfall and fog systems, radioisotopes will be used in the two small chambers which will be set up in a radioisotope facility. We describe here the outline of the ACEF and the preliminary research programs being undertaken using both kinds of chambers. (author)

  9. Artificial climate experiment facility in Institute for Environmental Sciences

    International Nuclear Information System (INIS)

    Hisamatsu, Shunichi

    1999-01-01

    The Institute for Environmental Sciences is now constructing the artificial climate experiment facility (ACEF) to research the effect of climate on movement of elements in the various environments. The ACEF will have one large, and five small artificial climate experiment chambers. The large chamber is designed to simulate climate conditions in all Japan. It will equip systems to simulate sunshine, rainfall (including acid rain), snowfall and fog (including acid fog). 'Yamase' condition will also be reproduced in it. Yamase is a Japanese term describing the characteristic weather condition occurring mainly on the Pacific Ocean side at the northern Japan. While the small chamber will not have rainfall, snowfall and fog systems, radioisotopes will be used in the two small chambers which will be set up in a radioisotope facility. We describe here the outline of the ACEF and the preliminary research programs being undertaken using both kinds of chambers. (author)

  10. Project and feedback experience on nuclear facility decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Santiago, J.L. [ENRESA (Spain); Benest, T.G. [United Kingdom Atomic Energy Authority, Windscale, Cumbria (United Kingdom); Tardy, F.; Lefevre, Ph. [Electricite de France (EDF/CIDEN), 69 - Villeurbanne (France); Willis, A. [VT Nuclear Services (United Kingdom); Gilis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R. [Belgoprocess (Belgium); Jeanjacques, M. [CEA Saclay, 91 - Gif sur Yvette (France); Bohar, M.P.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.; Binet, C. [CEA Fontenay aux Roses, 92 (France); Fontana, Ph.; Fraize, G. [CEA Marcoule 30 (France); Seurat, Ph. [AREVA NC, 75 - Paris (France); Chesnokov, A.V.; Fadin, S.Y.; Ivanov, O.P.; Kolyadin, V.I.; Lemus, A.V.; Pavlenko, V.I.; Semenov, S.G.; Shisha, A.D.; Volkov, V.G.; Zverkov, Y.A. [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)

    2008-11-15

    This series of 6 short articles presents the feedback experience that has been drawn from various nuclear facility dismantling and presents 3 decommissioning projects: first, the WAGR project that is the UK demonstration project for power reactor decommissioning (a review of the tools used to dismantle the reactor core); secondly, the dismantling project of the Bugey-1 UNGG reactor for which the dismantling works of the reactor internals is planned to be done underwater; and thirdly, the decommissioning project of the MR reactor in the Kurchatov Institute. The feedback experience described concerns nuclear facilities in Spain (Vandellos-1 and the CIEMAT research center), in Belgium (the Eurochemic reprocessing plant), and in France (the decommissioning of nuclear premises inside the Fontenay-aux-roses Cea center and the decommissioning of the UP1 spent fuel reprocessing plant at the Marcoule site). (A.C.)

  11. Project and feedback experience on nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Santiago, J.L.; Benest, T.G.; Tardy, F.; Lefevre, Ph.; Willis, A.; Gilis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R.; Jeanjacques, M.; Bohar, M.P.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.; Binet, C.; Fontana, Ph.; Fraize, G.; Seurat, Ph.; Chesnokov, A.V.; Fadin, S.Y.; Ivanov, O.P.; Kolyadin, V.I.; Lemus, A.V.; Pavlenko, V.I.; Semenov, S.G.; Shisha, A.D.; Volkov, V.G.; Zverkov, Y.A.

    2008-01-01

    This series of 6 short articles presents the feedback experience that has been drawn from various nuclear facility dismantling and presents 3 decommissioning projects: first, the WAGR project that is the UK demonstration project for power reactor decommissioning (a review of the tools used to dismantle the reactor core); secondly, the dismantling project of the Bugey-1 UNGG reactor for which the dismantling works of the reactor internals is planned to be done underwater; and thirdly, the decommissioning project of the MR reactor in the Kurchatov Institute. The feedback experience described concerns nuclear facilities in Spain (Vandellos-1 and the CIEMAT research center), in Belgium (the Eurochemic reprocessing plant), and in France (the decommissioning of nuclear premises inside the Fontenay-aux-roses Cea center and the decommissioning of the UP1 spent fuel reprocessing plant at the Marcoule site). (A.C.)

  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. 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)

  14. The First Experiments on the National Ignition Facility

    International Nuclear Information System (INIS)

    Landen, O L; Glenzer, S; Froula, D; Dewald, E; Suter, L J; Schneider, M; Hinkel, D; Fernandez, J; Kline, J; Goldman, S; Braun, D; Celliers, P; Moon, S; Robey, H; Lanier, N; Glendinning, G; Blue, B; Wilde, B; Jones, O; Schein, J; Divol, L; Kalantar, D; Campbell, K; Holder, J; MacDonald, J; Niemann, C; Mackinnon, A; Collins, R; Bradley, D; Eggert, J; Hicks, D; Gregori, G; Kirkwood, R; Young, B; Foster, J; Hansen, F; Perry, T; Munro, D; Baldis, H; Grim, G; Heeter, R; Hegelich, B; Montgomery, D; Rochau, G; Olson, R; Turner, R; Workman, J; Berger, R; Cohen, B; Kruer, W; Langdon, B; Langer, S; Meezan, N; Rose, H; Still, B; Williams, E; Dodd, E; Edwards, J; Monteil, M; Stevenson, M; Thomas, B; Coker, R; Magelssen, G; Rosen, P; Stry, P; Woods, D; Weber, S; Alvarez, S; Armstrong, G; Bahr, R; Bourgade, J; Bower, D; Celeste, J; Chrisp, M; Compton, S; Cox, J; Constantin, C; Costa, R; Duncan, J; Ellis, A; Emig, J; Gautier, C; Greenwood, A; Griffith, R; Holdner, F; Holtmeier, G; Hargrove, D; James, T; Kamperschroer, J; Kimbrough, J; Landon, M; Lee, D; Malone, R; May, M; Montelongo, S; Moody, J; Ng, E; Nikitin, A; Pellinen, D; Piston, K; Poole, M; Rekow, V; Rhodes, M; Shepherd, R; Shiromizu, S; Voloshin, D; Warrick, A; Watts, P; Weber, F; Young, P; Arnold, P; Atherton, L J; Bardsley, G; Bonanno, R; Borger, T; Bowers, M; Bryant, R; Buckman, S; Burkhart, S; Cooper, F; Dixit, S; Erbert, G; Eder, D; Ehrlich, B; Felker, B; Fornes, J; Frieders, G; Gardner, S; Gates, C; Gonzalez, M; Grace, S; Hall, T; Haynam, C; Heestand, G; Henesian, M; Hermann, M; Hermes, G; Huber, S; Jancaitis, K; Johnson, S; Kauffman, B; Kelleher, T; Kohut, T; Koniges, A E; Labiak, T; Latray, D; Lee, A; Lund, D; Mahavandi, S; Manes, K R; Marshall, C; McBride, J; McCarville, T; McGrew, L; Menapace, J.

    2005-01-01

    A first set of laser-plasma interaction, hohlraum energetics and hydrodynamic experiments have been performed using the first 4 beams of the National Ignition Facility (NIF), in support of indirect drive Inertial Confinement Fusion (ICF) and High Energy Density Physics (HEDP). In parallel, a robust set of optical and x-ray spectrometers, interferometer, calorimeters and imagers have been activated. The experiments have been undertaken with laser powers and energies of up to 8 TW and 17 kJ in flattop and shaped 1-9 ns pulses focused with various beam smoothing options

  15. Hohlraum modeling for opacity experiments on the National Ignition Facility

    Science.gov (United States)

    Dodd, E. S.; DeVolder, B. G.; Martin, M. E.; Krasheninnikova, N. S.; Tregillis, I. L.; Perry, T. S.; Heeter, R. F.; Opachich, Y. P.; Moore, A. S.; Kline, J. L.; Johns, H. M.; Liedahl, D. A.; Cardenas, T.; Olson, R. E.; Wilde, B. H.; Urbatsch, T. J.

    2018-06-01

    This paper discusses the modeling of experiments that measure iron opacity in local thermodynamic equilibrium (LTE) using laser-driven hohlraums at the National Ignition Facility (NIF). A previous set of experiments fielded at Sandia's Z facility [Bailey et al., Nature 517, 56 (2015)] have shown up to factors of two discrepancies between the theory and experiment, casting doubt on the validity of the opacity models. The purpose of the new experiments is to make corroborating measurements at the same densities and temperatures, with the initial measurements made at a temperature of 160 eV and an electron density of 0.7 × 1022 cm-3. The X-ray hot spots of a laser-driven hohlraum are not in LTE, and the iron must be shielded from a direct line-of-sight to obtain the data [Perry et al., Phys. Rev. B 54, 5617 (1996)]. This shielding is provided either with the internal structure (e.g., baffles) or external wall shapes that divide the hohlraum into a laser-heated portion and an LTE portion. In contrast, most inertial confinement fusion hohlraums are simple cylinders lacking complex gold walls, and the design codes are not typically applied to targets like those for the opacity experiments. We will discuss the initial basis for the modeling using LASNEX, and the subsequent modeling of five different hohlraum geometries that have been fielded on the NIF to date. This includes a comparison of calculated and measured radiation temperatures.

  16. Development and installation of the GERDA experiment

    International Nuclear Information System (INIS)

    Smolnikov, A

    2010-01-01

    The progress in the development of the GERDA (GErmanium Detector Array) experiment is presented. The goal of the experiment is the search for neutrinoless double beta decay of 76 Ge with considerable reduction of background in comparison with predecessor experiments. GERDA will operate bare germanium semiconductor detectors (enriched in 76 Ge) submerged in high purity liquid argon supplemented by a water shield. The experimental set up is currently under construction in the underground facility of LNGS, Italy. The results of various R and D efforts and the main steps of the GERDA set up design and installation are given as well as several novel methods for background reduction are described.

  17. 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.

  18. W-1 Sodium Loop Safety Facility experiment centerline fuel thermocouple performance

    International Nuclear Information System (INIS)

    Meyers, S.C.; Henderson, J.M.

    1980-05-01

    The W-1 Sodium Loop Safety Facility (SLSF) experiment is the fifth in a series of experiments sponsored by the Department of Energy (DOE) as part of the National Fast Breeder Reactor (FBR) Safety Assurance Program. The experiments are being conducted under the direction of Argonne National Laboratory (ANL) and Hanford Engineering Development Laboratory (HEDL). The irradiation phase of the W-1 SLSF experiment was conducted between May 27 and July 20, 1979, and terminated with incipient fuel pin cladding failure during the final boiling transient. Experimental hardware and facility performed as designed, allowing completion of all planned tests and test objectives. This paper focuses on high temperature in-fuel thermocouples and discusses their development, fabrication, and performance in the W-1 experiment

  19. Materials Science Experiments Under Microgravity - A Review of History, Facilities, and Future Opportunities

    Science.gov (United States)

    Stenzel, Ch.

    2012-01-01

    Materials science experiments have been a key issue already since the early days of research under microgravity conditions. A microgravity environment facilitates processing of metallic and semiconductor melts without buoyancy driven convection and sedimentation. Hence, crystal growth of semiconductors, solidification of metallic alloys, and the measurement of thermo-physical parameters are the major applications in the field of materials science making use of these dedicated conditions in space. In the last three decades a large number of successful experiments have been performed, mainly in international collaborations. In parallel, the development of high-performance research facilities and the technological upgrade of diagnostic and stimuli elements have also contributed to providing optimum conditions to perform such experiments. A review of the history of materials science experiments in space focussing on the development of research facilities is given. Furthermore, current opportunities to perform such experiments onboard ISS are described and potential future options are outlined.

  20. The First Experiments on the National Ignition Facility

    International Nuclear Information System (INIS)

    Glenzer, S. H.; Dewald, E. L.; Landen, O. L.; Suter, L. J.; Jones, O. S.; Schein, J.; Froula, L.; Divol, K.; Campbell, K.; Schneider, M. S.; McDonal, J. W.; Niemann, C.; Mackinnon, A. J.

    2005-01-01

    Recently the first hohlraum and laser propagation experiments have been performed at the National Ignition Facility (NIF) in support of indirect dd drive Inertial Confinement Fusion (ICR) and High Energy Density Physics. Vacuum hohlraums have been irradiated with laser powers up to 8 TW, 1-9 ns pulse lengths and energies up to 17 kJ to activate several drive diagnostics, to study the hohlraum radiation temperature scaling with the lase power and hohlraum size, and to make contact with hohlraum experiments performed at the NOVA and Omega laser facilities. The experiments have validated analytical models and LASNEX calculations of hohlraum plasma filling and coronal hohlraum radiation production. furthermore, the effects of laser beam smooching by spectral dispersion (SSD) and polarization smoothing (PS) on the laser beam propagation has been studied in plasmas with sizes that reach for the first time the laser propagation length in indirect-drive gas-filled ignition hohlraum designs. the long scale gas-filled target experiments have shown propagation over 7 mm of low Z plasma without filamentation and beam break up when using full laser smoothing. The comparison of these results with modeling will be discussed. (Author)

  1. The First Experiments on the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Glenzer, S. H.; Dewald, E. L.; Landen, O. L.; Suter, L. J.; Jones, O. S.; Schein, J.; Froula, L.; Divol, K.; Campbell, K.; Schneider, M. S.; McDonal, J. W.; Niemann, C.; Mackinnon, A. J.

    2005-07-01

    Recently the first hohlraum and laser propagation experiments have been performed at the National Ignition Facility (NIF) in support of indirect dd drive Inertial Confinement Fusion (ICR) and High Energy Density Physics. Vacuum hohlraums have been irradiated with laser powers up to 8 TW, 1-9 ns pulse lengths and energies up to 17 kJ to activate several drive diagnostics, to study the hohlraum radiation temperature scaling with the lase power and hohlraum size, and to make contact with hohlraum experiments performed at the NOVA and Omega laser facilities. The experiments have validated analytical models and LASNEX calculations of hohlraum plasma filling and coronal hohlraum radiation production. furthermore, the effects of laser beam smooching by spectral dispersion (SSD) and polarization smoothing (PS) on the laser beam propagation has been studied in plasmas with sizes that reach for the first time the laser propagation length in indirect-drive gas-filled ignition hohlraum designs. the long scale gas-filled target experiments have shown propagation over 7 mm of low Z plasma without filamentation and beam break up when using full laser smoothing. The comparison of these results with modeling will be discussed. (Author)

  2. 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

  3. 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…

  4. Operational experience of the fuel cleaning facility of Joyo

    International Nuclear Information System (INIS)

    Mukaibo, R.; Matsuno, Y.; Sato, I.; Yoneda, Y.; Ito, H.

    1978-01-01

    Spent fuel assemblies in 'Joyo', after they are taken out of the core, are taken to the Fuel Cleaning Facility in the reactor service building and sodium removal is done. The cleaning process is done by cooling the assembly with argon gas, steam charging and rinsing by demineralized water. Deposited sodium was 50 ∼ 60 g per assembly. The sodium and steam reaction takes about 15 minutes to end and the total time the fuel is placed in the pot is about an hour. The total number of assemblies cleaned in the facility was 95 as of November 1977. In this report the operational experience together with discussions of future improvements are given. (author)

  5. Operational experience of the fuel cleaning facility of Joyo

    Energy Technology Data Exchange (ETDEWEB)

    Mukaibo, R; Matsuno, Y; Sato, I; Yoneda, Y; Ito, H [O-arai Engineering Centre, PNC, Ibaraki-ken, Tokio (Japan)

    1978-08-01

    Spent fuel assemblies in 'Joyo', after they are taken out of the core, are taken to the Fuel Cleaning Facility in the reactor service building and sodium removal is done. The cleaning process is done by cooling the assembly with argon gas, steam charging and rinsing by demineralized water. Deposited sodium was 50 {approx} 60 g per assembly. The sodium and steam reaction takes about 15 minutes to end and the total time the fuel is placed in the pot is about an hour. The total number of assemblies cleaned in the facility was 95 as of November 1977. In this report the operational experience together with discussions of future improvements are given. (author)

  6. Operational experiences and upgradation of waste management facilities Trombay, India

    International Nuclear Information System (INIS)

    Chander, Mahesh; Bodke, S.B.; Bansal, N.K.

    2001-01-01

    Full text: Waste Management Facilities Trombay provide services for the safe management of radioactive wastes generated from the operation of non power sources at Bhabha Atomic Research Centre, India. The paper describes in detail the current operational experience and facility upgradation by way of revamping of existing processes equipment and systems and augmentation of the facility by way of introducing latest processes and technologies to enhance the safety. Radioactive wastes are generated from the operation of research reactors, fuel fabrication, spent fuel reprocessing, research labs. manufacture of sealed sources and labeled compounds. Use of radiation sources in the field of medical, agriculture and industry also leads to generation of assorted solid waste and spent sealed radiation sources which require proper waste management. Waste Management Facilities Trombay comprise of Effluent Treatment Plant (ETP), Decontamination Centre (DC) and Radioactive Solid Waste Management Site (RSMS). Low level radioactive liquid effluents are received at ETP. Plant has 100 M 3 /day treatment capacity. Decontamination of liquid effluents is effected by chemical treatment method using co- precipitation as a process. Plant has 1800 M 3 of storage capacity. Chemical treatment system comprises of clarifloculator, static mixer and chemical feed tanks. Plant has concentrate management facility where chemical sludge is centrifuged to effect volume reduction of more that 15. Thickened sludge is immobilized in cement matrix. Decontamination Centre caters to the need of equipment decontamination from research reactors. Process used is ultrasonic chemical decontamination. Besides this DC provides services for decontamination of protective wears. Radioactive Solid Waste Management Site is responsible for the safe management of solid waste generated at various research reactors, plants, laboratories in Bhabha Atomic Research Centre. Spent sealed radiation sources are also stored

  7. EXPERIENCE AND PLANS OF THE JLAB FEL FACILITY AS A USER FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Michelle D. Shinn

    2007-08-26

    Jefferson Lab's IR Upgrade FEL building was planned from the beginning to be a user facility, and includes an associated 600 m2 area containing seven laboratories. The high average power capability (multikilowatt-level) in the near-infrared (1-3 microns), and many hundreds of watts at longer wavelengths, along with an ultrafast (~ 1 ps) high PRF (10's MHz) temporal structure makes this laser a unique source for both applied and basic research. In addition to the FEL, we have a dedicated laboratory capable of delivering high power (many tens of watts) of broadband THz light. After commissioning the IR Upgrade, we once again began delivering beam to users in 2005. In this presentation, I will give an overview of the FEL facility and its current performance, lessons learned over the last two years, and a synopsis of current and future experiments.

  8. The first target experiments on the National Ignition Facility

    International Nuclear Information System (INIS)

    Landen, O.L.; Glenzer, S.H.; Froula, D.H.; Dewald, E.L.; Suter, L.J.; Schneider, M.B.; Hinkel, D.E.; Fernandez, J.C.; Kline, J.L.; Goldman, S.R.; Braun, D.G.; Celliers, P.M.; Moon, S.J.; Robey, H.S.; Lanier, N.E.; Glendinning, S.G.; Blue, B.E.; Wilde, B.H.; Jones, O.S.; Schein, J.; Divol, L.; Kalantar, D.H.; Campbell, K.M.; Holder, J.P.; McDonald, J.W.; Niemann, C.; Mackinnon, A.J.; Collins, G.W.; Bradley, D.K.; Eggert, J.H.; Hicks, D.G.; Gregori, G.; Kirkwood, R.K.; Young, B.K.; Foster, J.M.; Hansen, J.F.; Perry, T.S.; Munro, D.H.; Baldis, H.A.; Grim, G.P.; Heeter, R.F.; Hegelich, M.B.; Montgomery, D.S.; Rochau, G.A.; Olson, R.E.; Turner, R.E.; Workman, J.B.; Berger, R.L.; Cohen, B.I.; Kruer, W.L.; Langdon, A.B.; Langer, S.H.; Meezan, N.B.; Rose, H.A.; Still, C.H.; Williams, E.A.; Dodd, E.A.; Edwards, M.J.; Monteil, M.C.; Stevenson, R.M.; Thomas, B.R.; Coker, R.F.; Magelssen, G.R.; Rosen, P.A.; Stry, P.E.; Woods, D.; Weber, S.V.; Young, P.E.; Alvarez, S.; Armstrong, G.; Bahr, R.; Bourgade, G.L.; Bower, D.; Celeste, J.; Chrisp, M.; Compton, S.; Cox, J.; Constantin, C.; Costa, R.; Duncan, J.; Ellis, A.; Emig, J.; Gautier, C.; Greenwood, A.; Griffith, R.; Holdner, F.; Holtmeier, G.; Hargrove, D.; James, T.; Kamperschroer, J.; Kimbrough, J.; Landon, M.; Lee, F.D.; Malone, R.; May, M.; Montelongo, S.; Moody, J.; Ng, E.; Nikitin, A.; Pellinen, D.; Piston, K.; Poole, M.; Rekow, V.; Rhodes, M.; Shepherd, R.; Shiromizu, S.; Voloshin, D.; Warrick, A.; Watts, P.; Weber, F.; Young, P.; Arnold, P.

    2007-01-01

    A first set of shock timing, laser-plasma interaction, hohlraum energetics and hydrodynamic experiments have been performed using the first 4 beams of the National Ignition Facility (NIF), in support of indirect drive Inertial Confinement Fusion (ICF) and High Energy Density Physics (HEDP). In parallel, a robust set of optical and X-ray spectrometers, interferometer, calorimeters and imagers have been activated. The experiments have been undertaken with laser powers and energies of up to 8 TW and 17 kJ in flattop and shaped 1-9 ns pulses focused with various beam smoothing options. The experiments have demonstrated excellent agreement between measured and predicted laser-target coupling in foils and hohlraums, even when extended to a longer pulse regime unattainable at previous laser facilities, validated the predicted effects of beam smoothing on intense laser beam propagation in long scale-length plasmas and begun to test 3-dimensional codes by extending the study of laser driven hydrodynamic jets to 3-dimensional geometries. (authors)

  9. The first target experiments on the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Landen, O.L.; Glenzer, S.H.; Froula, D.H.; Dewald, E.L.; Suter, L.J.; Schneider, M.B.; Hinkel, D.E.; Fernandez, J.C.; Kline, J.L.; Goldman, S.R.; Braun, D.G.; Celliers, P.M.; Moon, S.J.; Robey, H.S.; Lanier, N.E.; Glendinning, S.G.; Blue, B.E.; Wilde, B.H.; Jones, O.S.; Schein, J.; Divol, L.; Kalantar, D.H.; Campbell, K.M.; Holder, J.P.; McDonald, J.W.; Niemann, C.; Mackinnon, A.J.; Collins, G.W.; Bradley, D.K.; Eggert, J.H.; Hicks, D.G.; Gregori, G.; Kirkwood, R.K.; Young, B.K.; Foster, J.M.; Hansen, J.F.; Perry, T.S.; Munro, D.H.; Baldis, H.A.; Grim, G.P.; Heeter, R.F.; Hegelich, M.B.; Montgomery, D.S.; Rochau, G.A.; Olson, R.E.; Turner, R.E.; Workman, J.B.; Berger, R.L.; Cohen, B.I.; Kruer, W.L.; Langdon, A.B.; Langer, S.H.; Meezan, N.B.; Rose, H.A.; Still, C.H.; Williams, E.A.; Dodd, E.A.; Edwards, M.J.; Monteil, M.C.; Stevenson, R.M.; Thomas, B.R.; Coker, R.F.; Magelssen, G.R.; Rosen, P.A.; Stry, P.E.; Woods, D.; Weber, S.V.; Young, P.E.; Alvarez, S.; Armstrong, G.; Bahr, R.; Bourgade, G.L.; Bower, D.; Celeste, J.; Chrisp, M.; Compton, S.; Cox, J.; Constantin, C.; Costa, R.; Duncan, J.; Ellis, A.; Emig, J.; Gautier, C.; Greenwood, A.; Griffith, R.; Holdner, F.; Holtmeier, G.; Hargrove, D.; James, T.; Kamperschroer, J.; Kimbrough, J.; Landon, M.; Lee, F.D.; Malone, R.; May, M.; Montelongo, S.; Moody, J.; Ng, E.; Nikitin, A.; Pellinen, D.; Piston, K.; Poole, M.; Rekow, V.; Rhodes, M.; Shepherd, R.; Shiromizu, S.; Voloshin, D.; Warrick, A.; Watts, P.; Weber, F.; Young, P.; Arnold, P

    2007-08-15

    A first set of shock timing, laser-plasma interaction, hohlraum energetics and hydrodynamic experiments have been performed using the first 4 beams of the National Ignition Facility (NIF), in support of indirect drive Inertial Confinement Fusion (ICF) and High Energy Density Physics (HEDP). In parallel, a robust set of optical and X-ray spectrometers, interferometer, calorimeters and imagers have been activated. The experiments have been undertaken with laser powers and energies of up to 8 TW and 17 kJ in flattop and shaped 1-9 ns pulses focused with various beam smoothing options. The experiments have demonstrated excellent agreement between measured and predicted laser-target coupling in foils and hohlraums, even when extended to a longer pulse regime unattainable at previous laser facilities, validated the predicted effects of beam smoothing on intense laser beam propagation in long scale-length plasmas and begun to test 3-dimensional codes by extending the study of laser driven hydrodynamic jets to 3-dimensional geometries. (authors)

  10. 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.

  11. Antares facility for inertial-fusion experiments: status and plans

    International Nuclear Information System (INIS)

    Goldstone, P.D.; Allen, G.; Jansen, H.; Saxman, A.; Singer, S.; Thuot, M.

    1982-01-01

    Antares is a large, 30 to 40 kJ CO 2 laser system which will provide a base for experiments to determine the efficiency with which 10 μm light can be used to drive target implosions while maintaining an acceptable level of preheat. Construction of the facility is in the final stages and diagnostics for initial experiments are being designed and constructed with operations scheduled to begin early in FY-84. After an initial shakedown period, we expect to perform a series of measurements to determine the energy scaling of hot electron temperature and target coupling efficiency in selected set of targets including simple spheres. We also expect to continue experiments, now planned for Helios, to determine whether CO 2 -produced ions are appropriate for driving inertial fusion targets with acceptable efficiency (Helios experiments have demonstrated that as much as 40% of the incident light can be converted to fast ions). Details of these experiments, as well as plans for further experiments, are still being defined

  12. Radiological operating experience at FFTF [Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Bunch, W.L.; Prevo, P.R.

    1986-11-01

    The Fast Flux Test Facility has been in operation for approximately five years, including about one thousand days of full power operation of the Fast Test Reactor. During that time the collective dose equivalents received by operating personnel have been about two orders of magnitude lower than those typically received at commercial light water reactors. No major contamination problems have been encountered in operating and maintaining the plant, and release of radioactive gas to the environment has been minimal and well below acceptable limits. All shields have performed satisfactorily. Experience to date indicates an apparent radiological superiority of liquid metal reactor systems over current light water plants

  13. 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...

  14. Research and development experience

    International Nuclear Information System (INIS)

    Slater, J.B.

    1980-06-01

    In the early 1950s, Atomic Energy of Canada Limited (AECL), in collaboration with Canadian industry and the power utilities, started on the task of developing and establishing the CANDU power reactor system and the necessary industrial infrastructure. While international activity provided a useful background and information to support Canadian activities, there were several unique features of the CANDU reactor which demanded specific programs of research and development work with a physics orientation. The four major areas were basic reactor physics, reactor control, heavy water and tritium monitoring and instruments and, finally, the potential of alternative fuel cycles. These four topics are discussed with the objective of providing an overview of what has been accomplished and what remains to be done. (auth)

  15. Shuttle Laser Technology Experiment Facility (LTEF)-to-airplane lasercom experiment: Airplane considerations

    Science.gov (United States)

    Kalil, Ford

    1990-01-01

    NASA is considering the use of various airplanes for a Shuttle Laser Technology Experiment Facility (LTEF)-to-Airplane laser communications experiment. As supporting documentation, pertinent technical details are included about the potential use of airplanes located at Ames Research Center and Wallops Flight Facility. The effects and application of orbital mechanics considerations are also presented, including slant range, azimuth, elevation, and time. The pros and cons of an airplane equipped with a side port with a bubble window versus a top port with a dome are discussed.

  16. Safety Research Experiment Facilities, Idaho National Engineering Laboratory, Idaho. Draft environmental statement

    International Nuclear Information System (INIS)

    1977-01-01

    This environmental statement was prepared in accordance with the National Environmental Policy Act of 1969 (NEPA) in support of the Energy Research and Development Administration's (ERDA) proposal for legislative authorization and appropriations for the Safety Research Experiment Facilities (SAREF) Project. The purpose of the proposed project is to modify some existing facilities and provide a new test facility at the Idaho National Engineering Laboratory (INEL) for conducting fast breeder reactor (FBR) safety experiments. The SAREF Project proposal has been developed after an extensive study which identified the FBR safety research needs requiring in-reactor experiments and which evaluated the capability of various existing and new facilities to meet these needs. The proposed facilities provide for the in-reactor testing of large bundles of prototypical FBR fuel elements under a wide variety of conditions, ranging from those abnormal operating conditions which might be expected to occur during the life of an FBR power plant to the extremely low probability, hypothetical accidents used in the evalution of some design options and in the assessment of the long-term potential risk associated with wide-scale deployment of the FBR

  17. Laser fusion experiments, facilities and diagnostics at Lawrence Livermore Laboratory

    International Nuclear Information System (INIS)

    Ahlstrom, H.G.

    1980-02-01

    The progress of the LLL Laser Fusion Program to achieve high gain thermonuclear micro-explosions is discussed. Many experiments have been successfully performed and diagnosed using the large complex, 10-beam, 30 TW Shiva laser system. A 400 kJ design of the 20-beam Nova laser has been completed. The construction of the first phase of this facility has begun. New diagnostic instruments are described which provide one with new and improved resolution, information on laser absorption and scattering, thermal energy flow, suprathermal electrons and their effects, and final fuel conditions. Measurements were made on the absorption and Brillouin scattering for target irradiations at both 1.064 μm and 532 nm. These measurements confirm the expected increased absorption and reduced scattering at the shorter wavelength. Implosion experiments have been performed which have produced final fuel densities over the range of 10x to 100x liquid DT density

  18. New synchrotron powder diffraction facility for long-duration experiments.

    Science.gov (United States)

    Murray, Claire A; Potter, Jonathan; Day, Sarah J; Baker, Annabelle R; Thompson, Stephen P; Kelly, Jon; Morris, Christopher G; Yang, Sihai; Tang, Chiu C

    2017-02-01

    A new synchrotron X-ray powder diffraction instrument has been built and commissioned for long-duration experiments on beamline I11 at Diamond Light Source. The concept is unique, with design features to house multiple experiments running in parallel, in particular with specific stages for sample environments to study slow kinetic systems or processes. The instrument benefits from a high-brightness X-ray beam and a large area detector. Diffraction data from the commissioning work have shown that the objectives and criteria are met. Supported by two case studies, the results from months of measurements have demonstrated the viability of this large-scale instrument, which is the world's first dedicated facility for long-term studies (weeks to years) using synchrotron radiation.

  19. Advances in shock timing experiments on the National Ignition Facility

    International Nuclear Information System (INIS)

    Robey, H F; Celliers, P M; Moody, J D; Sater, J; Parham, T; Kozioziemski, B; Dylla- Spears, R; Ross, J S; LePape, S; Ralph, J E; Hohenberger, M; Dewald, E L; Berzak Hopkins, L; Kroll, J J; Yoxall, B E; Hamza, A V; Landen, O L; Edwards, M J; Boehly, T R; Nikroo, A

    2016-01-01

    Recent advances in shock timing experiments and analysis techniques now enable shock measurements to be performed in cryogenic deuterium-tritium (DT) ice layered capsule implosions on the National Ignition Facility (NIF). Previous measurements of shock timing in inertial confinement fusion (ICF) implosions were performed in surrogate targets, where the solid DT ice shell and central DT gas were replaced with a continuous liquid deuterium (D2) fill. These previous experiments pose two surrogacy issues: a material surrogacy due to the difference of species (D2 vs. DT) and densities of the materials used and a geometric surrogacy due to presence of an additional interface (ice/gas) previously absent in the liquid-filled targets. This report presents experimental data and a new analysis method for validating the assumptions underlying this surrogate technique. (paper)

  20. Advances in shock timing experiments on the National Ignition Facility

    Science.gov (United States)

    Robey, H. F.; Celliers, P. M.; Moody, J. D.; Sater, J.; Parham, T.; Kozioziemski, B.; Dylla-Spears, R.; Ross, J. S.; LePape, S.; Ralph, J. E.; Hohenberger, M.; Dewald, E. L.; Berzak Hopkins, L.; Kroll, J. J.; Yoxall, B. E.; Hamza, A. V.; Boehly, T. R.; Nikroo, A.; Landen, O. L.; Edwards, M. J.

    2016-03-01

    Recent advances in shock timing experiments and analysis techniques now enable shock measurements to be performed in cryogenic deuterium-tritium (DT) ice layered capsule implosions on the National Ignition Facility (NIF). Previous measurements of shock timing in inertial confinement fusion (ICF) implosions were performed in surrogate targets, where the solid DT ice shell and central DT gas were replaced with a continuous liquid deuterium (D2) fill. These previous experiments pose two surrogacy issues: a material surrogacy due to the difference of species (D2 vs. DT) and densities of the materials used and a geometric surrogacy due to presence of an additional interface (ice/gas) previously absent in the liquid-filled targets. This report presents experimental data and a new analysis method for validating the assumptions underlying this surrogate technique.

  1. Shock timing on the National Ignition Facility: First experiments

    Directory of Open Access Journals (Sweden)

    Celliers P.M.

    2013-11-01

    Full Text Available An experimental campaign to tune the initial shock compression sequence of capsule implosions on the National Ignition Facility (NIF was initiated in late 2010. The experiments use a NIF ignition-scale hohlraum and capsule that employs a re-entrant cone to provide optical access to the shocks as they propagate in the liquid deuterium-filled capsule interior. The strength and timing of the shock sequence is diagnosed with velocity interferometry that provides target performance data used to set the pulse shape for ignition capsule implosions that follow. From the start, these measurements yielded significant new information on target performance, leading to improvements in the target design. We describe the results and interpretation of the initial tuning experiments.

  2. Shock timing on the National Ignition Facility: First Experiments

    International Nuclear Information System (INIS)

    Celliers, P.M.; Robey, H.F.; Boehly, T.R.; Alger, E.; Azevedo, S.; Berzins, L.V.; Bhandarkar, S.D.; Bowers, M.W.; Brereton, S.J.; Callahan, D.; Castro, C.; Chandrasekaran, H.; Choate, C.; Clark, D.; Coffee, K.R.; Datte, P.S.; Dewald, E.L.; DiNicola, P.; Dixit, S.; Doeppner, T.; Dzenitis, E.; Edwards, M.J.; Eggert, J.H.; Fair, J.; Farley, D.R.; Frieders, G.; Gibson, C.R.; Giraldez, E.; Haan, S.; Haid, B.; Hamza, A.V.; Haynam, C.; Hicks, D.G.; Holunga, D.M.; Horner, J.B.; Jancaitis, K.; Jones, O.S.; Kalantar, D.; Kline, J.L.; Krauter, K.G.; Kroll, J.J.; LaFortune, K.N.; Pape, S.L.; Malsbury, T.; Maypoles, E.R.; Milovich, J.L.; Moody, J.D.; Moreno, K.; Munro, D.H.; Nikroo, A.; Olson, R.E.; Parham, T.; Pollaine, S.; Radousky, H.B.; Ross, G.F.; Sater, J.; Schneider, M.B.; Shaw, M.; Smith, R.F.; Thomas, C.A.; Throop, A.; Town, R.J.; Trummer, D.; Van Wonterghem, B.M.; Walters, C.F.; Widmann, K.; Widmayer, C.; Young, B.K.; Atherton, L.J.; Collins, G.W.; Landen, O.L.; Lindl, J.D.; MacGowan, B.J.; Meyerhofer, D.D.; Moses, E.I.

    2011-01-01

    An experimental campaign to tune the initial shock compression sequence of capsule implosions on the National Ignition Facility (NIF) was initiated in late 2010. The experiments use a NIF ignition-scale hohlraum and capsule that employs a reentrant cone to provide optical access to the shocks as they propagate in the liquid deuterium-filled capsule interior. The strength and timing of the shock sequence is diagnosed with velocity interferometry that provides target performance data used to set the pulse shape for ignition capsule implosions that follow. From the start, these measurements yielded significant new information on target performance, leading to improvements in the target design. We describe the results and interpretation of the initial tuning experiments.

  3. A review of experiments and results from the TREAT facility

    International Nuclear Information System (INIS)

    Deitrich, L.W.; Dickerman, C.E.; Klickman, A.E.; Wright, A.E.

    1998-01-01

    The Transient Reactor Test (TREAT) facility was designed and built in the late 1950s at Argonne National Laboratory (ANL) to provide a transient reactor for safety experiments on samples of reactor fuels. It first operated in 1959. Throughout its history, experiments conducted in TREAT have been important in establishing the behavior of a wide variety of reactor fuel elements under conditions predicted to occur in reactor accidents ranging from mild off-normal transients to hypothetical core disruptive accidents. For much of its history, TREAT was used primarily to test liquid-metal reactor fuel elements, initially for the Experimental Breeder Reactor-II (EBR-II), then for the Fast Flux Test Facility (FFTF), the Clinch River Breeder Reactor Plant (CRBRP), the British Prototype Fast Reactor (PFR), and finally for the Integral Fast Reactor (IFR). Both oxide and metal elements were tested in dry capsules and in flowing sodium loops. The data obtained were instrumental in establishing the behavior of the fuel under off-normal and accident conditions, a necessary part of the safety analysis of the various reactors. In addition, TREAT was used to test light water reactor (LWR) elements in a steam environment to obtain fission product release data under meltdown conditions. Studies are now under way on applications of TREAT to testing of the behavior of high-burnup LWR elements under reactivity-initiated accident (RIA) conditions using a high-pressure water loop

  4. First experiment on LMJ facility: pointing and synchronisation qualification

    Science.gov (United States)

    Henry, Olivier; Raffestin, Didier; Bretheau, Dominique; Luttmann, Michel; Graillot, Herve; Ferri, Michel; Seguineau, Frederic; Bar, Emmanuel; Patissou, Loic; Canal, Philippe; Sautarel, Franöise; Tranquille-Marques, Yves

    2017-10-01

    The LMJ (Laser mega Joule) facility at the CESTA site (Aquitaine, France) is a tool designed to deliver up to 1.2 MJ at 351 nm for plasma experiments. The experiment system will include 11 diagnostics: UV and X energy balances, imagers (Streak and stripe camera, CCD), spectrometers, and a Visar/pyrometer. The facility must be able to deliver, within the hour following the shot, all the results of the plasma diagnostics, alignment images and laser diagnostic measurements. These results have to be guaranteed in terms of conformity to the request and quality of measurement. The end of 2016 was devoted to the qualification of system pointing on target and synchronization within and between beams. The shots made with two chains (divided in 4 quads - 8 laser beams) have achieved 50 µm of misalignment accuracy (chain and quad channel) and a synchronization accuracy in the order of 50 ps . The performances achieved for plasma diagnostic (in the order of less 100 µm of alignment and timing accuracy less than 150 ps) comply with expectations. At the same time the first automatic sequences were tested. They allowed a shot on target every 6h:30 and in some case twice a day by reducing preparation actions, leading to a sequence of 4h:00.

  5. Experience in the upgrading of radioactive waste disposal facility 'Ekores'

    International Nuclear Information System (INIS)

    Rozdyalovskaya, L.

    2000-01-01

    The national Belarus radioactive disposal facility 'Ekores' is designed for waste from nuclear applications in industry, medicine and research. Currently 12-20 tons of waste and over 6000 various types spent sources annually come to the 'Ekores'. Total activity in the vaults is evaluated as 352.8 TBq. Approximately 150 000 spent sources disposed of in the vaults and wells have total activity about 1327 TBq. In 1997 the Government initiated a project for the facility reconstruction in order to upgrade radiological safety of the site by creating adequate safety conditions for managing and storage of the waste. The reconstruction project developed by Belarus specialists has been reviewed by IAEA experts. This covers modernising technologies for new coming waste and also that the waste currently disposed in the pits is retrieved, sorted and treated in the same way as the new coming waste

  6. Experience in the Application of INES scale to events in the Spanish Radioactive facilities

    International Nuclear Information System (INIS)

    Ramirez, M. L.; Alvarez, C.

    2002-01-01

    In February 2001, the International Atomic Energy Agency (IAEA) and the Nuclear energy Agency of the OECD (NEA) published a new edition of the INES User's Manual for the classification of nuclear events. One of the new developments introduced with respect to the scope of the former Manual was the inclusion within the INES of any event associated with radioactive material and/or radiation. This would include events occurred in radioactive facilities so the INES would apply not only to events in nuclear facilities. During the publication process some doubts rose about the applicability of INES to other non nuclear types of events. The IAEA was open to the future development of more practical guidance for the application of the scale. Since the beginning of 2001 the Consejo de Seguridad Nuclear (CSN) has been using INES to test the applicability of the system to classify events in radioactive facilities. A total of 31 events occurred at Spanish radioactive facilities has been classified applying INES scale and a report was sent to IAEA to publish our experience. The objective of this presentation is to introduce the experience obtained by the application of the International Nuclear Events Scale (INES) to classify events in radioactive facilities in Spain and to present several issues raised during its application that may need further development in a practical guidance. (Author)

  7. 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.

  8. 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

  9. Experiments on injection performance of SMART ECC facility using SWAT

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Young Il; Cho, Seok; Ko, Yung Joo; Min, Kyoung Ho; Shin, Yong Cheol; Kwon, Tae Soon; Yi, Sung Jae; Lee, Won Jae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    SMART (System-integrated Modular Advanced ReacTor), an advanced integrated PWR is now in the under developing stages by KAERI. Such integral PWR excludes large-size piping of the primary system of conventional PWR and incorporates the SGs into RPV, which means no LBLOCA could occur in SMART. Therefore, the SBLOCA is considered as a major DBA (Design Basis Accident) in SMART and it is mainly analyzed by using TASS/SMR computer code. The TASS/SMR code should be validated using experimental data from both Integral Effect Test and Separate Effect Test facilities. To investigate injection performance of the ECC system, on SET facility, named as SWAT (SMART ECC Water Asymmetric Two-phase choking test facility), has been constructed at KAERI. The SWAT simulates the geometric configurations of the SG-side upper downcomer annulus and ECCSs of those of SMART. It is designed based on the modified linear scaling method with a scaling ratio of 1/5, to preserve the geometrical similarity and minimize gravitational distortion. The purpose of the SWAT tests is to investigate the safety injection performance, such as the ECC bypass in the downcomer and the penetration rate in the core during the SBLOCA, and hence to produce experimental data to validate and the prediction capability of safety analysis codes, TASS/SMR

  10. 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.)

  11. Design Optimisation of a High Intensity Beam Facility and Feasibility Experiment of a Solid Fragmented Target

    CERN Document Server

    Charitonidis, Nikolaos; Rivkin, Leonid

    2014-06-13

    The present PhD thesis describes the design, execution and results of the HRMT-10 experiment performed at the HiRadMat facility of the CERN/SPS complex. The first part of the thesis covers the design optimization studies of the HiRadMat facility, focusing in particular on the radiation protection issues. A detailed Monte-Carlo model of the facility has been developed and validated through comparison with measurements. A very satisfactory agreement between the simulation and the experimental data is observed. In the second part of this thesis, a novel feasibility experiment of a fragmented solid target for a future Neutrino Factory or a Super Beam facility, able to support high beam powers ( 1 MW) is presented in detail. A solid granular target has been proposed as an interesting alternative to an open Hg jet target, presently considered as the baseline for such facilities, but posing considerable technical challenges. The HRMT-10 experiment seeks to address the lack of experimental data of the feasibility of...

  12. 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

  13. Software Development Infrastructure for the FAIR Experiments

    International Nuclear Information System (INIS)

    Uhlig, F; Al-Turany, M; Bertini, D; Karabowicz, R

    2011-01-01

    The proposed project FAIR (Facility for Anti-proton and Ion Research) is an international accelerator facility of the next generation. It builds on top of the experience and technological developments already made at the existing GSI facility, and incorporate new technological concepts. The four scientific pillars of FAIR are NUSTAR (nuclear structure and astrophysics), PANDA (QCD studies with cooled beams of anti-protons), CBM (physics of hadronic matter at highest baryon densities), and APPA (atomic physics, plasma physics, and applications). The FairRoot framework used by all of the big FAIR experiments as a base for their own specific developments, provides basic functionality like IO, geometry handling etc. The challenge is to support all the different experiments with their heterogeneous requirements. Due to the limited manpower, one of the first design decisions was to (re)use as much as possible already available and tested software and to focus on the development of the framework. Beside the framework itself, the FairRoot core team also provides some software development tools. We will describe the complete set of tools in this article. The Makefiles for all projects are generated using CMake. For software testing and the corresponding quality assurance, we use CTest to generate the results and CDash as web front end. The tools are completed by subversion as source code repository and trac as tool for the complete source code management. This set of tools allows us to offer the full functionality we have for FairRoot also to the experiments based on FairRoot.

  14. Simulation of photofission experiments at the ELI-NP facility

    International Nuclear Information System (INIS)

    Constantin, P.; Balabanski, D.L.; Cuong, P.V.

    2016-01-01

    An extensive experimental program for the study of photofission will take place at the Extreme Light Infrastructure – Nuclear Physics (ELI-NP) facility, where different actinide targets will be exposed to a brilliant gamma beam to produce fission fragments. We report on the implementation within the Geant4 simulation toolkit of the photofission process, of related background processes, and of extended ionic charge parameterization. These developments are used to evaluate the production rates of photofission fragments and their release efficiency from the actinide targets.

  15. Simulation of photofission experiments at the ELI-NP facility

    Energy Technology Data Exchange (ETDEWEB)

    Constantin, P., E-mail: paul.constantin@eli-np.ro [Extreme Light Infrastructure – Nuclear Physics, “Horia Hulubei” National Institute for Physics and Nuclear Engineering, Str. Reactorului 30, 077125 Bucharest Magurele (Romania); Balabanski, D.L. [Extreme Light Infrastructure – Nuclear Physics, “Horia Hulubei” National Institute for Physics and Nuclear Engineering, Str. Reactorului 30, 077125 Bucharest Magurele (Romania); Cuong, P.V. [Centre of Nuclear Physics, Institute of Physics, Vietnam Academy of Science and Technology, Hanoi (Viet Nam)

    2016-04-01

    An extensive experimental program for the study of photofission will take place at the Extreme Light Infrastructure – Nuclear Physics (ELI-NP) facility, where different actinide targets will be exposed to a brilliant gamma beam to produce fission fragments. We report on the implementation within the Geant4 simulation toolkit of the photofission process, of related background processes, and of extended ionic charge parameterization. These developments are used to evaluate the production rates of photofission fragments and their release efficiency from the actinide targets.

  16. Steam line rupture experiments with the PPOOLEX test facility

    International Nuclear Information System (INIS)

    Laine, J.; Puustinen, M.

    2008-07-01

    The results of the steam line rupture experiment series in 2007 with the scaled down PPOOLEX test facility designed and constructed at Lappeenranta University of Technology are reported. The test facility is a closed stainless steel vessel divided into two compartments, dry well and wet well. Air was blown into the dry well compartment and from there through a DN200 blowdown pipe to the condensation pool. Altogether five experiments, each consisting of several blows (tests), were carried out. The main purpose of the experiment series was to study the initial phase of a postulated steam line break accident inside a BWR containment. Specifically, thermal stratification in the dry well compartment and ejection of water plug from the blowdown pipe were of interest. In addition, the effect of counterpressure on bubble dynamics was studied. A temperature difference of approximately 15 deg. C between the upper and lower part of the dry well was measured. In the wet well gas space, a temperature difference of more than 30 deg. C was registered. These were measured during the compression period of the tests. Towards the end of the tests the temperature differences tended to disappear. To get a more detailed picture of temperature distribution in the wet well, especially close to the water level, a dense net of measurements is required in future experiments. In longer experiments, heat conduction to structures and heat losses to surroundings should also be taken into account. Ejection of water plugs from the blowdown pipe did not cause notable loads to the structures due to the suppressing effect of the dry well compartment. The maximum measured pressure pulse at the pool bottom was only 10 kPa and the maximum strain amplitude at the pool bottom rounding was negligible both in axial and circumferential direction. As the counterpressure of the system increased, but the flow rate remained the same, the maximum size of the air bubbles at the blowdown pipe outlet got smaller and

  17. Steam line rupture experiments with the PPOOLEX test facility

    Energy Technology Data Exchange (ETDEWEB)

    Laine, J.; Puustinen, M. (Lappeenranta Univ. of Technology, Nuclear Safety Research Unit (Finland))

    2008-07-15

    The results of the steam line rupture experiment series in 2007 with the scaled down PPOOLEX test facility designed and constructed at Lappeenranta University of Technology are reported. The test facility is a closed stainless steel vessel divided into two compartments, dry well and wet well. Air was blown into the dry well compartment and from there through a DN200 blowdown pipe to the condensation pool. Altogether five experiments, each consisting of several blows (tests), were carried out. The main purpose of the experiment series was to study the initial phase of a postulated steam line break accident inside a BWR containment. Specifically, thermal stratification in the dry well compartment and ejection of water plug from the blowdown pipe were of interest. In addition, the effect of counterpressure on bubble dynamics was studied. A temperature difference of approximately 15 deg. C between the upper and lower part of the dry well was measured. In the wet well gas space, a temperature difference of more than 30 deg. C was registered. These were measured during the compression period of the tests. Towards the end of the tests the temperature differences tended to disappear. To get a more detailed picture of temperature distribution in the wet well, especially close to the water level, a dense net of measurements is required in future experiments. In longer experiments, heat conduction to structures and heat losses to surroundings should also be taken into account. Ejection of water plugs from the blowdown pipe did not cause notable loads to the structures due to the suppressing effect of the dry well compartment. The maximum measured pressure pulse at the pool bottom was only 10 kPa and the maximum strain amplitude at the pool bottom rounding was negligible both in axial and circumferential direction. As the counterpressure of the system increased, but the flow rate remained the same, the maximum size of the air bubbles at the blowdown pipe outlet got smaller and

  18. 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

  19. HITRAP: A Facility for Experiments with Trapped Highly Charged Ions

    International Nuclear Information System (INIS)

    Quint, W.; Dilling, J.; Djekic, S.; Haeffner, H.; Hermanspahn, N.; Kluge, H.-J.; Marx, G.; Moore, R.; Rodriguez, D.; Schoenfelder, J.; Sikler, G.; Valenzuela, T.; Verdu, J.; Weber, C.; Werth, G.

    2001-01-01

    HITRAP is a planned ion trap facility for capturing and cooling of highly charged ions produced at GSI in the heavy-ion complex of the UNILAC-SIS accelerators and the ESR storage ring. In this facility heavy highly charged ions up to uranium will be available as bare nuclei, hydrogen-like ions or few-electron systems at low temperatures. The trap for receiving and studying these ions is designed for operation at extremely high vacuum by cooling to cryogenic temperatures. The stored highly charged ions can be investigated in the trap itself or can be extracted from the trap at energies up to about 10 keV/q. The proposed physics experiments are collision studies with highly charged ions at well-defined low energies (eV/u), high-accuracy measurements to determine the g-factor of the electron bound in a hydrogen-like heavy ion and the atomic binding energies of few-electron systems, laser spectroscopy of HFS transitions and X-ray spectroscopy

  20. 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.

  1. 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

  2. Polar-direct-drive experiments on the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Hohenberger, M.; Radha, P. B.; Myatt, J. F.; Marozas, J. A.; Marshall, F. J.; Michel, D. T.; Regan, S. P.; Seka, W.; Shvydky, A.; Sangster, T. C.; Betti, R.; Boehly, T. R.; Bonino, M. J.; Collins, T. J. B.; Craxton, R. S.; Delettrez, J. A.; Edgell, D. H.; Epstein, R.; Fiksel, G.; Froula, D. H. [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623-1299 (United States); and others

    2015-05-15

    To support direct-drive inertial confinement fusion experiments at the National Ignition Facility (NIF) [G. H. Miller, E. I. Moses, and C. R. Wuest, Opt. Eng. 43, 2841 (2004)] in its indirect-drive beam configuration, the polar-direct-drive (PDD) concept [S. Skupsky et al., Phys. Plasmas 11, 2763 (2004)] has been proposed. Ignition in PDD geometry requires direct-drive–specific beam smoothing, phase plates, and repointing the NIF beams toward the equator to ensure symmetric target irradiation. First experiments to study the energetics and preheat in PDD implosions at the NIF have been performed. These experiments utilize the NIF in its current configuration, including beam geometry, phase plates, and beam smoothing. Room-temperature, 2.2-mm-diam plastic shells filled with D{sub 2} gas were imploded with total drive energies ranging from ∼500 to 750 kJ with peak powers of 120 to 180 TW and peak on-target irradiances at the initial target radius from 8 × 10{sup 14} to 1.2 × 10{sup 15 }W/cm{sup 2}. Results from these initial experiments are presented, including measurements of shell trajectory, implosion symmetry, and the level of hot-electron preheat in plastic and Si ablators. Experiments are simulated with the 2-D hydrodynamics code DRACO including a full 3-D ray-trace to model oblique beams, and models for nonlocal electron transport and cross-beam energy transport (CBET). These simulations indicate that CBET affects the shell symmetry and leads to a loss of energy imparted onto the shell, consistent with the experimental data.

  3. CHARM 2010: Experiment summary and future charm facilities

    Energy Technology Data Exchange (ETDEWEB)

    Appel, Jeffrey A.; /Fermilab

    2010-12-01

    The CHARM 2010 meeting had over 30 presentations of experimental results, plus additional future facilities talks just before this summary talk. Since there is not enough time to even summarize all that has been shown from experiments and to recognize all the memorable plots and results - tempting as it is to reproduce the many clean signals and data vs theory figures, the quantum correlations plots, and the D-mixing plots before and after the latest CLEO-c data is added. So, this review will give only my personal observations, exposing my prejudices and my areas of ignorance, no doubt. This overview will be at a fairly high level of abstraction - no re-showing individual plots or results. I ask the forgiveness of those who will have been slighted in this way - meaning all the presents.

  4. Experience in startup and operation of fast flux facility

    International Nuclear Information System (INIS)

    Moffitt, W.C.

    1980-01-01

    The testing program was structured to perform all testing under formal testing procedures with a test engineer as the test director and the plant operators operating the systems and equipment. This provided excellent training and experience for the operators in preparation for eventual reactor operation. Operations preparations for the testing and operation activities has consisted of academic training, formal on-the-job training including systems operation and examinations by persons with an expert knowledge on that portion of the plant, training at EBR-II and the High Temperature Sodium Facility for selected senior operators, operating procedure preparation, training on an FFTF Control Room operator training simulator, and formal written, oral and operating examinations

  5. Gas-filled hohlraum experiments at the National Ignition Facility

    International Nuclear Information System (INIS)

    Fernandez, Juan C.; Goldman, S.R.; Kline, J.L.; Dodd, E.S.; Gautier, C.; Grim, G.P.; Hegelich, B.M.; Montgomery, D.S.; Lanier, N.E.; Rose, H.; Schmidt, D.W.; Workman, J.B.; Braun, D.G.; Dewald, E.L.; Landen, O.L.; Campbell, K.M.; Holder, J.P.; MacKinnon, A.J.; Niemann, C.; Schein, J.

    2006-01-01

    Experiments done at the National Ignition Facility laser [J. A. Paisner, E. M. Campbell, and W. Hogan, Fusion Technol. 26, 755 (1994)] using gas-filled hohlraums demonstrate a key ignition design feature, i.e., using plasma pressure from a gas fill to tamp the hohlraum-wall expansion for the duration of the laser pulse. Moreover, our understanding of hohlraum energetics and the ability to predict the hohlraum soft-x-ray drive has been validated in ignition-relevant conditions. Finally, the laser reflectivity from stimulated Raman scattering in the fill plasma, a key threat to hohlraum performance, is shown to be suppressed by choosing a design with a sufficiently high ratio of electron temperature to density

  6. Operating experience with superconducting cavities at the TESLA test facility

    International Nuclear Information System (INIS)

    Moeller, Wolf-Dietrich

    2003-01-01

    A description of the TESLA Test Facility, which has been set up at DESY by the TeV Energy Superconducting Accelerator (TESLA) collaboration, will be given as it is now after five years of installation and operation. The experience with the first three modules, each containing 8 superconducting 9-cell cavities, installed and operated in the TTF-linac will be described. The measurements in the vertical and horizontal cryostats as well as in the modules will be compared. Recent results of the operation at the TESLA design current, macropulses of 800 μsec with bunches of 3.2 nC at a rate of 2.25 MHz are given. New measurement results of the higher order modes (HOM) will be presented. The operation and optimisation of the TTF Free Electron Laser (TTF-FEL) will also be covered in this paper. (author)

  7. 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

  8. 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

  9. Atlas Pulsed Power Facility for High Energy Density Physics Experiments

    International Nuclear Information System (INIS)

    Miller, R.B.; Ballard, E.O.; Barr, G.W.; Bowman, D.W.; Chochrane, J.C.; Davis, H.A.; Elizondo, J.M.; Gribble, R.F.; Griego, J.R.; Hicks, R.D.; Hinckley, W.B.; Hosack, K.W.; Nielsen, K.E.; Parker, J.V.; Parsons, M.O.; Rickets, R.L.; Salazar, H.R.; Sanchez, P.G.; Scudder, D.W.; Shapiro, C.; Thompson, M.C.; Trainor, R.J.; Valdez, G.A.; Vigil, B.N.; Watt, R.G.; Wysock, F.J.

    1999-01-01

    The Atlas facility, now under construction at Los Alamos National Laboratory (LANL), will provide a unique capability for performing high-energy-density experiments in support of weapon-physics and basic-research programs. It is intended to be an international user facility, providing opportunities for researchers from national laboratories and academic institutions around the world. Emphasizing institutions around the world. Emphasizing hydrodynamic experiments, Atlas will provide the capability for achieving steady shock pressures exceeding 10-Mbar in a volume of several cubic centimeters. In addition, the kinetic energy associated with solid liner implosion velocities exceeding 12 km/s is sufficient to drive dense, hydrodynamic targets into the ionized regime, permitting the study of complex issues associated with strongly-coupled plasmas. The primary element of Atlas is a 23-MJ capacitor bank, comprised of 96 separate Marx generators housed in 12 separate oil-filled tanks, surrounding a central target chamber. Each tank will house two, independently-removable maintenance units, with each maintenance unit consisting of four Marx modules. Each Marx module has four capacitors that can each be charged to a maximum of 60 kilovolts. When railgap switches are triggered, the marx modules erect to a maximum of 240 kV. The parallel discharge of these 96 Marx modules will deliver a 30-MA current pulse with a 4-5-micros risetime to a cylindrical, imploding liner via 24 vertical, tri-plate, oil-insulated transmission lines. An experimental program for testing and certifying all Marx and transmission line components has been completed. A complete maintenance module and its associated transmission line (the First Article) are now under construction and testing. The current Atlas schedule calls for construction of the machine to be complete by August, 2000. Acceptance testing is scheduled to begin in November, 2000, leading to initial operations in January, 2001

  10. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    Energy Technology Data Exchange (ETDEWEB)

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  11. Proton therapy detector studies under the experience gained at the CATANA facility

    International Nuclear Information System (INIS)

    Cuttone, G.; Cirrone, G.A.P.; Di Rosa, F.; Lojacono, P.A.; Lo Nigro, S.; Marino, C.; Mongelli, V.; Patti, I.V.; Pittera, S.; Raffaele, L.; Russo, G.; Sabini, M.G.; Salamone, V.; Valastro, L.M.

    2007-01-01

    Proton therapy represents the most promising radiotherapy technique for external tumor treatments. At Laboratori Nazionali del Sud of the Istituto Nazionale di Fisica Nucleare (INFN-LNS), Catania (I), a proton therapy facility is active since March 2002 and 140 patients, mainly affected by choroidal and iris melanoma, have been successfully treated. Proton beams are characterized by higher dose gradients and linear energy transfer with respect to the conventional photon and electron beams, commonly used in medical centers for radiotherapy. In this paper, we report the experience gained in the characterization of different dosimetric systems, studied and/or developed during the last ten years in our proton therapy facility

  12. Proton therapy detector studies under the experience gained at the CATANA facility

    Energy Technology Data Exchange (ETDEWEB)

    Cuttone, G.; Cirrone, G.A.P.; Di Rosa, F. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy); Lojacono, P.A. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy); Dipartimento di Fisica ed Astronomia, Universita degli Studi di Catania (Italy); Lo Nigro, S.; Marino, C. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy); Dipartimento di Fisica ed Astronomia, Universita degli Studi di Catania (Italy); Centro Siciliano di Fisica Nucleare e Struttura della Materia, Catania (Italy); Mongelli, V. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy); Dipartimento di Fisica ed Astronomia, Universita degli Studi di Catania (Italy); Patti, I.V. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy); Pittera, S. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy); Dipartimento di Fisica ed Astronomia, Universita degli Studi di Catania (Italy); Centro Siciliano di Fisica Nucleare e Struttura della Materia, Catania (Italy); Raffaele, L. [A.O.U. Policlinico, Universita degli Studi di Catania (Italy); Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy); Russo, G. [Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy); Dipartimento di Fisica ed Astronomia, Universita degli Studi di Catania (Italy); Sabini, M.G. [A.O. Cannizzaro, Catania (Italy); Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy); Salamone, V.; Valastro, L.M. [A.O.U. Policlinico, Universita degli Studi di Catania (Italy); Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali dei Sud, Catania (Italy)

    2007-10-15

    Proton therapy represents the most promising radiotherapy technique for external tumor treatments. At Laboratori Nazionali del Sud of the Istituto Nazionale di Fisica Nucleare (INFN-LNS), Catania (I), a proton therapy facility is active since March 2002 and 140 patients, mainly affected by choroidal and iris melanoma, have been successfully treated. Proton beams are characterized by higher dose gradients and linear energy transfer with respect to the conventional photon and electron beams, commonly used in medical centers for radiotherapy. In this paper, we report the experience gained in the characterization of different dosimetric systems, studied and/or developed during the last ten years in our proton therapy facility.

  13. Proton therapy detector studies under the experience gained at the CATANA facility

    Science.gov (United States)

    Cuttone, G.; Cirrone, G. A. P.; Di Rosa, F.; Lojacono, P. A.; Lo Nigro, S.; Marino, C.; Mongelli, V.; Patti, I. V.; Pittera, S.; Raffaele, L.; Russo, G.; Sabini, M. G.; Salamone, V.; Valastro, L. M.

    2007-10-01

    Proton therapy represents the most promising radiotherapy technique for external tumor treatments. At Laboratori Nazionali del Sud of the Istituto Nazionale di Fisica Nucleare (INFN-LNS), Catania (I), a proton therapy facility is active since March 2002 and 140 patients, mainly affected by choroidal and iris melanoma, have been successfully treated. Proton beams are characterized by higher dose gradients and linear energy transfer with respect to the conventional photon and electron beams, commonly used in medical centers for radiotherapy.In this paper, we report the experience gained in the characterization of different dosimetric systems, studied and/or developed during the last ten years in our proton therapy facility.

  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. Technology of mirror machines: LLL facilities for magnetic mirror fusion experiments

    International Nuclear Information System (INIS)

    Batzer, T.H.

    1977-01-01

    Significant progress in plasma confinement and temperature has been achieved in the 2XIIB facility at Livermore. These encouraging results, and their theoretical corroboration, have provided a firm basis for the design of a new generation of magnetic mirror experiments, adding support to the mirror concept of a fusion reactor. Two new mirror experiments have been proposed to succeed the currently operating 2XIIB facility. The first of these called TMX (Tandem Mirror Experiment) has been approved and is currently under construction. TMX is designed to utilize the intrinsic positive plasma potential of two strong, and relatively small, minimum B mirror cells to enhance the confinement of a much larger, magnetically weaker, centrally-located mirror cell. The second facility, MFTF (Mirror Fusion Test Facility), is currently in preliminary design with line item approval anticipated for FY 78. MFTF is designed primarily to exploit the experimental and theoretical results derived from 2XIIB. Beyond that, MFTF will develop the technology for the transition from the present small mirror experiments to large steady-state devices such as the mirror FERF/FTR. The sheer magnitude of the plasma volume, magnetic field, neutral beam power, and vacuum pumping capacity, particularly in the case of MFTF, has placed new and exciting demands on engineering technology. An engineering overview of MFTF, TMX, and associated MFE activities at Livermore will be presented

  16. Summarisation of construction and commissioning experience for nuclear power integrated test facility

    International Nuclear Information System (INIS)

    Xiao Zejun; Jia Dounan; Jiang Xulun; Chen Bingde

    2003-01-01

    Since the foundation of Nuclear Power Institute of China, it has successively designed various engineering experimental facilities, and constructed nuclear power experimental research base, and accumulated rich construction experiences of nuclear power integrated test facility. The author presents experience on design, construction and commissioning of nuclear power integrated test facility

  17. MagLev Cobra: Test Facilities and Operational Experiments

    International Nuclear Information System (INIS)

    Sotelo, G G; Dias, D H J N; De Oliveira, R A H; Ferreira, A C; De Andrade, R Jr; Stephan, R M

    2014-01-01

    The superconducting MagLev technology for transportation systems is becoming mature due to the research and developing effort of recent years. The Brazilian project, named MagLev-Cobra, started in 1998. It has the goal of developing a superconducting levitation vehicle for urban areas. The adopted levitation technology is based on the diamagnetic and the flux pinning properties of YBa 2 Cu 3 O 7−δ (YBCO) bulk blocks in the interaction with Nd-Fe-B permanent magnets. A laboratory test facility with permanent magnet guideway, linear induction motor and one vehicle module is been built to investigate its operation. The MagLev-Cobra project state of the art is presented in the present paper, describing some construction details of the new test line with 200 m.

  18. MagLev Cobra: Test Facilities and Operational Experiments

    Science.gov (United States)

    Sotelo, G. G.; Dias, D. H. J. N.; de Oliveira, R. A. H.; Ferreira, A. C.; De Andrade, R., Jr.; Stephan, R. M.

    2014-05-01

    The superconducting MagLev technology for transportation systems is becoming mature due to the research and developing effort of recent years. The Brazilian project, named MagLev-Cobra, started in 1998. It has the goal of developing a superconducting levitation vehicle for urban areas. The adopted levitation technology is based on the diamagnetic and the flux pinning properties of YBa2Cu3O7-δ (YBCO) bulk blocks in the interaction with Nd-Fe-B permanent magnets. A laboratory test facility with permanent magnet guideway, linear induction motor and one vehicle module is been built to investigate its operation. The MagLev-Cobra project state of the art is presented in the present paper, describing some construction details of the new test line with 200 m.

  19. Commissioning experience and beam physics measurements at the SwissFEL Injector Test Facility

    Directory of Open Access Journals (Sweden)

    T. Schietinger

    2016-10-01

    Full Text Available The SwissFEL Injector Test Facility operated at the Paul Scherrer Institute between 2010 and 2014, serving as a pilot plant and test bed for the development and realization of SwissFEL, the x-ray Free-Electron Laser facility under construction at the same institute. The test facility consisted of a laser-driven rf electron gun followed by an S-band booster linac, a magnetic bunch compression chicane and a diagnostic section including a transverse deflecting rf cavity. It delivered electron bunches of up to 200 pC charge and up to 250 MeV beam energy at a repetition rate of 10 Hz. The measurements performed at the test facility not only demonstrated the beam parameters required to drive the first stage of an FEL facility, but also led to significant advances in instrumentation technologies, beam characterization methods and the generation, transport and compression of ultralow-emittance beams. We give a comprehensive overview of the commissioning experience of the principal subsystems and the beam physics measurements performed during the operation of the test facility, including the results of the test of an in-vacuum undulator prototype generating radiation in the vacuum ultraviolet and optical range.

  20. Target designs for energetics experiments on the National Ignition Facility

    International Nuclear Information System (INIS)

    Meezan, N B; Glenzer, S H; Suter, L J

    2008-01-01

    The goal of the first hohlraum energetics experiments on the National Ignition Facility (NIF) [G. H. Miller et al, Optical Eng. 43, 2841 (2004)] is to select the hohlraum design for the first ignition experiments. Sub-scale hohlraums heated by 96 of the 192 laser beams on the NIF are used to emulate the laser-plasma interaction behavior of ignition hohlraums. These 'plasma emulator' targets are 70% scale versions of the 1.05 MJ, 300 eV ignition hohlraum and have the same energy-density as the full-scale ignition designs. Radiation-hydrodynamics simulations show that the sub-scale target is a good emulator of plasma conditions inside the ignition hohlraum, reproducing density n e within 10% and temperature T e within 15% along a laser beam path. Linear backscatter gain analysis shows the backscatter risk to be comparable to that of the ignition target. A successful energetics campaign will allow the National Ignition Campaign to focus its efforts on optimizing ignition hohlraums with efficient laser coupling

  1. The Holifield Radioactive Ion Beams Facility (HRIBF) - getting ready to do experiments

    International Nuclear Information System (INIS)

    Shapira, D.; Lewis, T.A.

    1998-01-01

    The conversion of the HHIRF facility to a Radioactive Ion Beam facility started in 1994. In this ISOL type facility the Cyclotron has been re-fitted as a driver providing high intensity proton beams which react with the target from which the radioactive products are extracted and then accelerated in the Tandem Electrostatic Accelerator to the desired energy for nuclear science studies. Facilities for nuclear physics experiments are at different stages of development: A Recoil Mass Spectrometer (RMS) with a complement of detectors at the focal plane and around the target is used primarily for nuclear structure studies. A large recoil separator combining velocity and momentum selection, with its complement of focal plane detectors, will be dedicated to measurements relevant to nuclear astrophysics. The Enge Split Pole spectrograph is being re-fitted for operation in a gas filled mode, making it a more versatile tool for nuclear reaction studies. With the new experimental equipment being commissioned and the prospects of running experiments with low intensity radioactive beams a significant effort to develop equipment for beam diagnostics is underway. Some of the efforts and results in developing beam diagnostic tools will be described

  2. 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.

  3. 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

  4. Multiple blowdown pipe experiments with the PPOOLEX facility

    International Nuclear Information System (INIS)

    Puustinen, M.; Laine, J.; Raesaenen, A.

    2011-03-01

    This report summarizes the results of the experiments with two steel blowdown pipes carried out with the scaled down PPOOLEX test facility designed and constructed at Lappeenranta University of Technology. Steam was blown into the dry well compartment and from there through the blowdown pipes to the condensation pool. The main purpose of the experiment series was to study chugging phenomena (rapid condensation) while steam is discharged through two parallel blowdown pipes into the condensation pool filled with sub-cooled water. Particularly, the aim was to study if the pipe material (polycarbonate) used in the earlier experiment series with two blowdown pipes has had an effect on the general chugging behaviour and measured loads. In the experiments the initial temperature of the pool water was 20 deg. C. The steam flow rate ranged from 220 g/s to 2 350 g/s and the temperature of incoming steam from 148 deg. C to 207 deg. C. The formation and collapse of steam bubbles and the movement of the steam/water interface inside the pipes was non-synchronous. There could be even a 70 ms time difference between the occurrences of steam bubble collapses at the outlets of the two pipes. There was no clear pattern in which pipe the steam bubble first starts to collapse. Several successive bubbles could collapse first in either pipe but then the order changed for a single or several cycles. High pressure loads were measured inside the blowdown pipes due to rapid condensation of the steam volumes in the pipes and resulting water hammer effects. The loads seemed to be higher in pipe 1 than in pipe 2. An explanation for this could be a possible unequal distribution of steam flow between the two pipes. The pipe material has an effect on the condensation phenomena inside the blowdown pipes. A huge difference in the measured pressure curves inside the pipes could be observed compared to the experiments with the polycarbonate pipes. With the same test conditions the amplitude of the

  5. Multiple blowdown pipe experiments with the PPOOLEX facility

    Energy Technology Data Exchange (ETDEWEB)

    Puustinen, M.; Laine, J.; Raesaenen, A. (Lappeenranta Univ. of Technology, Nuclear Safety Research Unit (Finland))

    2011-03-15

    This report summarizes the results of the experiments with two steel blowdown pipes carried out with the scaled down PPOOLEX test facility designed and constructed at Lappeenranta University of Technology. Steam was blown into the dry well compartment and from there through the blowdown pipes to the condensation pool. The main purpose of the experiment series was to study chugging phenomena (rapid condensation) while steam is discharged through two parallel blowdown pipes into the condensation pool filled with sub-cooled water. Particularly, the aim was to study if the pipe material (polycarbonate) used in the earlier experiment series with two blowdown pipes has had an effect on the general chugging behaviour and measured loads. In the experiments the initial temperature of the pool water was 20 deg. C. The steam flow rate ranged from 220 g/s to 2 350 g/s and the temperature of incoming steam from 148 deg. C to 207 deg. C. The formation and collapse of steam bubbles and the movement of the steam/water interface inside the pipes was non-synchronous. There could be even a 70 ms time difference between the occurrences of steam bubble collapses at the outlets of the two pipes. There was no clear pattern in which pipe the steam bubble first starts to collapse. Several successive bubbles could collapse first in either pipe but then the order changed for a single or several cycles. High pressure loads were measured inside the blowdown pipes due to rapid condensation of the steam volumes in the pipes and resulting water hammer effects. The loads seemed to be higher in pipe 1 than in pipe 2. An explanation for this could be a possible unequal distribution of steam flow between the two pipes. The pipe material has an effect on the condensation phenomena inside the blowdown pipes. A huge difference in the measured pressure curves inside the pipes could be observed compared to the experiments with the polycarbonate pipes. With the same test conditions the amplitude of the

  6. Experience Learning and Community Development

    Directory of Open Access Journals (Sweden)

    Nena Mijoč

    1996-12-01

    Full Text Available Research in the field of education, carried out in living and working environment, which has undergone so profound changes recently, is of extreme importance. In schools, courses and seminars, one cannot prepare him/herself for the changes as these are often so rapid that it is impossible to foresee them. Therefore, one can only learn by experience. In defining the term 'experience learning', the teoreticians vary greatly. In this paper, experience learning is understood as a process of learning taking part mainly outside the planned educational process and including an active and participative attitude towards environment and people. Original and direct experience can thus serve as a basis for gaining new comprehensions, for planning future activities as well as for a reinterpretation of the past experiences. Let us first mention the basic factors of successful experience learning, such as an individual's character features, possibilities for learning, learning atmosphere and positive stimulations. It has been estimated that local community can increase or decrease the possibilities for experience learning. However, the relation is active in other direction too: the more experience learning bas been asserted in a community, the greater its influence on social and cultural development of the community. On has to bear in mind that well-planned education for local community and stimulating sociocultural animation can facilitate the development of local community.

  7. 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)

  8. 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.)

  9. 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)

  10. 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

  11. 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)

  12. 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

  13. 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

  14. Swedish spent fuel management systems, facilities and operating experiences

    International Nuclear Information System (INIS)

    Vogt, J.

    1998-01-01

    About 50% of the electricity in Sweden is generated by means of nuclear power from 12 LWR reactors located at four sites and with a total capacity of 10,000 MW. The four utilities have jointly created SKB, the Swedish Nuclear Fuel and Waste Management Company, which has been given the mandate to manage the spent fuel and radioactive waste from its origin at the reactors to the final disposal. SKB has developed a system for the safe handling of all kinds of radioactive waste from the Swedish nuclear power plants. The keystones now in operation of this system are a transport system, a central interim storage facility for spent nuclear fuel (CLAB), a final repository for short-lived, low and intermediate level waste (SFR). The remaining, system components being planned are an encapsulation plant for spent nuclear fuel and a deep repository for encapsulated spent fuel and other long-lived radioactive wastes. (author)

  15. Diagnosing and controlling mix in National Ignition Facility implosion experiments

    International Nuclear Information System (INIS)

    Hammel, B. A.; Scott, H. A.; Cerjan, C.; Clark, D. S.; Edwards, M. J.; Glenzer, S. H.; Haan, S. W.; Izumi, N.; Koch, J. A.; Landen, O. L.; Langer, S. H.; Smalyuk, V. A.; Suter, L. J.; Regan, S. P.; Epstein, R.; Kyrala, G. A.; Wilson, D. C.; Peterson, K.

    2011-01-01

    High mode number instability growth of ''isolated defects'' on the surfaces of National Ignition Facility [Moses et al., Phys. Plasmas 16, 041006 (2009)] capsules can be large enough for the perturbation to penetrate the imploding shell, and produce a jet of ablator material that enters the hot-spot. Since internal regions of the CH ablator are doped with Ge, mixing of this material into the hot-spot results in a clear signature of Ge K-shell emission. Evidence of jets entering the hot-spot has been recorded in x-ray images and spectra, consistent with simulation predictions [Hammel et al., High Energy Density Phys. 6, 171 (2010)]. Ignition targets have been designed to minimize instability growth, and capsule fabrication improvements are underway to reduce ''isolated defects.'' An experimental strategy has been developed where the final requirements for ignition targets can be adjusted through direct measurements of mix and experimental tuning.

  16. 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)

  17. MOX fuel development: Experience in Argentina

    International Nuclear Information System (INIS)

    Marchi, D.E.; Adelfang, P.; Menghini, J.E.

    1999-01-01

    Since 1973, when a laboratory conceived for the safe manipulation of a few hundred grams of plutonium was built, the CNEA (Argentinean Atomic Energy Commission) has been involved in the small-scale development of MOX fuel technology. The plutonium laboratory consists in a glove box facilityFacility) featuring the necessary equipment to prepare MOX fuel rods for experimental irradiations and to carry out studies on preparative processes development and chemical and physical characterization. The irradiation of the first prototypes of (U,Pu)O 2 fuels fabricated in Argentina began in 1986. These experiments were carried out in the HFR (High Flux Reactor)- Petten , Holland. The rods were prepared and controlled in the CNEA's a Facility. The post-irradiation examinations (PIE) were performed in the KFK (Kernforschungszentrum Karlsruhe), Germany and the JRC (Joint Research Center), Petten. In the period 1991-1995, the development of new laboratory methods of co-conversion of uranium and plutonium were carried out: reverse strike co-precipitation of ADU-Pu(OH) 4 and direct denitration using microwaves. The reverse strike process produced pellets with a high sintered density, excellent micro-homogeneity and good solubility in nitric acid. Liquid wastes showed a very low content of actinides and the process is easy to operate in a glove box environment. The microwave direct denitration was optimized with uranium alone and the conditions to obtain high density pellets, with a good microstructure, without using a milling step, have been developed. At present, new experiments are being carried out to improve the reverse strike co-precipitation process and direct microwave denitration. A new glove box is being installed at the plutonium laboratory, this glove box has process equipment designed to recover scrap from previous fabrication campaigns, and to co-convert mixed U-Pu solutions by direct microwave denitration. (author)

  18. Experiment archive, analysis, and visualization at the National Ignition Facility

    International Nuclear Information System (INIS)

    Hutton, Matthew S.; Azevedo, Stephen; Beeler, Richard; Bettenhausen, Rita; Bond, Essex; Casey, Allan; Liebman, Judith; Marsh, Amber; Pannell, Thomas; Warrick, Abbie

    2012-01-01

    Highlights: ► We show the computing architecture to manage scientific data from NIF experiments. ► NIF laser “shots” generate GBs of data for sub-microsec events separated by hours. ► Results are archived, analyzed and displayed with parallel and scalable code. ► Data quality and pedigree, based on calibration of each part, are tracked. ► Web-based visualization tools present data across shots and diagnostics. - Abstract: The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory is the world's most energetic laser, providing a scientific research center to study inertial confinement fusion and matter at extreme energy densities and pressures. A target shot involves over 30 specialized diagnostics measuring critical x-ray, optical and nuclear phenomena to quantify ignition results for comparison with computational models. The Shot Analysis and Visualization System (SAVI) acquires and analyzes target diagnostic data for display within a time-budget of 30 min. Laser and target diagnostic data are automatically loaded into the NIF archive database through clustered software data collection agents. The SAVI Analysis Engine distributes signal and image processing tasks to a Linux cluster where computation is performed. Intermediate results are archived at each step of the analysis pipeline. Data is archived with metadata and pedigree. Experiment results are visualized through a web-based user interface in interactive dashboards tailored to single or multiple shot perspectives. The SAVI system integrates open-source software, commercial workflow tools, relational database and messaging technologies into a service-oriented and distributed software architecture that is highly parallel, scalable, and flexible. The architecture and functionality of the SAVI system will be presented along with examples.

  19. Risk management for operations of the LANL Critical Experiments Facility

    International Nuclear Information System (INIS)

    Paternoster, R.; Butterfield, K.

    1998-01-01

    The Los Alamos Critical Experiments Facility (LACEF) currently operates two burst reactors (Godiva-IV and Skua), one solution assembly [the Solution High-Energy Burst Assembly (SHEBA)], two fast-spectrum benchmark assemblies (Flattop and Big Ten), and five general-purpose remote assembly machines that may be configured with nuclear materials and assembled by remote control. Special nuclear materials storage vaults support these and other operations at the site. With this diverse set of operations, several approaches are possible in the analysis and management of risk. The most conservative approach would be to write a safety analysis report (SAR) for each assembly and experiment. A more cost-effective approach is to analyze the probability and consequences of several classes of operations representative of operations on each critical assembly machine and envelope the bounding case accidents. Although the neutron physics of these machines varies widely, the operations performed at LACEF fall into four operational modes: steady-state mode, approach-to-critical mode, prompt burst mode, and nuclear material operations, which can include critical assembly fuel loading. The operational sequences of each mode are very nearly identical, whether operated on one assembly machine or another. The use of an envelope approach to accident analysis is facilitated by the use of classes of operations and the use of bounding case consequence analysis. A simple fault tree analysis of operational modes helps resolve which operations are sensitive to human error and which are initiated by hardware of software failures. Where possible, these errors and failures are blocked by TSR LCOs. Future work will determine the probability of accidents with various initiators

  20. Virtual neutron scattering experiments - Training and preparing students for large-scale facility experiments

    Directory of Open Access Journals (Sweden)

    Julie Hougaard Overgaard

    2016-11-01

    Full Text Available Dansk Vi beskriver, hvordan virtuelle eksperimenter kan udnyttes i et læringsdesign ved at forberede de studerende til hands-on-eksperimenter ved storskalafaciliteter. Vi illustrerer designet ved at vise, hvordan virtuelle eksperimenter bruges på Niels Bohr Institutets kandidatkursus om neutronspredning. I den sidste uge af kurset, rejser studerende til et storskala neutronspredningsfacilitet for at udføre neutronspredningseksperimenter. Vi bruger studerendes udsagn om deres oplevelser til at argumentere for, at arbejdet med virtuelle experimenter forbereder de studerende til at engagere sig mere frugtbart med eksperimenter ved at lade dem fokusere på fysikken og relevante data i stedet for instrumenternes funktion. Vi hævder, at det er, fordi de kan overføre deres erfaringer med virtuelle eksperimenter til rigtige eksperimenter. Vi finder dog, at læring stadig er situeret i den forstand, at kun kendskab til bestemte eksperimenter overføres. Vi afslutter med at diskutere de muligheder, som virtuelle eksperimenter giver. English We describe how virtual experiments can be utilized in a learning design that prepares students for hands-on experiments at large-scale facilities. We illustrate the design by showing how virtual experiments are used at the Niels Bohr Institute in a master level course on neutron scattering. In the last week of the course, students travel to a large-scale neutron scattering facility to perform real neutron scattering experiments. Through student interviews and survey answers, we argue, that the virtual training prepares the students to engage more fruitfully with experiments by letting them focus on physics and data rather than the overwhelming instrumentation. We argue that this is because they can transfer their virtual experimental experience to the real-life situation. However, we also find that learning is still situated in the sense that only knowledge of particular experiments is transferred. We proceed to

  1. The Pajarito Site operating procedures for the Los Alamos Critical Experiments Facility

    International Nuclear Information System (INIS)

    Malenfant, R.E.

    1991-12-01

    Operating procedures consistent with DOE Order 5480.6, and the American National Standard Safety Guide for the Performance of Critical Experiments are defined for the Los Alamos Critical Experiments Facility (LACEF) of the Los Alamos National Laboratory. These operating procedures supersede and update those previously published in 1983 and apply to any criticality experiment performed at the facility. 11 refs

  2. 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...

  3. 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

  4. Commissioning experience and beam physics measurements at the SwissFEL Injector test Facility

    CERN Document Server

    Schietinger, T.; Aiba, M.; Arsov, V.; Bettoni, S.; Beutner, B.; Calvi, M.; Craievich, P.; Dehler, M.; Frei, F.; Ganter, R.; Hauri, C. P.; Ischebeck, R.; Ivanisenko, Y.; Janousch, M.; Kaiser, M.; Keil, B.; Löhl, F.; Orlandi, G. L.; Ozkan Loch, C.; Peier, P.; Prat, E.; Raguin, J.-Y.; Reiche, S.; Schilcher, T.; Wiegand, P.; Zimoch, E.; Anicic, D.; Armstrong, D.; Baldinger, M.; Baldinger, R.; Bertrand, A.; Bitterli, K.; Bopp, M.; Brands, H.; Braun, H. H.; Brönnimann, M.; Brunnenkant, I.; Chevtsov, P.; Chrin, J.; Citterio, A.; Csatari Divall, M.; Dach, M.; Dax, A.; Ditter, R.; Divall, E.; Falone, A.; Fitze, H.; Geiselhart, C.; Guetg, M. W.; Hämmerli, F.; Hauff, A.; Heiniger, M.; Higgs, C.; Hugentobler, W.; Hunziker, S.; Janser, G.; Kalantari, B.; Kalt, R.; Kim, Y.; Koprek, W.; Korhonen, T.; Krempaska, R.; Laznovsky, M.; Lehner, S.; Le Pimpec, F.; Lippuner, T.; Lutz, H.; Mair, S.; Marcellini, F.; Marinkovic, G.; Menzel, R.; Milas, N.; Pal, T.; Pollet, P.; Portmann, W.; Rezaeizadeh, A.; Ritt, S.; Rohrer, M.; Schär, M.; Schebacher, L.; Scherrer, St.; Schlott, V.; Schmidt, T.; Schulz, L.; Smit, B.; Stadler, M.; Steffen, Bernd; Stingelin, L.; Sturzenegger, W.; Treyer, D. M.; Trisorio, A.; Tron, W.; Vicario, C.; Zennaro, R.; Zimoch, D.

    2016-10-26

    The SwissFEL Injector Test Facility operated at the Paul Scherrer Institute between 2010 and 2014, serving as a pilot plant and test bed for the development and realization of SwissFEL, the x-ray Free Electron Laser facility under construction at the same institute. The test facility consisted of a laser-driven rf electron gun followed by an S-band booster linac, a magnetic bunch compression chicane and a diagnostic section including atransverse deflecting rf cavity. It delivered electron bunchesof up to200 pC chargeand up to 250 MeV beam energy at a repetition rate of 10 Hz. The measurements performed at the test facility not only demonstrated the beam parameters required to drive the first stage of a FEL facility, but also led to significant advances in instrumentation technologies, beam characterization methods and the generation, transport and compression of ultralow-emittance beams. We give a comprehensive overview of the commissioning experience of the principal subsystems and the beam physics measureme...

  5. 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...

  6. 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.

  7. 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.)

  8. 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

  9. 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

  10. 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.

  11. 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

  12. Safety requirements and safety experience of nuclear facilities in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Schnurer, H.L.

    1977-01-01

    Peaceful use of nuclear energy within the F.R.G. is rapidly growing. The Energy Programme of the Federal Government forecasts a capacity of up to 50.000 MW in 1985. Whereas most of this capacity will be of the LWR-Type, other activities are related to LMFBR - and HTGR - development, nuclear ships, and facilities of the nuclear fuel cycle. Safety of nuclear energy is the pacemaker for the realization of nuclear programmes and projects. Due to a very high population - and industrialisation density, safety has the priority before economical aspects. Safety requirements are therefore extremely stringent, which will be shown for the legal, the technical as well as for the organizational area. They apply for each nuclear facility, its site and the nuclear energy system as a whole. Regulatory procedures differ from many other countries, assigning executive power to state authorities, which are supervised by the Federal Government. Another particularity of the regulatory process is the large scope of involvement of independent experts within the licensing procedures. The developement of national safety requirements in different countries generates a necessity to collaborate and harmonize safety and radiation protection measures, at least for facilities in border areas, to adopt international standards and to assist nuclear developing countries. However, different nationally, regional or local situations might raise problems. Safety experience with nuclear facilities can be concluded from the positive construction and operation experience, including also a few accidents and incidents and the conclusions, which have been drawn for the respective factilities and others of similar design. Another tool for safety assessments will be risk analyses, which are under development by German experts. Final, a scope of future problems and developments shows, that safety of nuclear installations - which has reached a high performance - nevertheless imposes further tasks to be solved

  13. 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.

  14. 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.)

  15. 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.

  16. 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

  17. Developing Effective Undergraduate Research Experience

    Science.gov (United States)

    Evans, Michael; Ilie, Carolina C.

    2011-03-01

    Undergraduate research is a valuable educational tool for students pursuing a degree in physics, but these experiences can become problematic and ineffective if not handled properly. Undergraduate research should be planned as an immersive learning experience in which the student has the opportunity to develop his/her skills in accordance with their interests. Effective undergraduate research experiences are marked by clear, measurable objectives and frequent student-professor collaboration. These objectives should reflect the long and short-term goals of the individual undergraduates, with a heightened focus on developing research skills for future use. 1. Seymour, E., Hunter, A.-B., Laursen, S. L. and DeAntoni, T. (2004), ``Establishing the benefits of research experiences for undergraduates in the sciences: First findings from a three-year study''. Science Education, 88: 493--534. 2. Behar-Horenstein, Linda S., Johnson, Melissa L. ``Enticing Students to Enter Into Undergraduate Research: The Instrumentality of an Undergraduate Course.'' Journal of College Science Teaching 39.3 (2010): 62-70.

  18. Utilization of the BARC critical facility for ADS related experiments

    Indian Academy of Sciences (India)

    The paper discusses the basic design of the critical facility, whose main pur- ... systems. In addition, it will have a flux mapping system based on 25 fission ... neutron source leads to peaked flux distribution exciting other higher harmonic.

  19. Radiolysis of Fricke solution: initial experiments with the pelletron facility

    International Nuclear Information System (INIS)

    Sharma, S.B.; Rao, B.S.M.

    1994-01-01

    Experimental details of heavy ion irradiation of aqueous solutions using the Nuclear Science Centre (NSC) pelletron facility and the initial results from the radiolysis of Fricke solution using oxygen-16 ions are reported. (author). 4 refs., 1 fig

  20. 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

  1. Activity of safety review for the facilities using nuclear material (2). Safety review results and maintenance experiences for hot laboratories

    International Nuclear Information System (INIS)

    Amagai, Tomio; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Ohmori, Tsuyoshi

    2009-01-01

    In the site of O-arai Research and Development Center of Japan Atomic Energy Agency (JAEA), five hot laboratories for post-irradiation examination and development of plutonium fuels are operated more than 30 years. A safety review method for preventive maintenance on these hot laboratories includes test facilities and devices are established in 2003. After that, the safety review of these facilities and devices are done and taken the necessary maintenance based on the results in each year. In 2008, 372 test facilities and devices in these hot laboratories were checked and reviewed by this method. As a results of the safety review, repair issues of 38 facilities of above 372 facilities were resolved. This report shows the review results and maintenance experiences based on the results. (author)

  2. Safety analysis of the Los Alamos critical experiments facility

    International Nuclear Information System (INIS)

    Paxton, H.C.

    1975-10-01

    The safety of Pajarito Site critical assembly operations depends upon protection built into the facility, upon knowledgeable personnel, and upon good practice as defined by operating procedures and experimental plans. Distance, supplemented by shielding in some cases, would protect personnel against an extreme accident generating 10 19 fissions. During the facility's 28-year history, the direct cost of criticality accidents has translated to a risk of less than $200 per year

  3. 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.

  4. 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.

  5. Verification of the Korsar code on results of experiments executed on the PSB-VVER facility

    International Nuclear Information System (INIS)

    Roginskaya, V.L.; Pylev, S.S.; Elkin, I.V.

    2005-01-01

    Full text of publication follows: Paper represents some results of computational research executed within the framework of verification of the KORSAR thermal hydraulic code. This code was designed in the NITI by A.P. Aleksandrov (Russia). The general purpose of the work was development of a nodding scheme of the PSB-VVER integral facility, scheme testing and computational modelling of the experiment 'The PSB-VVER Natural Circulation Test With Stepwise Reduction of the Primary Inventory'. The NC test has been performed within the framework of the OECD PSB-VVER Project (task no. 3). This Project is focused upon the provision of experimental data for codes assessment with regard to VVER analysis. Paper presents a nodding scheme of the PSB-VVER facility and results of pre- and post-test calculations of the specified experiment, obtained with the KORSAR code. The experiment data and the KORSAR pre-test calculation results are in good agreement. A post-test calculation of the experiment with KORSAR code has been performed in order to assess the code capability to simulate the phenomena relevant to the test. The code showed a reasonable prediction of the phenomena measured in the experiment. (authors)

  6. Verification of the Korsar code on results of experiments executed on the PSB-VVER facility

    Energy Technology Data Exchange (ETDEWEB)

    Roginskaya, V.L.; Pylev, S.S.; Elkin, I.V. [NSI RRC ' Kurchatov Institute' , Kurchatov Sq., 1, Moscow, 123182 (Russian Federation)

    2005-07-01

    Full text of publication follows: Paper represents some results of computational research executed within the framework of verification of the KORSAR thermal hydraulic code. This code was designed in the NITI by A.P. Aleksandrov (Russia). The general purpose of the work was development of a nodding scheme of the PSB-VVER integral facility, scheme testing and computational modelling of the experiment 'The PSB-VVER Natural Circulation Test With Stepwise Reduction of the Primary Inventory'. The NC test has been performed within the framework of the OECD PSB-VVER Project (task no. 3). This Project is focused upon the provision of experimental data for codes assessment with regard to VVER analysis. Paper presents a nodding scheme of the PSB-VVER facility and results of pre- and post-test calculations of the specified experiment, obtained with the KORSAR code. The experiment data and the KORSAR pre-test calculation results are in good agreement. A post-test calculation of the experiment with KORSAR code has been performed in order to assess the code capability to simulate the phenomena relevant to the test. The code showed a reasonable prediction of the phenomena measured in the experiment. (authors)

  7. In-pile experiments and test facilities proposed for fast reactor safety

    International Nuclear Information System (INIS)

    Grolmes, M.A.; Avery, R.; Goldman, A.J.; Fauske, H.K.; Marchaterre, J.F.; Rose, D.; Wright, A.E.

    1976-01-01

    The role of in-pile experiments in support of the resolution of fast breeder reactor safety and licensing issues has been re-examined, with emphasis on key safety issues. Experiment needs have been related to the specific characteristics of these safety issues and to realistic requirements for additional test facility capabilities which can be achieved and utilized within the next ten years. It is found that those safety issues related to the energetics of core disruptive accidents have the largest impact on new facility requirements. However, utilization of existing facilities with modifications can provide for a continuing increase in experiment capability and experiment results on a timely bases. Emphasis has been placed upon maximum utilization of existing facilities and minimum requirements for new facilities. This evaluation has concluded that a new Safety Test Facility, STF, along with major modifications to the EBR II facility, improvement in TREAT capabilities, the existing Sodium Loop Safety Facility and corresponding Support Facilities provide the essential elements of the Safety Research Experiment Facilities (SAREF) required for resolution of key issues

  8. 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.

  9. Material Control and Accountability Experience at the Fuel Conditioning Facility

    International Nuclear Information System (INIS)

    Vaden, D.; Fredrickson, G.L.

    2007-01-01

    The Fuel Conditioning Facility (FCF) at the Idaho National Laboratory (INL) treats spent nuclear fuel using an electrometallurgical process that separates the uranium from the fission products, sodium thermal bond, and cladding materials. Material accountancy is necessary at FCF for two reasons: 1) it provides a mechanism for detecting a potential loss of nuclear material for safeguards and security, and 2) it provides a periodic check of inventories to ensure that processes and materials are within control limits. Material Control and Accountability is also a Department of Energy (DOE) requirement (DOE Order 474.1). The FCF employs a computer based Mass Tracking (MTG) System to collect, store, retrieve, and process data on all operations that directly affect the flow of materials through the FCF. The MTG System is important for the operations of the FCF because it supports activities such as material control and accountability, criticality safety, and process modeling. To conduct material control and accountability checks and to monitor process performance, mass balances are routinely performed around the process equipment. The equipment used in FCF for pyro-processing consists of two mechanical choppers and two electro-refiners (the Mark-IV with the accompanying element chopper and Mark-V with the accompanying blanket chopper for processing driver fuel and blanket, respectively), and a cathode processor (used for processing both driver fuel and blanket) and casting furnace (mostly used for processing driver fuel). Performing mass balances requires the measurement of the masses and compositions of several process streams and equipment inventories. The masses of process streams are obtained via in-cell balances (i.e., load cells) that weigh containers entering and leaving the process equipment. Samples taken at key locations are analyzed to determine the composition of process streams and equipment inventories. In cases where equipment or containers cannot be

  10. Design of the plutonium facility for animal experiments and its management experience

    International Nuclear Information System (INIS)

    Koizumi, Akira; Fukuda, Satoshi

    1998-01-01

    Design and radiation control of authors' facility which was made as a nuclear fuel laboratory for animal experiments were described. Before construction, the animals thought to be used were rats, mice, beagle dogs and monkeys. 239 Pu and certain other radioisotopes were to be used. At present, 200 dogs and 1800 small animals can be maintained. The points for design were tolerability against quake, reduced-pressure management and permanent storage of waste containing Pu. The facility building composed from 2nd, 4th, and 6th laboratory floors and between them, from the so-called mechanical floors which are spaces for ducts. The latter floors are quite useful. The system for reduced pressure is of 3 patterns of rooms without hood, with ordinary hood and with air-curtain hood. For animal maintenance, there are 3 types of maintenance means: Glove box, hood and ordinary animal room. There are drainage equipment where Pu can be removed by precipitation and charcoal adsorption and incineration equipment which is necessary for reducing the waste volume. In the latter, HEPA filters are finally used for releasing the gas. There is no particular problem in the radiation control. For the personnel control, lung-monitoring is performed before and at the end of personnel registration. Environmental monitoring of Pu is optionally performed. Removal of Pu particles generated in the inhalation experiments could be attained by the use of ULPA and HEPA filters to the level less than 1/10 17 times the reference level. Keeping the technology level enough high for facility maintenance and management was considered to be important at present and in future. (K.H.)

  11. 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

  12. 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.

  13. 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

  14. 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)

  15. Defense waste processing facility radioactive operations. Part 1 - operating experience

    International Nuclear Information System (INIS)

    Little, D.B.; Gee, J.T.; Barnes, W.M.

    1997-01-01

    The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation's first and the world's largest vitrification facility. Following a ten year construction program and a 3 year non-radioactive test program, DWPF began radioactive operations in March 1996. This paper presents the results of the first 9 months of radioactive operations. Topics include: operations of the remote processing equipment reliability, and decontamination facilities for the remote processing equipment. Key equipment discussed includes process pumps, telerobotic manipulators, infrared camera, Holledge trademark level gauges and in-cell (remote) cranes. Information is presented regarding equipment at the conclusion of the DWPF test program it also discussed, with special emphasis on agitator blades and cooling/heating coil wear. 3 refs., 4 figs

  16. Recent development in CMB experiments

    International Nuclear Information System (INIS)

    Matsumura, T.

    2014-01-01

    The rich data from the measurements of the cosmic microwave background (CMB) have played a key role to establish the ΛCDM cosmology. The WMAP results combined with Type Ia Supernova and BAO constrain not only the standard cosmological parameters to a few percent level. The combination of the data such as WMAP, SPT and H 0 started constraining such as the cosmic inflation r ν <0.38, and the equation of the dark energy w=-1.087 ± 0.096. The current experimental efforts are focused to measure the CMB B-mode polarization to probe deeper to 'beyond standard model' parameters from the sky. The upcoming ground-base and balloon-borne experiments are designed for r∼0.01. This sensitivity with an arcmin scale angular resolution is also well within the detection of the lensing B-mode. I review the recent development and the prospect from the upcoming CMB experiments. (author)

  17. The LPCTrap facility for in-trap decay experiments

    International Nuclear Information System (INIS)

    Rodriguez, D.; Ban, G.; Durand, D.; Duval, F.; Flechard, X.; Herbane, M.; Lienard, E.; Mauger, F.; Mery, A.; Naviliat-Cuncic, O.; Thomas, J.-C.

    2007-01-01

    The LPCTrap facility is coupled to the low-energy beam line LIRAT of the SPIRAL source at GANIL (France). The facility comprises an RFQ trap for beam preparation and a transparent Paul trap for in-trap decay studies. The system has been tested for several ion species. The Paul trap has been fully characterized for 6 Li + and 23 Na + ions. This characterization together with GEANT4 simulations of the in-trap decay setup (Paul trap and detection system) has permitted to predict the effect of the size of the ion cloud on the decay study of 6 He + .

  18. 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)

  19. 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)

  20. Discriminative facility and its role in the perceived quality of interactional experiences.

    Science.gov (United States)

    Cheng, C; Chiu, C Y; Hong, Y Y; Cheung, J S

    2001-10-01

    Discriminative facility refers to an individual's sensitivity to subtle cues about the psychological meaning of a situation. This research aimed at examining (a) the conceptual distinctiveness of discriminative facility, (b) the situation-appropriate aspect of this construct, and (c) the relationship between discriminative facility and interpersonal experiences. Discriminative facility was assessed by a new measure of situation-appropriate behaviors across a variety of novel stressful situations. Results from study 1 showed that discriminative facility had weak positive relationships with cognitive complexity and nonsignificant relationships with self-monitoring and social desirability, indicating that discriminative facility is a unique construct. Results from Study 2 revealed that higher levels of discriminative facility were associated with higher levels of perceived social support and a greater number of pleasant interpersonal events experienced, thus providing support for the theoretical proposition that discriminative facility is an aspect of social intelligence.

  1. Economies of using seismic experience data qualification methods at Department of Energy facilities

    International Nuclear Information System (INIS)

    Loceff, F.; Antaki, G.; Goen, L.

    1995-01-01

    This paper summarizes the implementation of the seismic qualification of existing equipment using experience data techniques. The emphasis is on the economies of this approach compared with standard qualification methods of analysis and testing or replacement with qualified equipment. Seismic qualification of existing equipment using experience data is a technical necessity and is the most economically attractive of the options. Representative costs for seismic qualification at two facilities show costs are substantially lower than the costs for qualification using conventional methods. Because of the experience to date, the authors recommend that the Department of Energy continue to sponsor the Existing Facilities Program for applying qualification using experience data techniques at DOE facilities

  2. Design and Testing of a Breadboard Electrical Power Control Unit for the Fluid Combustion Facility Experiment

    Science.gov (United States)

    Kimnach, Greg L.; Lebron, Ramon C.

    1999-01-01

    The Fluid Combustion Facility (FCF) Project and the Power Technology Division at the NASA Glenn Research Center (GRC) at Lewis Field in Cleveland, OH along with the Sundstrand Corporation in Rockford, IL are jointly developing an Electrical Power Converter Unit (EPCU) for the Fluid Combustion Facility to be flown on the International Space Station (ISS). The FCF facility experiment contains three racks: A core rack, a combustion rack, and a fluids rack. The EPCU will be used as the power interface to the ISS 120V(sub dc) power distribution system by each FCF experiment rack which requires 28V(sub dc). The EPCU is a modular design which contains three 120V(sub dc)-to-28V(sub dc) full-bridge, power converters rated at 1 kW(sub e) each bus transferring input relays and solid-state, current-limiting input switches, 48 current-limiting, solid-state, output switches; and control and telemetry hardware. The EPCU has all controls required to autonomously share load demand between the power feeds and--if absolutely necessary--shed loads. The EPCU, which maximizes the usage of allocated ISS power and minimizes loss of power to loads, can be paralleled with other EPCUs. This paper overviews the electrical design and operating characteristics of the EPCU and presents test data from the breadboard design.

  3. HIPPI developments for CERN experiments

    International Nuclear Information System (INIS)

    van Praag, A.; Anguelov, T.; Burckhart, D.; McLaren, R.A.; van der Bij, H.C.; Bovier, J.; Cristin, P.; Haben, M.; Jovanovic, P.; Kenyon, I.; Staley, R.

    1992-01-01

    Standard, fast, simple, inexpensive; is this not a contradiction in terms? The High-Performance Parallel Interface (HIPPI) is a new ANSI standard, using a minimal protocol and providing 100 Mbyte/s. transfers over distances up to 25 m. Equipment using this standard is offered by a growing number of computer manufacturers. A commercially available HIPPI chip set allows low cost implementations. In this article a brief technical introduction to the HIPPI will be given, followed by examples of planned applications in high energy physics experiments including the present developments involving CERN: a detector emulator, a risc processor based VME connection, a long distance fiber optics connection, and a HIPPI testbox

  4. Ectopic pregnancy experience in a tertiary health facility in South ...

    African Journals Online (AJOL)

    Background: Ectopic pregnancy is a life-threatening gynecological emergency, and a significant cause of maternal morbidity and mortality in Nigeria. Objective: To determine the incidence, clinical presentation, risk factors and management outcomes of ectopic pregnancies in a tertiary health facility. Methods: A retrospective ...

  5. 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)

  6. 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.

  7. Equipment experience in a radioactive LFCM [liquid-fed ceramic melter] vitrification facility

    International Nuclear Information System (INIS)

    Holton, L.K. Jr.; Dierks, R.D.; Sevigny, G.J.; Goles, R.W.; Surma, J.E.; Thomas, N.M.

    1986-11-01

    Since October 1984, the Pacific Northwest Laboratory (PNL) has operated a pilot-scale radioactive liquid-fed ceramic melter (RLFCM) vitrification process in shielded manipulator hot cells. This vitrification facility is being operated for the Department of Energy (DOE) to remotely test vitrification equipment components in a radioactive environment and to develop design and operation data that can be applied to production-scale projects. This paper summarizes equipment and process experience obtained from the operations of equipment systems for waste feeding, waste vitrification, canister filling, canister handling, and vitrification off-gas treatment

  8. 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.

  9. 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

  10. 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)

  11. Simulation of power maneuvering experiment of MASLWR test facility by MARS-KS code

    Energy Technology Data Exchange (ETDEWEB)

    Park, Ju Yeop [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    In the present study, KINS simulation result by the MARS-KS code (KS-002 version) for the SP-3 experiment is presented in detail and conclusion on MARS-KS code performance drawn through this simulation is described. Performance of the MARS-KS code is evaluated through the simulation of the power maneuvering experiment of the MASLWR test facility. Steady run shows the helical coil specific heat transfer model of the code is reasonable. However, identified discrepancy of the primary mass flowrate at transient run shows code performance for pressure drop needs to be improved considering sensitivity of the flowrate to the pressure drop at natural circulation. Since 2009, IAEA has conducted a research program entitled as ICSP (International Collaborative Standard Problem) on integral PWR design to evaluate current the state of the art of thermal-hydraulic code in simulating natural circulation flow within integral type reactor. In this ICSP, experimental data obtained from MASLWR (Multi-Application Small Light Water Reactor) test facility located at Oregon state university in the US have been simulated by various thermal-hydraulic codes of each participant of the ICSP and compared among others. MASLWR test facility is a mock-up of a passive integral type reactor equipped with helical coil steam generator. Since SMART reactor which is currently being developed in Korea also adopts a helical coil steam generator, Korea Institute of Nuclear Safety (KINS) has joined this ICSP to assess the applicability of a domestic regulatory audit thermal-hydraulic code (i. e. MARS-KS code) for the SMART reactor including wall-to-fluid heat transfer model modification based on independent international experiment data. In the ICSP, two types of transient experiments have been focused and they are loss of feedwater transient with subsequent ADS operation and long term cooling (SP-2) and normal operating conditions at different power levels (SP-3)

  12. Simulation of power maneuvering experiment of MASLWR test facility by MARS-KS code

    Energy Technology Data Exchange (ETDEWEB)

    Park, Ju Yeop [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    In this ICSP, experimental data obtained from MASLWR (Mulit-Application Small Light Water Reactor) test facility located at Oregon state university in the US have been simulated by various thermal-hydraulic codes of each participant of the ICSP and compared among others. MASLWR test facility is a mock-up of a passive integral type reactor equipped with helical coil steam generator. Since SMART reactor which is currently being developed in Korea also adopts a helical coil steam generator, Korea Institute of Nuclear Safety (KINS) has joined this ICSP to assess the applicability of a domestic regulatory audit thermal-hydraulic code (i. e. MARS-KS code) for the SMART reactor including wall-to-fluid heat transfer model modification based on independent international experiment data. In the ICSP, two types of transient experiments have been focused and they are 1) loss of feedwater transient with subsequent ADS operation and long term cooling (SP-2) and normal operating conditions at different power levels. In the present study, KINS simulation result by the MARS-KS code (KS-002 version) for the SP-3 experiment is presented in detail and conclusion on MARS-KS code performance drawn through this simulation is described. Performance of the MARS-KS code is evaluated through the simulation of the power maneuvering experiment of the MASLWR test facility. Steady run shows the helical coil specific heat transfer model of the code is reasonable. However, identified discrepancy of the primary mass flowrate at transient run shows code performance for pressure drop needs to be improved considering sensitivity of the flowrate to the pressure drop at natural circulation.

  13. Fire simulation in nuclear facilities: the FIRAC code and supporting experiments

    International Nuclear Information System (INIS)

    Burkett, M.W.; Martin, R.A.; Fenton, D.L.; Gunaji, M.V.

    1984-01-01

    The fire accident analysis computer code FIRAC was designed to estimate radioactive and nonradioactive source terms and predict fire-induced flows and thermal and material transport within the ventilation systems of nuclear fuel cycle facilities. FIRAC maintains its basic structure and features and has been expanded and modified to include the capabilities of the zone-type compartment fire model computer code FIRIN developed by Battelle Pacific Northwest Laboratory. The two codes have been coupled to provide an improved simulation of a fire-induced transient within a facility. The basic material transport capability of FIRAC has been retained and includes estimates of entrainment, convection, deposition, and filtration of material. The interrelated effects of filter plugging, heat transfer, gas dynamics, material transport, and fire and radioactive source terms also can be simulated. Also, a sample calculation has been performed to illustrate some of the capabilities of the code and how a typical facility is modeled with FIRAC. In addition to the analytical work being performed at Los Alamos, experiments are being conducted at the New Mexico State University to support the FIRAC computer code development and verification. This paper summarizes two areas of the experimental work that support the material transport capabiities of the code: the plugging of high-efficiency particulate air (HEPA) filters by combustion aerosols and the transport and deposition of smoke in ventilation system ductwork

  14. Fire simulation in nuclear facilities--the FIRAC code and supporting experiments

    International Nuclear Information System (INIS)

    Burkett, M.W.; Martin, R.A.; Fenton, D.L.; Gunaji, M.V.

    1985-01-01

    The fire accident analysis computer code FIRAC was designed to estimate radioactive and nonradioactive source terms and predict fire-induced flows and thermal and material transport within the ventilation systems of nuclear fuel cycle facilities. FIRAC maintains its basic structure and features and has been expanded and modified to include the capabilities of the zone-type compartment fire model computer code FIRIN developed by Battelle Pacific Northwest Laboratory. The two codes have been coupled to provide an improved simulation of a fire-induced transient within a facility. The basic material transport capability of FIRAC has been retained and includes estimates of entrainment, convection, deposition, and filtration of material. The interrelated effects of filter plugging, heat transfer, gas dynamics, material transport, and fire and radioactive source terms also can be simulated. Also, a sample calculation has been performed to illustrate some of the capabilities of the code and how a typical facility is modeled with FIRAC. In addition to the analytical work being performed at Los Alamos, experiments are being conducted at the New Mexico State University to support the FIRAC computer code development and verification. This paper summarizes two areas of the experimental work that support the material transport capabilities of the code: the plugging of high-efficiency particulate air (HEPA) filters by combustion aerosols and the transport and deposition of smoke in ventilation system ductwork

  15. An Experience of Thermowell Design in RCP Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Y. S.; Kim, B. D.; Youn, Y. J.; Jeon, W. J.; Kim, S.; Bae, B. U.; Cho, Y. J.; Choi, H. S.; Park, J. K; Cho, S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Flow rates for the test should vary in the range of 90% to 130% of rated flowrate under prototypic operational conditions, as shown in Table 1. Generally for the flow control, a combination of a control valve and an orifice was used in previous RCP test facilities. From the commissioning startup of the RCP test facility, it was found the combination of valve and orifice induced quite a large vibration for the RCP. As a solution to minimize the vibration and to facilitate the flowrate control, one of KAERI's staff suggested a variable restriction orifice (VRO), which controls most of the required flowrates except highest flowrates, as shown in Fig. 2. For the highest flowrates, e.g., around run-out flowrate (130%), control valves in bypass lines were also used to achieve required flowrates. From a performance test, it was found the VRO is very effective measures to control flowrates in the RCP test facility. During the commissioning startup operation, one of thermowells located at the upstream of the RCP was cracked due to high speed coolant velocity, which was - fortunately - found under a leakage test before running the RCP test loop. The cracked thermowell, whose tapered-shank was detached from the weld collar after uninstalling, is shown in Fig. 3. As can be seen the figure, most of the cross-section at the root of the thermowell shank was cracked. In this paper, an investigation of the integrity of thermowells in the RCP test facility was performed according to the current code and overall aspects on the thermowell designs were also discussed. An RCP test facility has been constructed in KAERI. During the commissioning startup operation, one of thermowells was cracked due to high speed coolant velocity. To complete the startup operation, a modified design of thermowells was proposed and all the original thermowells were replaced by the modified ones. From evaluation of the original and modified designs of thermowells according to the recent PTC code, the

  16. 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.)

  17. 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.)

  18. 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

  19. Citizenship Education Development: European Experience

    Directory of Open Access Journals (Sweden)

    A. V. Suslov

    2012-01-01

    Full Text Available The paper considers the European experience of the citizenship education developmentan important aspect of internal policy in the most countries. The education in question is considered to be the democratic citizenship training aimed at developing the loyal attitude to different value priorities in society, social responsibility, active citizenship position, awareness of democratic rights, capability of using and protecting them.The author looks at the transformation of citizenship education concept in the last three decades from the civics education (i.e. history, political science, law, etc. to the democratic citizen education. The paper analyzes differ- ent approaches to citizenship education in several European countries including the post-soviet ones. It is emphasized that both in western and eastern Europe a lot of effort is made for spreading and supporting the education in question. The author recommends considering the foreign experience of integrating the democratic citizenship education into the state academic curricula at the primary, secondary and higher school levels. 

  20. Simulation of hydrogen deflagration experiments in the ENACCEF facility using ASTEC code

    International Nuclear Information System (INIS)

    Povilaitis, Mantas; Urbonavicius, Egidijus; Rimkevicius, Sigitas

    2011-01-01

    During a hypothetic severe accident in the NPP involving degradation of the core of a light water reactor, hydrogen could be generated and released into the containment atmosphere posing a deflagration or even a detonation risk. In the case of deflagration, the integrity of the containment would be threatened by the increase of the containment atmosphere pressure and temperature. Other risks of containment damage due to turbulent flames exist, caused by high pressure pulses, shock waves and etc. For the simulation of such processes a reliable numerical codes are needed. Despite flame acceleration being largely studied for homogeneous hydrogen - air mixtures, there are still unresolved issues in this research area, e.g., the effect of turbulence level on flame acceleration and quenching. This paper presents simulations of hydrogen deflagration experiments in the ENACCEF facility using ASTEC code, performed in the frames of International Standard Program No. 49 and SARNET2 project. Experiments and simulations were performed with the aim of evaluating the codes' (a number of participants with various codes participated in the project) capabilities to simulate hydrogen combustion. ASTEC code is an integral lumped-parameter approach based nuclear safety analysis code. For the presented simulations, ASTEC modules CPA (containment thermohydromechanics) and FRONT (hydrogen deflagration) were used. Paper present ENACCEF test facility, its nodalisation schemes developed for the calculations, simulated experiments and simulations' results. Brief description of FRONT module is also presented. Calculations' results are compared with experimental results and analyzed. (author)

  1. Integrating supervision, control and data acquisition—The ITER Neutral Beam Test Facility experience

    Energy Technology Data Exchange (ETDEWEB)

    Luchetta, A., E-mail: adriano.luchetta@igi.cnr.it; Manduchi, G.; Taliercio, C.; Breda, M.; Capobianco, R.; Molon, F.; Moressa, M.; Simionato, P.; Zampiva, E.

    2016-11-15

    Highlights: • The paper describes the experience gained in the integration of different systems for the control and data acquisition system of the ITER Neutral Beam Test Facility. • It describes the way the different frameworks have been integrated. • It reports some lessons learnt during system integration. • It reports some authors’ considerations about the development the ITER CODAC. - Abstract: The ITER Neutral Beam (NBI) Test Facility, under construction in Padova, Italy consists in the ITER full scale ion source for the heating neutral beam injector, referred to as SPIDER, and the full size prototype injector, referred to as MITICA. The Control and Data Acquisition System (CODAS) for SPIDER has been developed and is going to be in operation in 2016. The system is composed of four main components: Supervision, Slow Control, Fast Control and Data Acquisition. These components interact with each other to carry out the system operation and, since they represent a common pattern in fusion experiments, software frameworks have been used for each (set of) component. In order to reuse as far as possible the architecture developed for SPIDER, it is important to clearly define the boundaries and the interfaces among the system components so that the implementation of any component can be replaced without affecting the overall architecture. This work reports the experience gained in the development of SPIDER components, highlighting the importance in the definition of generic interfaces among component, showing how the specific solutions have been adapted to such interfaces and suggesting possible approaches for the development of other ITER subsystems.

  2. Integrating supervision, control and data acquisition—The ITER Neutral Beam Test Facility experience

    International Nuclear Information System (INIS)

    Luchetta, A.; Manduchi, G.; Taliercio, C.; Breda, M.; Capobianco, R.; Molon, F.; Moressa, M.; Simionato, P.; Zampiva, E.

    2016-01-01

    Highlights: • The paper describes the experience gained in the integration of different systems for the control and data acquisition system of the ITER Neutral Beam Test Facility. • It describes the way the different frameworks have been integrated. • It reports some lessons learnt during system integration. • It reports some authors’ considerations about the development the ITER CODAC. - Abstract: The ITER Neutral Beam (NBI) Test Facility, under construction in Padova, Italy consists in the ITER full scale ion source for the heating neutral beam injector, referred to as SPIDER, and the full size prototype injector, referred to as MITICA. The Control and Data Acquisition System (CODAS) for SPIDER has been developed and is going to be in operation in 2016. The system is composed of four main components: Supervision, Slow Control, Fast Control and Data Acquisition. These components interact with each other to carry out the system operation and, since they represent a common pattern in fusion experiments, software frameworks have been used for each (set of) component. In order to reuse as far as possible the architecture developed for SPIDER, it is important to clearly define the boundaries and the interfaces among the system components so that the implementation of any component can be replaced without affecting the overall architecture. This work reports the experience gained in the development of SPIDER components, highlighting the importance in the definition of generic interfaces among component, showing how the specific solutions have been adapted to such interfaces and suggesting possible approaches for the development of other ITER subsystems.

  3. 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.

  4. The choice of Park & Ride Facilities: an analysis using a context-dependent hierarchical choice experiment

    OpenAIRE

    Heijden, R.E.C.M. van der; Molin, E.J.E.; Timmermans, H.J.P.

    2004-01-01

    Park and Ride facilities have been proposed in several countries to alleviate the accessibility problems in cities. Despite growing accessibility problems, these facilities do not seem to attract the expected number of car drivers and are under-used. In an attempt to measure consumer evaluations of the attributes of Park and Ride facilities, a stated choice experiment, based on the method of hierarchical information integration, was conducted in the city of Nijmegen, The Netherlands. This pap...

  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. 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

  10. Assessing users' experience of shared sanitation facilities: A case ...

    African Journals Online (AJOL)

    In the academic literature, users' feedback and experiences of technologies in the post-implementation phase have received scarce attention. The purpose of this study is to investigate users' experience of sanitation technologies in the early post-implementation phase, when opportunities for remedial intervention are still ...

  11. Experience with the instrumentation tests in large sodium test facilities

    International Nuclear Information System (INIS)

    Lauhoff, Th.; Ruppert, E.; Stehle, H.; Vinzens, K.

    1976-01-01

    A facility is described for fast breeder core components (AKB) to test specially instrumented fuel dummies and blanket elements, and also absorber elements under simulated normal and extreme reactor conditions. In addition to endurance testing of a special sodium and high temperature sub-assembly, instrumentation is provided to investigate thermohydraulic and vibrational behaviour of core elements. During tests of > 3000 h at temperatures above 820 K the main sub-assembly characteristics, e.g. pressure drop, leakage flow, vibration and noise spectra can be reproduced. The use of eddy current flow meters, strain gauges, magnetostrictive noise sensors, pressure transducers, thermocouples, and acoustic surveillance devices, are described. (U.K.)

  12. Fast Flux Test Facility sodium pump operating experience - mechanical

    International Nuclear Information System (INIS)

    Buonamici, R.

    1987-11-01

    The Heat Transport System (HTS) pumps were designed, fabricated, tested, and installed in the Fast Flux Test Facility (FFTF) Plant during the period from September 1970 through July 1977. Since completion of the installation and sodium fill in December 1978, the FFTF Plant pumps have undergone extensive testing and operation with HTS testing and reactor operation. Steady-state hydraulic and mechanical performances have been and are excellent. In all, FFTF primary and secondary pumps have operated in sodium for approximately 75,000 hours and 79,000 hours, respectively, to August 24, 1987

  13. Sensitivity of the Low Frequency Facility experiment around 10 Hz

    International Nuclear Information System (INIS)

    Di Virgilio, A.; Braccini, S.; Ballardin, G.; Bradaschia, C.; Cella, G.; Cuoco, E.; Dattilo, V.; Ferrante, I.; Fidecaro, F.; Frasconi, F.; Giazotto, A.; Gennai, A.; Holloway, L.H.; La Penna, P.; Losurdo, G.; Paoletti, F.; Pasqualetti, A.; Passaquieti, R.; Passuello, D.; Porzio, A.; Puppo, P.; Raffaelli, F.; Rapagnani, P.; Ricci, F.; Ricciardi, J.; Solimeno, S.; Stanga, R.; Vetrano, F.; Zhang, Z.

    2004-01-01

    The reduction of thermal noise is a fundamental issue for the improvement of future gravitational wave antennas. The main purpose of the Low Frequency Facility (LFF) is to study pendulum thermal noise in the region of 10 Hz. Data at the LFF has been taking since the beginning of 2003 and has been analyzed in order to thoroughly understand the region around 10 Hz. Above 7 Hz, the displacement noise floor is at the level of 10 -14 m/√Hz, decreasing with frequency approximately as 1/ν. Seismic noise contamination is not observed above a few Hz

  14. Sensitivity of the Low Frequency Facility experiment around 10 Hz

    Energy Technology Data Exchange (ETDEWEB)

    Di Virgilio, A.; Braccini, S.; Ballardin, G.; Bradaschia, C.; Cella, G.; Cuoco, E.; Dattilo, V.; Ferrante, I.; Fidecaro, F.; Frasconi, F.; Giazotto, A.; Gennai, A.; Holloway, L.H.; La Penna, P.; Losurdo, G.; Paoletti, F.; Pasqualetti, A.; Passaquieti, R.; Passuello, D.; Porzio, A.; Puppo, P.; Raffaelli, F.; Rapagnani, P.; Ricci, F.; Ricciardi, J.; Solimeno, S.; Stanga, R.; Vetrano, F.; Zhang, Z

    2004-02-23

    The reduction of thermal noise is a fundamental issue for the improvement of future gravitational wave antennas. The main purpose of the Low Frequency Facility (LFF) is to study pendulum thermal noise in the region of 10 Hz. Data at the LFF has been taking since the beginning of 2003 and has been analyzed in order to thoroughly understand the region around 10 Hz. Above 7 Hz, the displacement noise floor is at the level of 10{sup -14} m/{radical}Hz, decreasing with frequency approximately as 1/{nu}. Seismic noise contamination is not observed above a few Hz.

  15. Structuring the Environmental Experience Design Research Framework through Selected Aged Care Facility Data Analyses in Victoria

    Directory of Open Access Journals (Sweden)

    Nan Ma

    2017-11-01

    Full Text Available Humans relate to the living environment physically and psychologically. Environmental psychology has a rich developed history while experience design emerged recently in the industrial design domain. Nonetheless, these approaches have barely been merged, understood or implemented in architectural design practices. This study explored the correlation between experience design and environmental psychology. Moreover, it conducted literature reviews on theories about emotion, user experience design, experience design and environmental psychology, followed by the analyses of spatial settings and environmental quality data of a selected aged care facility in Victoria, Australia, as a case study. Accordingly, this study led to proposing a research framework on environmental experience design (EXD. It can be defined as a deliberate attempt that affiliates experience design and environmental psychology with creation of the built environment that should accommodate user needs and demands. The EXD research framework proposed in this study was tailored for transforming related design functions into the solutions that contribute to improving the built environment for user health and wellbeing.

  16. 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.

  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. Field-reversal experiments in the mirror fusion test facility (MFTF)

    International Nuclear Information System (INIS)

    Shearer, J.W.; Condit, W.C.

    1977-01-01

    Detailed consideration of several aspects of a field-reversal experiment was begun in the Mirror Fusion Test Facility (MFTF): Model calculations have provided some plausible parameters for a field-reversed deuterium plasma in the MFTF, and a buildup calculation indicates that the MFTF neutral-beam system is marginally sufficient to achieve field reversal by neutral injection alone. However, the many uncertainties indicate the need for further research and development on alternate buildup methods. A discussion of experimental objectives is presented and important diagnostics are listed. The range of parameter space accessible with the MFTF magnet design is explored, and we find that with proper aiming of the neutral beams, meaningful experiments can be performed to advance toward these objectives. Finally, it is pointed out that if we achieve enhanced n tau confinement by means of field reversal, then quasi-steady-state operation of MFTF is conceivable

  19. 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

  20. 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

  1. Diamond Ordinance Radiation Facility (DORF) reactor operating experiences

    International Nuclear Information System (INIS)

    Gieseler, Walter

    1970-01-01

    The Diamond Ordnance Radiation Facility Mark F Reactor is described and some of the problems encountered with its operation are discussed. In a period from reactor startup in September 1961 to June 1964, when the aluminum-clad core was changed to a stainless-steel clad core, a total of 30 fuel elements were removed from reactor service because of excessive growth. One leaking fuel element was detected during the lifetime of the aluminum- clad core. In June 1964, the core was changed to the stainless-steel-clad high hydride fuel elements. Since the installation of the stainless-steel-clad fuel element core, there has been a gradual decline of excess reactivity. Various theories were discussed as the cause but the investigations have resulted in no definitive conclusion that could account for the total reactivity loss

  2. Status of Wakefield Monitor Experiments at the CLIC Test Facility

    CERN Document Server

    Lillestøl, Reidar; Aftab, Namra; Corsini, Roberto; Döbert, Steffen; Farabolini, Wilfrid; Grudiev, Alexej; Javeed, Sumera; Pfingstner, Juergen; Wuensch, Walter

    2016-01-01

    For the very low emittance beams in CLIC, it is vital to mitigate emittance growth which leads to reduced luminosity in the detectors. One factor that leads to emittance growth is transverse wakefields in the accelerating structures. In order to combat this the structures must be aligned with a precision of a few um. For achieving this tolerance, accelerating structures are equipped with wakefield monitors that measure higher-order dipole modes excited by the beam when offset from the structure axis. We report on such measurements, performed using prototype CLIC accelerating structures which are part of the module installed in the CLIC Test Facility 3 (CTF3) at CERN. Measurements with and without the drive beam that feeds rf power to the structures are compared. Improvements to the experimental setup are discussed, and finally remaining measurements that should be performed before the completion of the program are summarized.

  3. First experiments at the QSPA-Be plasma gun facility

    International Nuclear Information System (INIS)

    Kovalenko, D V; Klimov, N S; Podkovyrov, V L; Muzichenko, A D; Zhitlukhin, A M; Khimchenko, L N; Kupriyanov, I B; Giniyatulin, R N

    2011-01-01

    This paper presents preliminary results on the erosion of beryllium under hydrogen plasma flow. Two samples made of two types of beryllium, TGP-56PS and S-65C, were exposed to plasma heat loads up to 1 MJ m - 2 and a pulse duration of 0.5 ms at the QSPA-Be facility in Bochvar Institute, Russia. The melting threshold for both beryllium types was experimentally determined to be 0.5 MJ m - 2. The dependence of the specific mass loss and erosion rate on pulse number for both beryllium types was measured. The possibility of generating radiation fluxes with parameters corresponding to mitigated ITER disruptions by means of plasma flow shock braking on a solid bar is shown.

  4. First experiments at the QSPA-Be plasma gun facility

    Science.gov (United States)

    Kovalenko, D. V.; Klimov, N. S.; Podkovyrov, V. L.; Muzichenko, A. D.; Zhitlukhin, A. M.; Khimchenko, L. N.; Kupriyanov, I. B.; Giniyatulin, R. N.

    2011-12-01

    This paper presents preliminary results on the erosion of beryllium under hydrogen plasma flow. Two samples made of two types of beryllium, TGP-56PS and S-65C, were exposed to plasma heat loads up to 1 MJ m-2 and a pulse duration of 0.5 ms at the QSPA-Be facility in Bochvar Institute, Russia. The melting threshold for both beryllium types was experimentally determined to be 0.5 MJ m-2. The dependence of the specific mass loss and erosion rate on pulse number for both beryllium types was measured. The possibility of generating radiation fluxes with parameters corresponding to mitigated ITER disruptions by means of plasma flow shock braking on a solid bar is shown.

  5. Criticality experiments with fast flux test facility fuel pins

    International Nuclear Information System (INIS)

    Bierman, S.R.

    1990-11-01

    A United States Department of Energy program was initiated during the early seventies at the Hanford Critical Mass Laboratory to obtain experimental criticality data in support of the Liquid Metal Fast Breeder Reactor Program. The criticality experiments program was to provide basic physics data for clean well defined conditions expected to be encountered in the handling of plutonium-uranium fuel mixtures outside reactors. One task of this criticality experiments program was concerned with obtaining data on PuO 2 -UO 2 fuel rods containing 20--30 wt % plutonium. To obtain this data a series of experiments were performed over a period of about twelve years. The experimental data obtained during this time are summarized and the associated experimental assemblies are described. 8 refs., 7 figs

  6. Multisensory experiments and data acquisition systems on the meson facilities

    International Nuclear Information System (INIS)

    Bystritskij, V.M.

    2000-01-01

    The paper describes some of the multisensory experiments performed or being performed at the meson factories PSI (Switzerland), TRIUMF (Canada), LAMPF (USA), KEK (Japan), RAL (England) in order to investigate the fundamental processes in elementary particle physics. Designs of various detectors are briefly reviewed, the organizational ideology and the structure of the recording electronics and data acquisition systems for these experiments are considered. The ideology underlying the off-line analysis software is touched upon and the most important results of the investigations at meson factories are given

  7. 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

  8. 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)

  9. 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.

  10. 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

  11. One year's experience of the WA medical cyclotron and radiopharmaceutical production facility

    International Nuclear Information System (INIS)

    DeRoach, J.; Tuchyna, T.; Jones, C.; Price, R.

    2004-01-01

    9 days owing to scheduled maintenance, and a total of 35 (1.6%) patients were cancelled owing to unscheduled maintenance on 7 days. The following major initiatives are now in place for the further development of this facility: 1. Development of a solid targetry facility for the production of 123 I, 124 I, 64 Cu, and other isotopes. Two prototype external beam lines have been developed and trialled. Experiments designed to measure the beam profile at the end of the external beam line are underway. 2. A synthesis module for the production of 18 FMISO and 18 FLT is being developed in-house in collaboration with the cyclotron manufacturer. 3. A module for the synthesis of 18 F-Choline has been installed. 4. A prototype synthesis module is under development which will allow experimentation in the production of novel radiopharmaceuticals based on isotopes produced from liquid targetry. Normalised over 12 months, production staff received on average 3.28 mSv whole body effective dose, with the worst case being 8.46 mSv. Finger doses were 35.6 mSv on average, 70.6 mSv worst case. (Note that production staff also dispense patient doses into individual syringes). Similarly, maintenance staff received 1.41 mSv (avg), 2.56 mSv (max) whole body effective dose, and 33.0 mSv (avg), 124.3 mSv (max) finger dose. A facility for the production and development of short-lived PET radiopharmaceuticals has been created with a capacity that is expected to satisfy Western Australian demands for the next ten years. This facility reliably and routinely produces FDG, and incorporates a well supported and vigorous radiopharmaceutical development function. Copyright (2004) Australasian College of Physical Scientists and Engineers in Medicine

  12. PROJECT EXPERIENCE REPORT DEMOLITION OF HANFORDS 233-S PLUTONIUM CONCENTRATION FACILITY

    International Nuclear Information System (INIS)

    BERLIN, G.T.; ORGILL, T.K.

    2004-01-01

    This report provides a summary of the preparation, operations, innovative work practices, and lessons learned associated with demolition of the 2334 Plutonium Concentration Facility. This project represented the first open-air demolition of a highly-contaminated plutonium facility at the Hanford Site. This project may also represent the first plutonium facility in the US. Department of Energy (DOE) complex to have been demolished without first decontaminating surfaces to near ''free release'' standards. Demolition of plutonium contaminated structures, if not properly managed, can subject cleanup personnel and the environment to significant risk. However, with proper sequencing and innovative use of commercially available equipment, materials, and services, this project demonstrated that a plutonium processing facility can be demolished while avoiding the need to perform extensive decontamination or to construct large enclosures. This project utilized an excavator with concrete shears, diamond circular saws, water misting and fogging equipment, commercially available fixatives and dust suppressants, conventional mobile crane and rigging services, and near real-time modeling of meteorological and radiological conditions. Following a significant amount of preparation, actual demolition of the 233-S Facility began in October 2003 and was completed in late April 2004. The knowledge and experience gained on this project are important to the Hanford Site as additional plutonium processing facilities are scheduled for demolition in the near future. Other sites throughout the DOE Complex may also be faced with similar challenges. Numerous innovations and effective work practices were implemented on this project. Accordingly, a series of ''Lessons Learned and Innovative Practices Fact Sheets'' were developed and are included as an appendix to this report. This collection of fact sheets is not intended to capture every innovative work practice and lesson learned, but rather

  13. PROJECT EXPERIENCE REPORT DEMOLITION OF HANFORDS 233-S PLUTONIUM CONCENTRATION FACILITY

    International Nuclear Information System (INIS)

    BERLIN, G.T.

    2004-01-01

    This report provides a summary of the preparation, operations, innovative work practices, and lessons learned associated with demolition of the 2334 Plutonium Concentration Facility. This project represented the first open-air demolition of a highly-contaminated plutonium facility at the Hanford Site. This project may also represent the first plutonium facility in the US. Department of Energy (DOE) complex to have been demolished without first decontaminating surfaces to near ''free release'' standards. Demolition of plutonium contaminated structures, if not properly managed, can subject cleanup personnel and the environment to significant risk. However, with proper sequencing and innovative use of commercially available equipment, materials, and services, this project demonstrated that a plutonium processing facility can be demolished while avoiding the need to perform extensive decontamination or to construct large enclosures. This project utilized an excavator with concrete shears, diamond circular saws, water misting and fogging equipment, commercially available fixatives and dust suppressants, conventional mobile crane and rigging services, and near real-time modeling of meteorological and radiological conditions. Following a significant amount of preparation, actual demolition of the 2333 Facility began in October 2003 and was completed in late April 2004. The knowledge and experience gained on this project are important to the Hanford Site as additional plutonium processing facilities are scheduled for demolition in the near future. Other sites throughout the DOE Complex may also be faced with similar challenges. Numerous innovations and effective work practices were implemented on this project. Accordingly, a series of ''Lessons Learned and Innovative Practices Fact Sheets'' were developed and are included as an appendix to this report. This collection of fact sheets is not intended to capture every innovative work practice and lesson learned, but rather to

  14. High temperature engineering research facilities and experiments in China

    International Nuclear Information System (INIS)

    Xu, Yuanhui; Liu, Meisheng; Yao, Huizhong; Ju, Huaiming

    1998-01-01

    June 14, 1995, the construction of a pebble bed type high temperature gas-cooled reactor (HTGR) started in China. It is a test reactor with 10 MW thermal power output (termed HTR- 10). The test reactor is located on the site of Institute of Nuclear Energy Technology (INET) of Tsinghua University in the northwest suburb of Beijing, about 40 km away from the city. Design of the HTR-10 test reactor represents the features of HTR-Modular design: 'side-by-side' arrangement, spherical fuel elements with 'multi-pass' loading scheme, completely passive decay heat removal, reactor shutdown systems in the side reflector, etc. However, in the HTR-10 design some modifications from the HTR-Module were made to satisfy Chinese conditions. For example, the steam generator is composed of a number of modular helical tubes with small diameter, pulse pneumatic discharging apparatus are used in the fuel handling system and step motor driving control rods are designed. These modifications would cause some uncertainty in our design. It is necessary to do engineering experiments to prove these new or modified ideas. Therefore, a program of engineering experiments for HTR-10 key technologies is being conducted at INET. The main aims of these engineering experiments are to verify the designed characteristics and performance of the components and systems, to feedback on design and to obtain operational experiences. Those engineering experiments are depressurization test of the hot gas duct at room temperature and operating pressure, performance test of the hot gas duct at operating helium temperature and pressure, performance test of the pulse pneumatic fuel handling system, test of the control rods driving apparatus, two phase flow stability test for the once through steam generator and cross mixture test at the bottom of the reactor core

  15. 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

  16. X-ray transport and radiation response assessment (XTRRA) experiments at the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Fournier, K. B., E-mail: fournier2@llnl.gov; Brown, C. G.; Yeoman, M. F.; Compton, S.; Holdener, F. R.; Kemp, G. E.; Blue, B. E. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94551 (United States); Fisher, J. H.; Newlander, C. D.; Gilliam, R. P.; Froula, N. [Fifth Gait Technologies, Inc., 14040 Camden Circle, Huntsville, Alabama 35803 (United States); Seiler, S. W.; Davis, J. F.; Lerch, MAJ. A. [Defense Threat Reduction Agency, 8725 John J. Kingman Road, Fort Belvoir, Virginia 22060-6201 (United States); Hinshelwood, D. [Naval Research Laboratory, 4555 Overlook Ave. SW, Washington, DC 20375 (United States); Lilly, M. [Dynasen, Inc., 20 Arnold Pl., Goleta, California 93117 (United States)

    2016-11-15

    Our team has developed an experimental platform to evaluate the x-ray-generated stress and impulse in materials. Experimental activities include x-ray source development, design of the sample mounting hardware and sensors interfaced to the National Ignition Facility’s diagnostics insertion system, and system integration into the facility. This paper focuses on the X-ray Transport and Radiation Response Assessment (XTRRA) test cassettes built for these experiments. The test cassette is designed to position six samples at three predetermined distances from the source, each known to within ±1% accuracy. Built-in calorimeters give in situ measurements of the x-ray environment along the sample lines of sight. The measured accuracy of sample responses as well as planned modifications to the XTRRA cassette is discussed.

  17. 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

  18. Summary review of Mound Facility's experience in decontamination of concrete

    International Nuclear Information System (INIS)

    Combs, A.B.; Davis, W.P.; Garner, J.M.; Geichman, J.R.

    1980-01-01

    Most of the current concrete decontamination work at Mound Facility involves surfaces that are contaminated with plutonium-238. Approximately 60,000 sq. ft. of concrete floors will have to be decontaminated in Mound's current Decontamination and Decommissioning (D and D) Project. Although most of these surfaces are partially protected by a barrier (tile or paint), contaminated water and acid have penetrated these barriers. The technique for decontaminating these floors is desribed. The initial cleaning of the floor involes standard water and detergent. Acids are not used in cleaning as they tend to drive the contamination deeper into the concrete surface. Next, the floor tile is manually removed inside a temporary enclosure under negative and filtered ventilation. Finally, layers of contaminated concrete are mechanically removed inside the ventilated enclosure. The suspected depth and surface area of contamination determines the type of mechanical tool used. In summary, several generic methods of concrete decontamination can be utilized: chemical, such as water, detergent, acids, paint remover, strippable paints, etc.; rotary using sanders, grinders, scarifiers, etc.; impact such as pressure washers (hydrolasers), particle blasters, scabblers, needlers, spallers, paving and rock breakers, ram hoes, etc. The particular method used depends on several factors: surface and area involved; depth of contamination; cost and availability of equipment; usage safety and radiological control; and waste generated

  19. Considerations on collected data with the Low Frequency Facility experiment

    Energy Technology Data Exchange (ETDEWEB)

    Di Virgilio, A [Istituto Nazionale di Fisica Nucleare, Sezione di Pisa, Polo Fibonacci Ed. C, via F. Buonarrori 2, Pisa (Italy); Cella, G [Istituto Nazionale di Fisica Nucleare, Sezione di Pisa, Polo Fibonacci Ed. C, via F. Buonarrori 2, Pisa (Italy); Dattilo, V [EGO, European, Gravitational Observatory, Cascina (Italy); Frasconi, F [Istituto Nazionale di Fisica Nucleare, Sezione di Pisa, Polo Fibonacci Ed. C, via F. Buonarrori 2, Pisa (Italy); Gennai, A [Istituto Nazionale di Fisica Nucleare, Sezione di Pisa, Polo Fibonacci Ed. C, via F. Buonarrori 2, Pisa (Italy); Penna, P La [EGO, European, Gravitational Observatory, Cascina (Italy); Losurdo, G [INFN Sezione di Firenze, Sesto Fiorentino (Italy); Pasqualetti, A [EGO, European, Gravitational Observatory, Cascina (Italy); Passuello, D [Istituto Nazionale di Fisica Nucleare, Sezione di Pisa, Polo Fibonacci Ed. C, via F. Buonarrori 2, Pisa (Italy); Piergiovanni, F [Universita di Urbino, Urbino (Italy); Porzio, A [Coherentia, CNR-INFM Napoli (Italy); Raffaelli, F [Istituto Nazionale di Fisica Nucleare, Sezione di Pisa, Polo Fibonacci Ed. C, via F. Buonarrori 2, Pisa (Italy); Rapagnani, P [Universita di Roma, Roma1, Rome (Italy); Ricci, F [Universita di Roma, Roma1, Rome (Italy); Solimeno, S [Coherentia, CNR-INFM Napoli (Italy); Istituto Nazionale di Fisica Nucleare, Sez. Napoli, and Dipartimento di Scienze Fisiche, Universita di Napoli ' Federico II' (Italy); Zhang, Z [EGO, European, Gravitational Observatory, Cascina (Italy)

    2006-03-02

    The Low Frequency Facility consists of a 1 cm Fabry-Perot cavity suspended to a single SuperAttenuator, which is the mechanical system adopted to isolate the test masses of the Virgo interferometer. In this paper we present the preliminary results of measurements performed with a cavity of finesse 4000 and lasting 1-2 hours in different working conditions. The analysis presented here is focused mainly on the region below 100 Hz, and uses data collected with longitudinal control bandwidth below 150 Hz. A calibration test confirmed that the collected data are in good agreement with the model of the longitudinal control loop based on the open loop measurements. In addition to this, above 2 Hz the power spectrum of the two mirrors relative displacement shows a stationary noise floor and few peaks with high mechanical quality factor. Studying these peaks in the time domain, it has been observed that the energy associated with a single peak is Boltzman distributed, whether the oscillations are not excited. The measured upper limit of the seismic noise contamination at 10 Hz is around 2 x 10{sup -14} m/{radical}Hz.

  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. [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.

  2. 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)

  3. Progress on establishing guidelines for National Ignition Facility (NIF) experiments to extend debris shield lifetime

    International Nuclear Information System (INIS)

    Tobin, M.; Eder, D.; Braun, D.; MacGowan, B.

    2002-01-01

    The survivability of the debris shields on the National Ignition Facility (NIF) are a key factor for the affordable operation of the facility. The improvements required over Nova debris shields are described. Estimates of debris shield lifetimes in the presence of target emissions with 4-8 J/cm 2 laser fluences indicate lifetimes that may contribute unacceptably to operations costs for NIF. We are developing detailed suggested guidance for target and experiment designers for NIF to assist in minimizing the damage to, and therefore the cost of, maintaining NIF debris shields. The guidance suggests a target mass quantity that as particulate on the debris shields (300 mg) may be within current operating budgets. It also suggests the amount of material that should become shrapnel on a shot (10 mg). Finally, it suggests the level of non-volatile residue (NVR) that would threaten the sol-gel coatings on the debris shields (1 μg/cm 2 ). We review the experimentation on the Nova chamber that included measuring quantities of particulate on debris shields by element and capturing shrapnel pieces in aerogel samples mounted in the chamber. We also describe computations of X-ray emissions from a likely NIF target and the associated ablation expected from this X-ray exposure on supporting target hardware. We describe progress in assessing the benefits of a pre-shield and the possible impact on the guidance for target experiments on NIF. Plans for possible experimentation on Omega and other facilities to improve our understanding of target emissions and their impacts are discussed. Our discussion of planned future work provides a forum to invite possible collaboration with the IFE community

  4. Experience in the decontamination and dismantling of alpha facilities

    International Nuclear Information System (INIS)

    Charamathieu, A.

    1988-01-01

    Experience in dismantling alpha-containing radiochemical installations in France is described. The dismantling programme undertaken by the Societe des Techniques en Milieu Ionisant since 1977 is tabulated. This includes the dismantling of CALCIO and FLUO (plutonium metal), the dismantling of a slag processing plant, the dismantling of part of a medium activity plutonium mine and the dismantling of rooms 82-100 at Marcoule, France. (author)

  5. 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

  6. What makes or mars the facility-based childbirth experience: thematic analysis of women's childbirth experiences in western Kenya.

    Science.gov (United States)

    Afulani, Patience A; Kirumbi, Leah; Lyndon, Audrey

    2017-12-29

    Sub-Saharan Africa accounts for approximately 66% of global maternal deaths. Poor person-centered maternity care, which emphasizes the quality of patient experience, contributes both directly and indirectly to these poor outcomes. Yet, few studies in low resource settings have examined what is important to women during childbirth from their perspective. The aim of this study is to examine women's facility-based childbirth experiences in a rural county in Kenya, to identify aspects of care that contribute to a positive or negative birth experience. Data are from eight focus group discussions conducted in a rural county in western Kenya in October and November 2016, with 58 mothers aged 15 to 49 years who gave birth in the preceding nine weeks. We recorded and transcribed the discussions and used a thematic approach for data analysis. The findings suggest four factors influence women's perceptions of quality of care: responsiveness, supportive care, dignified care, and effective communication. Women had a positive experience when they were received well at the health facility, treated with kindness and respect, and given sufficient information about their care. The reverse led to a negative experience. These experiences were influenced by the behavior of both clinical and support staff and the facility environment. This study extends the literature on person-centered maternity care in low resource settings. To improve person-centered maternity care, interventions need to address the responsiveness of health facilities, ensure women receive supportive and dignified care, and promote effective patient-provider communication.

  7. Fuel-Coolant Interaction Experiments in the TROI Facility

    Energy Technology Data Exchange (ETDEWEB)

    Min, B. T.; Hong, S. W.; Hong, S. H.; Park, I. K.; Kim, H. Y.; Song, J. H.; Kim, H. D

    2006-03-15

    A steam explosion has long been a concern in case of severe accidents in a nuclear reactor, since it might threaten the integrity of the containment. Although many studies have been performed on a steam explosion, there are still some remaining unsolved issues such as the explosivity of the real core material (corium) and the estimation of the energy conversion ratio. At the Korea Atomic Energy Research Institute (KAERI), the TROI steam explosion experiments were performed, in order to investigate the explosivity of corium. The TROI experiments were carried out to provide the experimental data for a proper estimation of a structural loading resulting from a steam explosion. These experiments were performed with prototypic materials such as ZrO{sub 2} melt and a mixture of ZrO{sub 2} and UO{sub 2} melt (corium). Total 46 tests were conducted in the TROI test series from year 2000 to the end of year 2004. The main test parameters were the variations on the composition of the melt, geometry of the interaction vessel, sub-cooling, ambient pressure, and amount of melt. Additionally the effects of an external trigger and argon environment were investigated. The main findings are that the composition, geometry, and inert gas had dominant effects on energetic steam explosions. In addition, the strength of the steam explosion was not that much strong compared to that of alumina, such as KROTOS-44. Even though efforts were made to maximize the strength of a steam explosion by increasing the amount of melt mass in water (increasing water depth), and fuel fraction (using a narrow test section), it did not work. The test results suggest that the melt of pure zirconia or eutectic corium in a wide test section leads to energetic spontaneous or triggered steam explosions, while the melt of other compositions does not.

  8. Gas-filled hohlraum experiments at the national ignition facility.

    Energy Technology Data Exchange (ETDEWEB)

    Fernández, J. C. (Juan C.); Gautier, D. C. (Donald Cort); Goldman, S. R. (Sanford R.); Grimm, B. M.; Hegelich, B. M. (Bjorn M.); Kline, J. L. (John L.); Montgomery, D. S. (David S.); Lanier, N. E. (Nicholas E.); Rose, H. A. (Harvey A.); Schmidt, D. M. (David M.); Swift, D. C.; Workman, J. B. (Jonathan B.); Alvarez, Sharon; Bower, Dan.; Braun, Dave.; Campbell, K. (Katherine); DeWald, E.; Glenzer, S. (Siegfried); Holder, J. (Joe P.); Kamperschroer, J. H. (James H.); Kimbrough, Joe (Joseph R.); Kirkwood, Robert (Bob); Landen, O. L. (Otto L.); Mccarville, Tom (Tomas J.); Macgowan, B.; Mackinnon, A.; Niemann, C.; Schein, J.; Schneider, M; Watts, Phil; Young, Ben-li [number : znumber] 194154; Young B.

    2004-01-01

    The summary of this paper is: (1) We have fielded on NIF a gas-filled hohlraum designed for future ignition experiments; (2) Wall-motion measurements are consistent with LASNEX simulations; (3) LPI back-scattering results have confounded expectations - (a) Stimulated Brillouin (SBS) dominates Raman (SRS) for any gas-fill species, (b) Measured SBS time-averaged reflectivity values are high, peak values are even higher, (c) SRS and SBS peak while laser-pulse is rising; and (4) Plasma conditions at the onset of high back-scattering yield high SBS convective linear gain - Wavelengths of the back-scattered light is predicted by linear theory.

  9. Soft x-ray laser experiments at Novette Laser Facility

    International Nuclear Information System (INIS)

    Matthews, D.; Hagelstein, P.; Rosen, M.

    1984-01-01

    We discuss the results of and future plans for experiments to study the possibility of producing an x-ray laser. The schemes we have investigated are all pumped by the Novette Laser, operated at short pulse (tau/sub L/ approx. 100 psec) and an incident wavelength of lambda /sub L/ approx. 0.53 μm. We have studied the possibility of lasing at 53.6, 68.0 to 72.0, 119.0, and 153.0 eV, using the inversion methods of resonant photo-excitation, collisional excitation, and three-body recombination

  10. Gas-filled hohlraum experiments at the national ignition facility

    International Nuclear Information System (INIS)

    Fernandez, J.C.; Gautier, D.C.; Goldman, S.R.; Grimm, B.M.; Hegelich, B.M.; Kline, J.L.; Montgomery, D.S.; Lanier, N.E.; Rose, H.A.; Schmidt, D.M.; Swift, D.C.; Workman, J.B.; Alvarez, Sharon; Bower, Dan; Braun, Dave; Campbell, K.; DeWald, E.; Glenzer, S.; Holder, J.; Kamperschroer, J.H.; Kimbrough, Joe; Kirkwood, Robert; Landen, O.L.; Mccarville, Tom; Macgowan, B.; Mackinnon, A.; Niemann, C.; Schein, J.; Schneider, M.; Watts, Phil; Young, Ben-li; Young B.

    2004-01-01

    The summary of this paper is: (1) We have fielded on NIF a gas-filled hohlraum designed for future ignition experiments; (2) Wall-motion measurements are consistent with LASNEX simulations; (3) LPI back-scattering results have confounded expectations - (a) Stimulated Brillouin (SBS) dominates Raman (SRS) for any gas-fill species, (b) Measured SBS time-averaged reflectivity values are high, peak values are even higher, (c) SRS and SBS peak while laser-pulse is rising; and (4) Plasma conditions at the onset of high back-scattering yield high SBS convective linear gain - Wavelengths of the back-scattered light is predicted by linear theory.

  11. An Overview of the GOLD Experiment Between the ETS-6 Satellite and the Table Mountain Facility

    Science.gov (United States)

    Wilson, K. E.

    1996-01-01

    The Ground/Orbiter Lasercomm Demonstration is a demonstration of optical communications between the Japanese Engineering Test Satellite (ETS-VI) and an optical ground transmitting and receiving station at the Table Mountain Facility in Wrightwood, California. Laser transmissions to the satellite are performed for approximately 4 hours every third night when the satellite is at apogee above Table Mountain. The experiment requires the coordination of resources at the Communications Research Laboratory (CRL), JPL, the National Aeronautics and Space Development Agency (NASDA) Tsukuba tracking station, and NASA's Deep Space Network at Goldstone, California, to generate and transmit real-time commands and receive telemetry from the ETS-VI. Transmissions to the ETS-VI began in November 1995 and are scheduled to last into the middle of January 1996, when the satellite is expected to be eclipsed by the Earth's shadow for a major part of its orbit. The eclipse is expected to last for about 2 months, and during this period there will be limited electrical power available on board the satellite. NASDA plans to restrict experiments with the ETS-VI during this period, and no laser transmissions are planned. Posteclipse experiments are currently being negotiated. GOLD is a joint NASA-CRL experiment that is being conducted by JPL in coordination with CRL and NASDA.

  12. 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)

  13. 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.

  14. 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.)

  15. 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

  16. 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

  17. 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

  18. Radon Reduction Experience at a Former Uranium Processing Facility

    International Nuclear Information System (INIS)

    Eger, K. J.; Rutherford, L.; Rickett, K.; Fellman, R.; Hungate, S.

    2004-01-01

    Approximately 6,200 cubic meters of waste containing about 2.0E8 MBq of radium-226 are stored in two large silos at the Fernald Site in southwest Ohio. The material is scheduled for retrieval, packaging, off site shipment and disposal by burial. Air in the silos above the stored material contained radon-222 at a concentration of 7.4 E5 Bq/L. Short-lived daughters formed by decay in these headspaces generated dose rates at contact with the top of the silos up to 1.05 mSv/hr and there complicate the process of retrieval. A Radon Control System (RCS) employing carbon adsorption beds has been designed under contract with the Fluor Fernald to remove most of the radon in the headspaces and maintain lower concentrations during periods when work on or above the domes is needed. Removing the radon also removes the short-lived daughters and reduces the dose rate near the domes to 20 to 30 μSv/hr. Failing to remove the radon would be costly, in the exposure of personnel needed to work extended periods at these moderate dose rates, or in dollars for the application of remote retrieval techniques. In addition, the RCS minimizes the potential for environmental releases. This paper describes the RCS, its mode of operation, and early experiences. The results of the test described herein and the experience gained from operation of the RCS during its first phase of continuous operation, will be used to determine the best air flow, and air flow distribution, the most desirable number and sequence number and sequence of adsorption beds to be used and the optimum application of air recycle within the RCS

  19. 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.

  20. 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.

  1. 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

  2. Conceptual design of initial opacity experiments on the national ignition facility

    Science.gov (United States)

    Heeter, R. F.; Bailey, J. E.; Craxton, R. S.; Devolder, B. G.; Dodd, E. S.; Garcia, E. M.; Huffman, E. J.; Iglesias, C. A.; King, J. A.; Kline, J. L.; Liedahl, D. A.; McKenty, P. W.; Opachich, Y. P.; Rochau, G. A.; Ross, P. W.; Schneider, M. B.; Sherrill, M. E.; Wilson, B. G.; Zhang, R.; Perry, T. S.

    2017-02-01

    Accurate models of X-ray absorption and re-emission in partly stripped ions are necessary to calculate the structure of stars, the performance of hohlraums for inertial confinement fusion and many other systems in high-energy-density plasma physics. Despite theoretical progress, a persistent discrepancy exists with recent experiments at the Sandia Z facility studying iron in conditions characteristic of the solar radiative-convective transition region. The increased iron opacity measured at Z could help resolve a longstanding issue with the standard solar model, but requires a radical departure for opacity theory. To replicate the Z measurements, an opacity experiment has been designed for the National Facility (NIF). The design uses established techniques scaled to NIF. A laser-heated hohlraum will produce X-ray-heated uniform iron plasmas in local thermodynamic equilibrium (LTE) at temperatures eV and electron densities 21~\\text{cm}-3$ . The iron will be probed using continuum X-rays emitted in a ps, diameter source from a 2 mm diameter polystyrene (CH) capsule implosion. In this design, of the NIF beams deliver 500 kJ to the mm diameter hohlraum, and the remaining directly drive the CH capsule with 200 kJ. Calculations indicate this capsule backlighter should outshine the iron sample, delivering a point-projection transmission opacity measurement to a time-integrated X-ray spectrometer viewing down the hohlraum axis. Preliminary experiments to develop the backlighter and hohlraum are underway, informing simulated measurements to guide the final design.

  3. Benchmark experiments at ASTRA facility on definition of space distribution of 235U fission reaction rate

    International Nuclear Information System (INIS)

    Bobrov, A. A.; Boyarinov, V. F.; Glushkov, A. E.; Glushkov, E. S.; Kompaniets, G. V.; Moroz, N. P.; Nevinitsa, V. A.; Nosov, V. I.; Smirnov, O. N.; Fomichenko, P. A.; Zimin, A. A.

    2012-01-01

    Results of critical experiments performed at five ASTRA facility configurations modeling the high-temperature helium-cooled graphite-moderated reactors are presented. Results of experiments on definition of space distribution of 235 U fission reaction rate performed at four from these five configurations are presented more detail. Analysis of available information showed that all experiments on criticality at these five configurations are acceptable for use them as critical benchmark experiments. All experiments on definition of space distribution of 235 U fission reaction rate are acceptable for use them as physical benchmark experiments. (authors)

  4. Does identity shape leadership and management practice? Experiences of PHC facility managers in Cape Town, South Africa

    Science.gov (United States)

    Daire, Judith; Gilson, Lucy

    2014-01-01

    In South Africa, as elsewhere, Primary Health Care (PHC) facilities are managed by professional nurses. Little is known about the dimensions and challenges of their job, or what influences their managerial practice. Drawing on leadership and organizational theory, this study explored what the job of being a PHC manager entails, and what factors influence their managerial practice. We specifically considered whether the appointment of professional nurses as facility managers leads to an identity transition, from nurse to manager. The overall intention was to generate ideas about how to support leadership development among PHC facility managers. Adopting case study methodology, the primary researcher facilitated in-depth discussions (about their personal history and managerial experiences) with eight participating facility managers from one geographical area. Other data were collected through in-depth interviews with key informants, document review and researcher field notes/journaling. Analysis involved data triangulation, respondent and peer review and cross-case analysis. The experiences show that the PHC facility manager’s job is dominated by a range of tasks and procedures focused on clinical service management, but is expected to encompass action to address the population and public health needs of the surrounding community. Managing with and through others, and in a complex system, requiring self-management, are critical aspects of the job. A range of personal, professional and contextual factors influence managerial practice, including professional identity. The current largely facility-focused management practice reflects the strong nursing identity of managers and broader organizational influences. However, three of the eight managers appear to self-identify an emerging leadership identity and demonstrate related managerial practices. Nonetheless, there is currently limited support for an identity transition towards leadership in this context. Better

  5. Future facilities for light quark spectroscopy: A perspective based on the LASS experience

    International Nuclear Information System (INIS)

    Ratcliff, B.N.

    1991-10-01

    Some desirable design features of a future facility for the study of light meson spectroscopy in hadroproduction are described and compared with what has been achieved by the LASS spectrometer. A few aspects of next-generation experiments using such a facility are also discussed, including final state sample sizes and performance requirements. The need for complementary production modes and decay channels, and the importance of a broad programmatic approach to the physics are stressed

  6. Health physics experience with nondestructive X-radiation facilities in the US Air Force

    International Nuclear Information System (INIS)

    Stencel, J.R.; Piltingsrud, H.V.

    1976-01-01

    Radiation safety experience in the construction and use of enclosed nondestructive inspection (NDI) facilities in the US Air Force, has reaffirmed the constant need for the health physicist to continually monitor and assit in upgrading these facilities. Health physics contributions include evaluation of initial shielding requirements, proper selection of construction material, insuring that adequate safety devices are installed and adequate personnel dosimetry devices are available, surveying the facility, and assisting in the safety education program. There is a need to better define NDI warning/safety devices, using the National Bureau of Standards, (NBS) Handbook 107 as the most applicable guide

  7. Cause finding experiments and environmental analysis on the accident of the fire and explosion in TRP bituminization facility

    International Nuclear Information System (INIS)

    Fujine, Sachio; Murata, Mikio; Abe, Hitoshi

    1999-09-01

    This report is the summary of the cause finding experiments and environmental analysis on the accident of the fire and explosion occurred at March 11th, 1997, in TRP bituminization facility of PNC (Power Reactor and Nuclear Fuel Development Corporation). Regarding the cause finding experiments, chemical components have been analyzed for the effluent samples taken from PNC's facility, bituminized mock waste has been produced using the simulated salt effluent prepared according to the results of chemical analysis, thermal analysis and experiment of runaway exothermic reaction have been conducted using the mock waste, and the component of flammable gases emitted from the heated waste have been collected and analyzed. Regarding environmental analysis on the accident, the amount of radioactive cesium released by the accident has been calculated by the comparative analysis using the atmospheric dispersion simulation code SPEEDI with the data of environmental monitoring and the public dose has been assessed. (author)

  8. Ground-facilities at the DLR Institute of Aerospace Medicine for preparation of flight experiments

    Science.gov (United States)

    Hemmersbach, Ruth; Hendrik Anken, Ralf; Hauslage, Jens; von der Wiesche, Melanie; Baerwalde, Sven; Schuber, Marianne

    In order to investigate the influence of altered gravity on biological systems and to identify gravisensitive processes, various experimental platforms have been developed, which are useful to simulate weightlessness or are able to produce hypergravity. At the Institute of Aerospace Medicine, DLR Cologne, a broad spectrum of applications is offered to scientists: clinostats with one rotation axis and variable rotation speeds for cultivation of small objects (including aquatic organisms) in simulated weightlessness conditions, for online microscopic observations and for online kinetic measurements. Own research concentrates on comparative studies with other kinds of methods to simulate weightlessness, also available at the institute: Rotating Wall Vessel (RWV) for aquatic studies, Random Positioning Machine (RPM; manufactured by Dutch Space, Leiden, The Netherlands). Correspondingly, various centrifuge devices are available to study different test objects under hypergravity conditions -such as NIZEMI, a slow rotating centrifuge microscope, and MUSIC, a multi-sample centrifuge. Mainly for experiments with human test subjects (artificial gravity), but also for biological systems or for testing various kinds of (flight-) hardware, the SAHC, a short arm human centrifuge -loaned by ESA -was installed in Cologne and completes our experimental scenario. Furthermore, due to our specific tasks such as providing laboratories during the German Parabolic Flight Experiments starting from Cologne and being the Facility Responsible Center for BIOLAB, a science rack in the Columbus module aboard the ISS, scientists have the possibility for an optimal preparation of their flight experiments.

  9. Performance Evaluation of the International Space Station Flow Boiling and Condensation Experiment (FBCE) Test Facility

    Science.gov (United States)

    Hasan, Mohammad; Balasubramaniam, R.; Nahra, Henry; Mackey, Jeff; Hall, Nancy; Frankenfield, Bruce; Harpster, George; May, Rochelle; Mudawar, Issam; Kharangate, Chirag R.; hide

    2016-01-01

    A ground-based experimental facility to perform flow boiling and condensation experiments is built in support of the development of the long duration Flow Boiling and Condensation Experiment (FBCE) destined for operation on board of the International Space Station (ISS) Fluid Integrated Rack (FIR). We performed tests with the condensation test module oriented horizontally and vertically. Using FC-72 as the test fluid and water as the cooling fluid, we evaluated the operational characteristics of the condensation module and generated ground based data encompassing the range of parameters of interest to the condensation experiment to be performed on the ISS. During this testing, we also evaluated the pressure drop profile across different components of the fluid subsystem, heater performance, on-orbit degassing subsystem, and the heat loss from different components. In this presentation, we discuss representative results of performance testing of the FBCE flow loop. These results will be used in the refinement of the flight system design and build-up of the FBCE which is scheduled for flight in 2019.

  10. 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)

  11. 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)

  12. Operating experience review - Ventilation systems at Department of Energy Facilities

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-01

    The Office of Special Projects (DP-35), formerly Office of Self-Assessment (DP-9), analyzed occurrences caused by problems with equipment and material and recommended the following systems for an in-depth study: (1) Selective Alpha Air Monitor (SAAM), (2) Emergency Diesel Generator, (3) Ventilation System, (4) Fire Alarm System. Further, DP-35 conducted an in-depth review of the problems associated with SAAM and with diesel generators, and made several recommendations. This study focusses on ventilation system. The intent was to determine the causes for the events related to these system that were reported in the Occurrence Reporting and Processing System (ORPS), to identify components that failed, and to provide technical information from the commercial and nuclear industries on the design, operation, maintenance, and surveillance related to the system and its components. From these data, sites can develop a comprehensive program of maintenance management, including surveillance, to avoid similar occurrences, and to be in compliance with the following DOE orders.

  13. Experience in developing countries in monitoring procurement and fabrication

    International Nuclear Information System (INIS)

    Csik, B.J.

    1977-01-01

    Owner's responsibility in monitoring procurement and fabrication. Monitoring ectivity, tasks, knowledge and personnel requirements, scope and organization. Contractual arrangements, commitments, responsibilities, rights and obligations. Domestic and foreign supplies. Staff and consultants. Experience in developing countries. Problem areas: availability of qualified staff, organization, methodology standards, codes, specifications, availability and flow of information, language, technical knowledge, access to suppliers' facilities, delays, nuclear safety related components, modifications and additionals. (orig.) [de

  14. A simple irradiation facility for radiobiological experiments with low energy protons from a cyclotron

    International Nuclear Information System (INIS)

    Mukherjee, B.

    1982-01-01

    An experimental facility for irradiation of small biological targets with low-energy protons has been developed. The depth-dose distribution in soft-tissue is calculated from the proton energy spectrum. (orig.)

  15. Tethered elevator and platforms as space station facilities: Systems studies and demonstrative experiments

    Science.gov (United States)

    1986-01-01

    Several key concepts of the science and applications tethered platforms were studied. Some conclusions reached are herein listed. Tether elevator and platform could improve the space station scientific and applicative capabilities. The space elevator presents unique characteristics as microgravity facility and as a tethered platform servicing vehicle. Pointing platforms could represent a new kind of observation facility for large class of payloads. The dynamical, control and technological complexity of these concepts advised demonstrative experiments. The on-going tethered satellite system offers the opportunity to perform such experiments. And feasibility studies are in progress.

  16. First start-up of nuclear criticality safety experiment facility for uranyl nitrate solution

    International Nuclear Information System (INIS)

    Zhu Qingfu; Shi Yongqian; Shen Leisheng; Hu Dingsheng; Zhao Shouzhi; He Tao; Sun Zheng; Lin Shenghuo; Yao Shigui

    2005-01-01

    The uranyl nitrate solution experiment facility for the research on nuclear criticality safety is described. The nuclear fuel loading steps in the first start-up for water-reflected core are presented. During the experiments, the critical volume of uranyl nitrate solution was determined as 20479.62 mL with count rate inverse extrapolation method, reactivity interpolation method, and steady power method. By calculation, critical mass of 235 U was derived as 1579.184 g from experimental data. The worth of control rods was also calibrated in the first start-up of the facility. (authors)

  17. Criticality experiment for No.2 core of DF-VI fast neutron criticality facility

    International Nuclear Information System (INIS)

    Yang Lijun; Liu Zhenhua; Yan Fengwen; Luo Zhiwen; Chu Chun; Liang Shuhong

    2007-01-01

    At the completion of the DF-VI fast neutron criticality facility, its core changed, and it was restarted and a series of experiments and measurements were made. According to the data from 29 criticality experiments, the criticality element number and mass were calculated, the control rod reactivity worth were measured by period method and rod compensate method, reactivity worth of safety rod and safety block were measured using reactivity instrument; the reactivity worth of outer elements and radial distribution of elements were measured too. Based on all the measurements mentioned above, safety operation parameters for core 2 in DF-VI fast neutron criticality facility were conformed. (authors)

  18. Discussion of the use of the Dragon reactor as a facility for integral reactor physics experiments

    Energy Technology Data Exchange (ETDEWEB)

    Gutmann, H

    1972-06-05

    The purpose and use of the Dragon Reactor Experiment (DRE) has changed considerably during the years of its operation. The original purpose was to show that the principle of a High Temperature Reactor is sound and demonstrate its operation. After this achievement, the purpose of the Dragon reactor changed to the use as a fuel testing facility. During recent years, a new use of the DRE has been added to its use as a fuel testing facility, namely Fuel Element Design Testing. The current report covers reactor physics experiments aspects.

  19. Soil and crop management experiments in the Laboratory Biosphere: An analogue system for the Mars on Earth ® facility

    Science.gov (United States)

    Silverstone, S.; Nelson, M.; Alling, A.; Allen, J. P.

    During the years 2002 and 2003, three closed system experiments were carried out in the "Laboratory Biosphere" facility located in Santa Fe, New Mexico. The program involved experimentation of "Hoyt" Soy Beans, (experiment #1) USU Apogee Wheat (experiment #2) and TU-82-155 sweet potato (experiment #3) using a 5.37 m 2 soil planting bed which was 30 cm deep. The soil texture, 40% clay, 31% sand and 28% silt (a clay loam), was collected from an organic farm in New Mexico to avoid chemical residues. Soil management practices involved minimal tillage, mulching, returning crop residues to the soil after each experiment and increasing soil biota by introducing worms, soil bacteria and mycorrhizae fungi. High soil pH of the original soil appeared to be a factor affecting the first two experiments. Hence, between experiments #2 and #3, the top 15 cm of the soil was amended using a mix of peat moss, green sand, humates and pumice to improve soil texture, lower soil pH and increase nutrient availability. This resulted in lowering the initial pH of 8.0-6.7 at the start of experiment #3. At the end of the experiment, the pH was 7.6. Soil nitrogen and phosphorus has been adequate, but some chlorosis was evident in the first two experiments. Aphid infestation was the only crop pest problem during the three experiments and was handled using an introduction of Hyppodamia convergens. Experimentation showed there were environmental differences even in this 1200 cubic foot ecological system facility, such as temperature and humidity gradients because of ventilation and airflow patterns which resulted in consequent variations in plant growth and yield. Additional humidifiers were added to counteract low humidity and helped optimize conditions for the sweet potato experiment. The experience and information gained from these experiments are being applied to the future design of the Mars On Earth ® facility (Silverstone et al., Development and research program for a soil

  20. Operation databook of the fuel treatment system of the Static Experiment Critical Facility (STACY) and the Transient Experiment Critical Facility (TRACY). JFY 2004 to JFY 2008

    International Nuclear Information System (INIS)

    Kokusen, Junya; Sumiya, Masato; Seki, Masakazu; Kobayashi, Fuyumi; Ishii, Junichi; Umeda, Miki

    2013-02-01

    Uranyl nitrate solution fuel used in the Static Experiment Critical Facility (STACY) and the Transient Experiment Critical Facility (TRACY) is adjusted in the Fuel Treatment System, in which such parameters are varied as concentration of uranium, free nitric acid, soluble neutron poison, and so on. Operations for concentration and denitration of the solution fuel were carried out with an evaporator from JFY 2004 to JFY 2008 in order to adjust the fuel to the experimental condition of the STACY and the TRACY. In parallel, the solution fuel in which some kinds of soluble neutron poison were doped was also adjusted in JFY 2005 and JFY 2006 for the purpose of the STACY experiments to determine neutron absorption effects brought by fission products, etc. After these experiments in the STACY, a part of the solution fuel including the soluble neutron poison was purified by the solvent extraction method with mixer-settlers in JFY 2006 and JFY 2007. This report summarizes operation data of the Fuel Treatment System from JFY 2004 to JFY 2008. (author)

  1. STAR - Research Experiences at National Laboratory Facilities for Pre-Service and Early Career Teachers

    Science.gov (United States)

    Keller, J. M.; Rebar, B.; Buxner, S.

    2012-12-01

    The STEM Teacher and Researcher (STAR) Program provides pre-service and beginning teachers the opportunity to develop identity as both teachers and researchers early in their careers. Founded and implemented by the Center for Excellence in Science and Mathematics Education (CESaME) at California Polytechnic State University on behalf of the California State University (CSU) system, STAR provides cutting edge research experiences and career development for students affiliated with the CSU system. Over the past three summers, STAR has also partnered with the NSF Robert Noyce Teacher Scholarship Program to include Noyce Scholars from across the country. Key experiences are one to three summers of paid research experience at federal research facilities associated with the Department of Energy (DOE), National Aeronautics and Space Administration (NASA), National Oceanic and Atmospheric Association (NOAA), and the National Optical Astronomy Observatory (NOAO). Anchoring beginning teachers in the research community enhances participant understanding of what it means to be both researchers and effective teachers. Since its inception in 2007, the STAR Program has partnered with 15 national lab facilities to provide 290 research experiences to 230 participants. Several of the 68 STAR Fellows participating in the program during Summer 2012 have submitted abstracts to the Fall AGU Meeting. Through continued partnership with the Noyce Scholar Program and contributions from outside funding sources, the CSU is committed to sustaining the STAR Program in its efforts to significantly impact teacher preparation. Evaluation results from the program continue to indicate program effectiveness in recruiting high quality science and math majors into the teaching profession and impacting their attitudes and beliefs towards the nature of science and teaching through inquiry. Additionally, surveys and interviews are being conducted of participants who are now teaching in the classroom as

  2. Rural energetic development: cuban experience

    International Nuclear Information System (INIS)

    Aguilera Barciela, M.

    1994-01-01

    The development of electro energetic national system in Cuba has been directed to the following objectives: to brake the rural population's exodus toward the cities, electrification of dairy farm, interconnection to the system electro energetic of all the sugar central production, these improves the rural population's conditions life

  3. 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

  4. 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)

  5. 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

  6. 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

  7. 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)

  8. 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

  9. 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

  10. Experiment-specific analyses in support of code development

    International Nuclear Information System (INIS)

    Ott, L.J.

    1990-01-01

    Experiment-specific models have been developed since 1986 by Oak Ridge National Laboratory Boiling Water Reactor (BWR) severe accident analysis programs for the purpose of BWR experimental planning and optimum interpretation of experimental results. These experiment-specific models have been applied to large integral tests (ergo, experiments) which start from an initial undamaged core state. The tests performed to date in BWR geometry have had significantly different-from-prototypic boundary and experimental conditions because of either normal facility limitations or specific experimental constraints. These experiments (ACRR: DF-4, NRU: FLHT-6, and CORA) were designed to obtain specific phenomenological information such as the degradation and interaction of prototypic components and the effects on melt progression of control-blade materials and channel boxes. Applications of ORNL models specific to the ACRR DF-4 and KfK CORA-16 experiments are discussed and significant findings from the experimental analyses are presented. 32 refs., 16 figs

  11. In situ water and gas injection experiments performed in the Hades Underground Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Volckaert, G.; Ortiz, L.; Put, M. [SCK-CEN, Mol (Belgium). Geological Waste Disposal Unit

    1995-12-31

    The movement of water and gas through plastic clay is an important subject in the research at SCK-CEN on the possible disposal of high level radioactive waste in the Boom clay layer at Mol. Since the construction of the Hades underground research facility in 1983, SCK-CEN has developed and installed numerous piezometers for the geohydrologic characterization and for in situ radionuclide migration experiments. In situ gas and water injection experiments have been performed at two different locations in the underground laboratory. The first location is a multi filter piezometer installed vertically at the bottom of the shaft in 1986. The second location is a three dimensional configuration of four horizontal multi piezometers installed from the gallery. This piezometer configuration was designed for the MEGAS (Modelling and Experiments on GAS migration through argillaceous rocks) project and installed in 1992. It contains 29 filters at distances between 10 m and 15 m from the gallery in the clay. Gas injection experiments show that gas breakthrough occurs at a gas overpressure of about 0.6 MPa. The breakthrough occurs by the creation of gas pathways along the direction of lowest resistance i.e. the zone of low effective stress resulting from the drilling of the borehole. The water injections performed in a filter -- not used for gas injection -- show that the flow of water is also influenced by the mechanical stress conditions. Low effective stress leads to higher hydraulic conductivity. However, water overpressures up to 1.3 MPa did not cause hydrofracturing. Water injections performed in a filter previously used for gas injections, show that the occluded gas hinders the water flow and reduces the hydraulic conductivity by a factor two.

  12. Rugby and elliptical-shaped hohlraums experiments on the OMEGA laser facility

    Science.gov (United States)

    Tassin, Veronique; Monteil, Marie-Christine; Depierreux, Sylvie; Masson-Laborde, Paul-Edouard; Philippe, Franck; Seytor, Patricia; Fremerye, Pascale; Villette, Bruno

    2017-10-01

    We are pursuing on the OMEGA laser facility indirect drive implosions experiments in gas-filled rugby-shaped hohlraums in preparation for implosion plateforms on LMJ. The question of the precise wall shape of rugby hohlraum has been addressed as part of future megajoule-scale ignition designs. Calculations show that elliptical-shaped holhraum is more efficient than spherical-shaped hohlraum. There is less wall hydrodynamics and less absorption for the inner cone, provided a better control of time-dependent symmetry swings. In this context, we have conducted a series of experiments on the OMEGA laser facility. The goal of these experiments was therefore to characterize energetics with a complete set of laser-plasma interaction measurements and capsule implosion in gas-filled elliptical-shaped hohlraum with comparison with spherical-shaped hohlraum. Experiments results are discussed and compared to FCI2 radiation hydrodynamics simulations.

  13. Record keeping for the decommissioning of nuclear facilities: Guidelines and experience

    International Nuclear Information System (INIS)

    2002-01-01

    This report covers record keeping for the decommissioning of nuclear facilities. Nuclear facilities include large commercial facilities such as nuclear power plants or chemical nuclear facilities (e.g. for fabrication and reprocessing), but also include smaller facilities such as research reactors and medical, industrial and other research facilities. Special attention may be needed for these small facilities owing to factors such as the low priority given to decommissioning by research teams and the possibility of poorly recorded structural and operational changes. A focus on research reactors is also important because of their widespread distribution. Two IAEA TECDOCs address record keeping for radioactive waste management and disposal facilities, and therefore these areas are not covered in this report. The objective of this report is to provide information, experience and assistance on how to identify, update as needed and maintain records to assist in the decommissioning of nuclear facilities, including for the decommissioning plan. This report is intended to be useful to policy makers, regulators, owners, operators, decommissioning contractors and other interested parties. Record keeping is an integral part of overall QA or quality management programmes, and this is emphasized in this report. This report also indicates the possible consequences of not maintaining adequate records. This report describes the needs and the sources of the records for decommissioning (Section 3) and the process of identifying and selecting these records (Section 4). Section 5 considers the records from the decommissioning process itself and their retention, while Section 6 deals with QA, organization and responsibilities. The Records Management System (RMS) is dealt with in Section 7 and the management of new records in Section 8. A summary of observations is included in Section 9. The report is complemented by an appendix and annexes that describe case histories

  14. The National Analysis Facility at DESY - status and use cases by the participating experiments

    Science.gov (United States)

    Aplin, S.; Ehrenfeld, W.; Haupt, A.; Kemp, Y.; Langenbruch, C.; Leffhalm, K.; Lucaci-Timoce, A.; Stadie, H.

    2011-12-01

    The German National Analysis Facility (NAF) was set up at DESY, starting end of 2007 in the context of the Helmholtz Alliance "Physics at the Terascale". The NAF complements the DESY and the German Grid resources, and hence offers users from the German HEP institutes the best possible environment for data analysis. In the first part, the key aspects and components of the NAF are briefly presented with an emphasis on recent improvements. In the second part, the use cases of the three participating LHC experiments, ATLAS, CMS and LHCb, will be presented. Differences and commonalities in the usage of the NAF will be shown. Special emphasis will be placed on the usage of PROOF, whose usage on the NAF has been pioneered by CMS. It is now adapted by ATLAS. The third part will concentrate on how the NAF was used for detector optimisation studies in the preparation of one of the ILC Lol's (ILD 2009), as well as how CALICE uses the NAF for the analysis of their data taken in several test beam experiments performed for detector R & D. Finally, future developments of the NAF are presented.

  15. The National Analysis Facility at DESY - status and use cases by the participating experiments

    International Nuclear Information System (INIS)

    Aplin, S; Ehrenfeld, W; Haupt, A; Kemp, Y; Leffhalm, K; Lucaci-Timoce, A; Langenbruch, C; Stadie, H

    2011-01-01

    The German National Analysis Facility (NAF) was set up at DESY, starting end of 2007 in the context of the Helmholtz Alliance 'Physics at the Terascale'. The NAF complements the DESY and the German Grid resources, and hence offers users from the German HEP institutes the best possible environment for data analysis. In the first part, the key aspects and components of the NAF are briefly presented with an emphasis on recent improvements. In the second part, the use cases of the three participating LHC experiments, ATLAS, CMS and LHCb, will be presented. Differences and commonalities in the usage of the NAF will be shown. Special emphasis will be placed on the usage of PROOF, whose usage on the NAF has been pioneered by CMS. It is now adapted by ATLAS. The third part will concentrate on how the NAF was used for detector optimisation studies in the preparation of one of the ILC Lol's (ILD 2009), as well as how CALICE uses the NAF for the analysis of their data taken in several test beam experiments performed for detector R and D. Finally, future developments of the NAF are presented.

  16. Safety Research Experiment Facility Project. Conceptual design report. Volume III. Utilities

    International Nuclear Information System (INIS)

    1975-12-01

    The SAREF Electric Power System supplies and distributes power from the EBR-II switchgear for operation of all normal facilities on the site, from an on-site Experiment Diesel Generator for operation of all experiment related loads, and from an emergency engine generator and/or an uninterruptible power supply for operation of all essential and critical loads during a failure of both of the other two systems

  17. Improvement in performance and operational experience of 14 UD Pelletron accelerator facility, BARC-TIFR

    International Nuclear Information System (INIS)

    Bhagwat, P.V.

    2002-01-01

    14 UD Pelletron accelerator facility at Mumbai has been operational since 1989. The project MEHIA (Medium Energy Heavy Ion Accelerator) started in 1982 and was formally inaugurated on 30th December 1988. Since then the accelerator has been working round the clock. Improvement in accelerator performance and operational experience are described. (author)

  18. Opportunities for parity violating electron scattering experiments at the planned MESA facility

    Science.gov (United States)

    Aulenbacher, Kurt

    2011-11-01

    We suggest to start an accelerator physics project called the Mainz Energy recovering Superconducting Accelerator (MESA) as an extension to our experimental facilities. MESA may allow to introduce an innovative internal target regime based on the ERL principle. A second mode of operation will be to use an external polarized electron beam for parity violating experiments.

  19. 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

  20. Experiment of ablative Rayleigh-Taylor instability in a strongly non linear regime on the National Ignition Facility

    International Nuclear Information System (INIS)

    Casner, A.; Masse, L.; Liberatore, S.; Delorme, B.; Jacquet, L.; Loiseau, P.; Smalyuk, V. A.; Martinez, D.; Remington, B. A.

    2012-01-01

    As the control of the development of Rayleigh-Taylor-type hydrodynamic instabilities is crucial to achieve efficient implosions on the Laser Megajoule, and as the complexity of these instabilities requires an experimental validation of theoretical models and of the associated numerical simulations, the authors briefly present a proposition of experiments aimed at studying the strongly non linear Rayleigh-Taylor instability on the National Ignition Facility (NIF). This should allow a regime of competition between bubbles to be achieved for the first time in direct attack. They evoke the first experiment performed in March 2013

  1. 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

  2. Thermal-hydraulic Experiments for Advanced Physical Model Development

    International Nuclear Information System (INIS)

    Song, Chulhwa

    2012-04-01

    The improvement of prediction models is needed to enhance the safety analysis capability through experimental database of local phenomena. To improve the two-phase interfacial area transport model, the various experiments were carried out with local two-phase interfacial structure test facilities. 2 Χ 2 and 6 Χ 6 rod bundle test facilities were used for the experiment on the droplet behavior. The experiments on the droplet behavior inside a heated rod bundle geometry. The experiments used GIRLS and JICO and CFD analysis were carried out to comprehend the local condensation of steam jet, turbulent jet induced by condensation and the thermal mixing in a pool. In order to develop a model for key phenomena of newly adapted safety system, experiments for boiling inside a pool and condensation in horizontal channel have been performed. An experimental database of the CHF (Critical Heat Flux) and PDO (Post-dryout) was constructed. The mechanism of the heat transfer enhancement by surface modifications in nano-fluid was investigated in boiling mode and rapid quenching mode. The special measurement techniques were developed. They are Double-sensor optical void probe, Optic Rod, PIV technique and UBIM system

  3. 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

  4. 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

  5. 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.

  6. 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

  7. Operating experience with sodium valves in the TNO-sodium test facilities

    International Nuclear Information System (INIS)

    Gasselt, M.L.G. van

    1974-01-01

    The development of sodium components for the SNR-300 in Holland has reached the stage where full scale testing in sodium has almost been finished and construction is at its height. It is against this background that a review is given of the weaknesses in one area or the other of the commercially available types of sodium valves used in TNO's smaller test facilities at Apeldoorn and TNO's 50 MW sodium components test facility at Hengelo. (U.S.)

  8. Status and future program of reactor physics experiments in JAERI Critical facilities, FCA and TCA

    International Nuclear Information System (INIS)

    Okajima, Shigeaki; Osugi, Toshitaka; Nakajima, Ken; Suzaki, Takenori; Miyoshi, Yoshinori

    1999-01-01

    The critical facilities in JAERI, FCA (Fast Critical Assembly) and TCA (Tank-type Critical Assembly), have been used to provide integral data for evaluation of nuclear data as well as for development of various types of reactor since they went critical in 1960's. In this paper a review is presented on the experimental programs in both facilities. And the experimental programs in next 5 years are also shown. (author)

  9. 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

  10. Severe accident experiments on PLINIUS platform. Results of first experiments on COLIMA facility related to VVER-440. Presentation of planned VULCANO and KROTOS tests

    International Nuclear Information System (INIS)

    Piluso, P.; Boccaccio, E.; Bonnet, J.-M.; Journeau, C.; Fouquart, P.; Magallon, D.; Ivanov, I.; Mladenov, I.; Kalchev, S.; Grudev, P.; Alsmeyer, H.; Fluhrer, B.; Leskovar, M.

    2005-01-01

    In the hypothetical case of a nuclear reactor severe accident, the reactor core could melt and form a mixture of nuclear fuel (UO 2 + Fission Products), metallic or oxidized cladding + steel, called c orium , of highly refractory oxides (UO 2 , ZrO 2 ) and metallic or oxidized steel, that could eventually flow out of the vessel and mix with the substrate decomposition products (generally oxides such as SiO 2 , Al 2 O 3 , CaO, Fe 2 O 3 ). The French Atomic Energy Commission (CEA) has launched a R and D programme aimed at providing the tools for improving the mastering of severe accidents. It encompasses the development of models and codes, performance of experiments in simulant and prototypic materials and the analysis of international experiments. The experiments with prototypic corium (i.e. material containing depleted UO 2 ) are performed in the PLINIUS experimental platform at CEA Cadarache. It comprises the VULCANO facility for 50-100 kg tests (corium-material interactions, corium solidification etc.), the COLIMA facility for smaller scale (∼1 kg) experiments, the VITI facility for corium properties measurement and the KROTOS facility for corium-water interaction (a few kg). In the framework of the 5 th European Framework Programme, free trans-national access to these facilities has been offered to EU and Associated States researchers. For the first PLINIUS access, COLIMA experiments have been conducted with a Bulgarian Team (TU/SOFIA, BAS/INRNE and NPP/KOZLODUY). This series of tests was devoted to experimental studies on fission products release and corium behaviour in the late phase in a hypothetic case of severe accident in a PWR type VVER-440. The COLIMA experimental results are consistent with previous experiments on irradiated fuels (VERCORS, PHEBUS) with small differences for some fission products and show new results for the remaining corium. For the second visit, scientific users from FZK in Germany were selected to validate the COMET core

  11. Assessment of the MARS Code Using the Two-Phase Natural Circulation Experiments at a Core Catcher Test Facility

    Directory of Open Access Journals (Sweden)

    Dong Hun Lee

    2017-01-01

    Full Text Available A core catcher has been developed to maintain the integrity of nuclear reactor containment from molten corium during a severe accident. It uses a two-phase natural circulation for cooling molten corium. Flow in a typical core catcher is unique because (i it has an inclined cooling channel with downwards-facing heating surface, of which flow processes are not fully exploited, (ii it is usually exposed to a low-pressure condition, where phase change causes dramatic changes in the flow, and (iii the effects of a multidimensional flow are very large in the upper part of the core catcher. These features make computational analysis more difficult. In this study, the MARS code is assessed using the two-phase natural circulation experiments that had been conducted at the CE-PECS facility to verify the cooling performance of a core catcher. The code is a system-scale thermal-hydraulic (TH code and has a multidimensional TH component. The facility was modeled by using both one- and three-dimensional components. Six experiments at the facility were selected to investigate the parametric effects of heat flux, pressure, and form loss. The results show that MARS can predict the two-phase flow at the facility reasonably well. However, some limitations are obviously revealed.

  12. 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)

  13. 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)

  14. 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

  15. 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

  16. Nuclear techniques for the study of environmental pollution and control: experience and facilities at PINSTECH

    International Nuclear Information System (INIS)

    Rajput, M.U.; Butt, N.M.

    2001-01-01

    Environmental pollution is a worldwide problem. Developed countries have already gone in the clutches of pollution. Now the rapid industrialization and modernization process has also started in the developing countries. This is posing a serious threat to their own environment. One of the important factors in the pollution control measures is to investigate the levels of environmental pollution, from time to time, by effective and reliable methods. Nuclear techniques due to their high sensitivities play an important role in this regard. These techniques have the potential to determine the concentration of pollutants in trace level quantities (ppm and ppb) and for locating the possible pollution sources such as power plants, refineries, municipal waste, industries etc. Pakistan Institute of Nuclear Science and Technology (PINSTECH) has qualified and experienced scientists and has nearly all the major nuclear facilities that are needed for environmental research such as mass spectrometry, tracer techniques, neutron activation analysis (NAA), X-ray fluorescence spectrometry (XRFS), atomic absorption spectrometry (AAS), atomic emission spectrometry (AES), inductively coupled plasma-optical emission spectrometry (ICP-OES) etc. This paper discusses the importance of environmental pollution with a particular reference to the pollution aspects in Pakistan and the associated environmental research experience based on nuclear methods available at PINSTECH. 308 refs. (author)

  17. Safety Research Experiment Facility project. Conceptual design report. Volume IX. Experiment handling

    International Nuclear Information System (INIS)

    1975-01-01

    Information on the SAREF Reactor experiment handling system is presented concerning functions and design requirements, design description, operation, casualty events and recovery procedures, and maintenance

  18. Reactor physics experiments in PURNIMA sub critical facility coupled with 14 MeV neutron source

    International Nuclear Information System (INIS)

    Kumar, Rajeev; Degweker, S.B.; Patel, Tarun; Bishnoi, Saroj; Adhikari, P.S.

    2011-01-01

    Accelerator Driven Sub-critical Systems (ADSS) are attracting increasing worldwide attention due to their superior safety characteristics and their potential for burning actinide and fission product waste and energy production. A number of countries around the world have drawn up roadmaps/programs for development of ADSS. Indian interest in ADSS has an additional dimension, which is related to the planned utilization of our large thorium reserves for future nuclear energy generation. A programme for development of ADSS is taken up at the Bhabha Atomic Research Centre (BARC) in India. This includes R and D activities for high current proton accelerator development, target development and Reactor Physics studies. As part of the ADSS Reactor Physics research programme, a sub-critical facility is coming up in BARC which will be coupled with an existing D-D/D-T neutron generator. Two types of cores are planned. In one of these, the sub-critical reactor assembly consists of natural uranium moderated by high density polyethylene (HDP) and reflected by BeO. The other consists of natural uranium moderated by light water. The maximum neutron yield of the neutron source with tritium target is around 10 10 neutron per sec. Various reactor physics experiments like measurement of the source strength, neutron flux distribution, buckling estimation and sub-critical source multiplication are planned. Apart from this, measurement of the total fission power and neutron spectrum will also be carried out. Mainly activation detectors will be used in all in-core neutron flux measurement. Measurement of the degree of sub-criticality by various deterministic and noise methods is planned. Helium detectors with advanced data acquisition card will be used for the neutron noise experiments. Noise characteristics of ADSS are expected to be different from that of traditional reactors due to the non-Poisson statistical features of the source. A new theory incorporating these features has been

  19. Beam studies and experimental facility for the AWAKE experiment at CERN

    International Nuclear Information System (INIS)

    Bracco, Chiara; Gschwendtner, Edda; Petrenko, Alexey; Timko, Helga; Argyropoulos, Theodoros; Bartosik, Hannes; Bohl, Thomas; Esteban Müller, Juan; Goddard, Brennan; Meddahi, Malika; Pardons, Ans; Shaposhnikova, Elena; Velotti, Francesco M.; Vincke, Helmut

    2014-01-01

    A Proton Driven Plasma Wakefield Acceleration Experiment has been proposed as an approach to eventually accelerate an electron beam to the TeV energy range in a single plasma section. To verify this novel technique, a proof of principle R and D experiment, AWAKE, is planned at CERN using 400 GeV proton bunches from the SPS. An electron beam will be injected into the plasma cell to probe the accelerating wakefield. The AWAKE experiment will be installed in the CNGS facility profiting from existing infrastructure where only minor modifications need to be foreseen. The design of the experimental area and the proton and electron beam lines are shown. The achievable SPS proton bunch properties and their reproducibility have been measured and are presented. - Highlights: • A proton driven plasma wakefield experiment using the first time protons as drive beam is proposed. • The integration of AWAKE experiment, the proton, laser and electron beam line in an existing CERN facility is demonstrated. • The necessary modifications in the experimental facility are presented. • Proton beam optics and a new electron beam line are adapted to match with the required beam parameters. • Short high-intensity bunches were studied in the SPS to guide the design parameters of the AWAKE project

  20. The FELIX program of experiments and code development

    International Nuclear Information System (INIS)

    Turner, L.R.

    1983-01-01

    An experimental program and test bed called FELIX (Fusion Electromagnetic Induction Experiment) which is under construction at Argonne National Laboratory is described. The facility includes the following facilities; (a) a sizable constant field, analogous to a tokamak toroidal field or the confining field of a mirror reactor, (b) a pulsed field with a sizable rate of change, analogous to a pulsed poloidal field or to the changing field of a plasma disruption, perpendicular to the constant field, and (c) a sufficiently large volume to assure that large, complex test pieces can be tested, and that the forces, torques, currents, and field distortions which are developed are large enough to be measured accurately. The development of the necessary computer codes and the experimental program are examined. (U.K.)

  1. Czech interim spent fuel storage facility: operation experience, inspections and future plans

    International Nuclear Information System (INIS)

    Fajman, V.; Bartak, L.; Coufal, J.; Brzobohaty, K.; Kuba, S.

    1999-01-01

    The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

  2. Physics issues related to the confinement of ICF experiments in the US National Ignition Facility

    International Nuclear Information System (INIS)

    Tobin, M.; Anderson, A.; Latkowski, J.

    1995-04-01

    ICF experiments planned for the proposed US National Ignition Facility (NIF) will produce emissions of neutrons, x rays, debris, and shrapnel. The NIF Target Area (TA) must acceptably confine these emissions and respond to their effects to allow an efficient rate of experiments, from 600 to possibly 1500 per year, and minimal down time for maintenance. Detailed computer code predictions of emissions are necessary to study their effects and impacts on Target Area operations. Preliminary results show that the rate of debris shield transmission loss (and subsequent periodicity of change-out) due to ablated material deposition is acceptable, neutron effects on optics are manageable, and preliminary safety analyses show a facility rating of low hazard, non-nuclear. Therefore, NIF Target Area design features such as fused silica debris shields, refractory first wall coating, and concrete shielding are effective solutions to confinement of ICF experiment emissions

  3. Summary of 2016 Light Microscopy Module (LMM) Physical Science Experiments on ISS. Update of LMM Science Experiments and Facility Capabilities

    Science.gov (United States)

    Sicker, Ronald J.; Meyer, William V.; Foster, William M.; Fletcher, William A.; Williams, Stuart J.; Lee, Chang-Soo

    2016-01-01

    This presentation will feature a series of short, entertaining, and informative videos that describe the current status and science support for the Light Microscopy Module (LMM) facility on the International Space Station. These interviews will focus on current experiments and provide an overview of future capabilities. The recently completed experiments include nano-particle haloing, 3-D self-assembly with Janus particles and a model system for nano-particle drug delivery. The videos will share perspectives from the scientists, engineers, and managers working with the NASA Light Microscopy program.

  4. Status report of the low frequency facility experiment, Virgo R and D

    Energy Technology Data Exchange (ETDEWEB)

    Di Virgilio, A.; Ballardin, G.; Braccini, S.; Bradaschia, C.; Calamai, G.; Casciano, C.; Cavalieri, R.; Cecchi, R.; Cella, G.; Chen, Sheng-Jui; Cuoco, E.; Dattilo, V.; Dominici, P.; Fabbroni, L.; Fazzi, M.; Frasca, S.; Ferrante, I.; Fidecaro, F.; Frasconi, F.; Gennaro, G.; Giazotto, A.; Guidi, G.; Holloway, L.; La Penna, P.; Lomtadze, T.; Losurdo, G.; Majorana, E.; Martelli, F.; Mazzoni, M.; Nenci, F.; Ni, Wei-Tou; Lelli, F.; Paoletti, F.; Pasqualetti, A.; Passaquieti, R.; Passuello, D.; Perciballi, M.; Poggiani, R.; Porzio, A.; Puppo, P.; Raffaelli, F.; Rapagnani, P.; Ricci, F.; Ricciardi, I.; Solimeno, S.; Stanga, R.; Taddei, R.; Vetrano, F.; Vicere, A.; Zhang, Z

    2003-11-10

    The low frequency facility, a Virgo R and D experiment, is composed by a Fabry-Perot cavity attached and controlled by the Virgo suspension; the goal is to measure the thermal noise of the apparatus above 10 Hz, with a displacement sensitivity as high as 10{sup -18} m/{radical}Hz. Since September 2001 the apparatus, located inside the INFN-Pisa experimental area, has been completely built and put into operation. Vacuum facilities and the control loops have been set up. Transfer functions, necessary to control the cavity, absolute test mass displacement and the first demonstration of the cavity locking are reported.

  5. 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.)

  6. 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)

  7. 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

  8. 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

  9. 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

  10. 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.

  11. Performance of the first Japanese large-scale facility for radon inhalation experiments with small animals

    International Nuclear Information System (INIS)

    Ishimori, Y.; Mitsunobu, F.; Yamaoka, K.; Tanaka, H.; Kataoka, T.; Sakoda, A.

    2011-01-01

    A radon test facility for small animals was developed in order to increase the statistical validity of differences of the biological response in various radon environments. This paper illustrates the performances of that facility, the first large-scale facility of its kind in Japan. The facility has a capability to conduct approximately 150 mouse-scale tests at the same time. The apparatus for exposing small animals to radon has six animal chamber groups with five independent cages each. Different radon concentrations in each animal chamber group are available. Because the first target of this study is to examine the in vivo behaviour of radon and its effects, the major functions to control radon and to eliminate thoron were examined experimentally. Additionally, radon progeny concentrations and their particle size distributions in the cages were also examined experimentally to be considered in future projects. (authors)

  12. 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.

  13. Development of portal Web pages for the LHD experiment

    International Nuclear Information System (INIS)

    Emoto, Masahiko; Funaba, Hisamichi; Nakanishi, Hideya; Iwata, Chie; Yoshida, Masanori; Nagayama, Yoshio

    2011-01-01

    Because the LHD project has been operating with the cooperation of many institutes in Japan, the remote participation facilities play an important role. Therefore, NIFS has been introducing these facilities to its remote participants. Because the authors regard Web services as essential tools for the current Internet communication, Web services for remote participation have been developed. However, because these services are dispersed among several servers in NIFS, users cannot find the required services easily. Therefore, the authors developed a portal Web server to list the existing and new Web services for the LHD experiment. The server provides services such as summary graph, plasma movie of the last plasma discharge, daily experiment logs, and daily experimental schedules. One of the most important information from these services is the summary graph. Usually, the plasma discharges of the LHD experiment are executed every three minutes. Between the discharges, the summary graph of the last plasma discharge is displayed on the front screen in the control room soon after the discharge is complete. The graph is useful in evaluating the last discharge, which is important information for determining the subsequent experiment schedule. Therefore, it is required to display the summary graph, which plots more than 10 data diagnostics, as soon as possible. On the other hand, the data-appearance time varies from one diagnostic to another. To display the graph faster, the new system retrieves the data asynchronously; several data retrieval processes work simultaneously, and the system plots the data all at once. (author)

  14. Experiments, conceptual design, preliminary cost estimates and schedules for an underground research facility

    International Nuclear Information System (INIS)

    Korbin, G.; Wollenberg, H.; Wilson, C.; Strisower, B.; Chan, T.; Wedge, D.

    1981-09-01

    Plans for an underground research facility are presented, incorporating techniques to assess the hydrological and thermomechanical response of a rock mass to the introduction and long-term isolation of radioactive waste, and to assess the effects of excavation on the hydrologic integrity of a repository and its subsequent backfill, plugging, and sealing. The project is designed to utilize existing mine or civil works for access to experimental areas and is estimated to last 8 years at a total cost for contruction and operation of $39.0 million (1981 dollars). Performing the same experiments in an existing underground research facility would reduce the duration to 7-1/2 years and cost $27.7 million as a lower-bound estimate. These preliminary plans and estimates should be revised after specific sites are identified which would accommodate the facility

  15. Experiences of registered nurses as managers and leaders in residential aged care facilities: a systematic review.

    Science.gov (United States)

    Dwyer, Drew

    2011-12-01

    The phenomenon of an ageing population is being experienced globally, as countries struggle to change and improve residential models of care and provide services to the elderly. The role of the registered nurse (RN) is considered crucial to the clinical governance and management of care given. To date, however, no systematic review has examined the RN's experience in leadership and management. The objective of this review is to critically appraise, synthesise and present best available evidence on the experiences of RNs as clinical leaders and managers in residential aged care facilities. This review considered qualitative research papers that addressed the experiences of RNs as clinical leaders and managers in residential aged care facilities. Participants of interest were RNs, nurse leaders, nurses holding registration and or regulation under a board of nursing, nurses working in residential aged care and long-term care facilities. The diversity and use of language to describe nurses' roles and models of care for the elderly care environment were considered in the review. The search strategy sought to find both published studies and papers, limited to the English language and published between January 1997 and February 2011. An initial limited search was done in Medical Literature Analysis and Retrieval System Online (MEDLINE) and Cumulative Index to Nursing and Allied Health Literature databases to identify the key words contained in the title or abstract and index terms used to describe the relevant terms in the article. A second extensive search was undertaken and extended to other relevant databases using all identified keywords and index terms. The third step involved searching reference lists and bibliographies of chosen articles for additional studies. Each paper was assessed by two independent reviewers for methodological quality prior to inclusion in the review using an appropriate critical appraisal instrument from the System for the Unified Management

  16. 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.

  17. 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)

  18. Decommissioning of nuclear facilities in Europe and the experience of TUV SUD

    International Nuclear Information System (INIS)

    Hummel, Lothar; Kim, Duill; Ha, Taegun; Yang, Kyunghwa

    2012-01-01

    Many commercial nuclear facilities of the first generation will be taken out of operation in the near future. As of January 2012, total 19 prototype and commercial nuclear reactors have been decommissioned or are under dismantling in Germany. Most of decommissioning projects were successfully performed and a great deal of experience has been accumulated. Selecting a decommissioning strategy is a very important step at the beginning of the decision making process. According to IAEA requirements immediate dismantling is chosen as a preferred option in many countries today. It is associated with less uncertainty, positive political and social effect, and it can make use of existing operational experience and know-how. The availability of funds and final repository is of high importance for a decommissioning strategy selection. The time frame for the dismantling of nuclear facilities depends on the type, size and complexity of the individual project. TUV SUD, which is supervising most of nuclear power plants in Germany, has accumulated lots of experience by taking parts in decommissioning projects. It direct dismantling is chosen, actual light water reactor in Germany decommissioned to green field in approx. 10 years. The activities of TUV SUD cover from establishing the decommissioning concept to the clearance of the sites. This provides an overview of decommissioning projects of nuclear facilities in Europe, including a detail illustration of the German situation. Finally, some recommendations are suggested for the first decommissioning project based on the lessons and experiences derived from many decommissioning works in Europe

  19. PMK-2 the Hungarian integral type test facility. Documentations, publications and archivations of experiments

    International Nuclear Information System (INIS)

    Perneczky, L.; Guba, A.; Ezsoel, G.; Toth, I.; Szabados, L.

    2002-01-01

    The PMK-2 experimental facility at the KFKI-AEKI, Budapest, is a full pressure, scaled down model of the primary and partly the secondary circuit of the Paks NPP, which is equipped with four VVER-440/213-type reactors. Since the start-up of the facility altogether 48 experiments have been performed for groups of transients as follows: one- and two-phase natural circulation, loss of coolant accidents, special plant transients and experiments in support of accident management procedures. The results have been used for the validation of thermal-hydraulic system codes for VVER applications. Following the experiments a detailed documentation and archiving activity - using an optimised data storage - was required to preserve the essential information and to assure these for a widely utilisation for the international nuclear community. In the publication list related to the facility and the experiments for the moment altogether 280 items - documents, articles in periodicals, papers in proceedings and research reports - in six languages were collected. The paper gives an overview on this activity including the participation in the EU CERTA-TN programme, where AEKI introduced representative databases of two PMK-2 tests in the STRESA Network.(author)

  20. 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…

  1. 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

  2. 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.

  3. Problems and experience of ensuring nuclear safety in NPP spent fuel storage facilities in Russia

    International Nuclear Information System (INIS)

    Vnukov, Victor S.; Ryazanov, Boris G.

    2003-01-01

    The amount of Nuclear Power Plant (NPP) spent fuel in special storage facilities of Russia runs to more than 15000 tons and the annual growth is equal to about 850 tons. The storage facilities for spent nuclear fuel from the main nuclear reactors of Russia (RBMK-1000, VVER-1000, BN-600, EGP-6) were designed in the 60s - 70s. In the last years when the concept of closed fuel cycle and safety requirements had changed, the need was generated to have the nuclear storage facilities more crowded. First of all it is due to the necessity to increase the storage capacity because the RBMK-1000, VVER-1000, EGP-6 fuel is not reprocessed. So there comes the need for the facilities of a bigger capacity which meet the current safety requirements. The paper presents the results of studies of the most important nuclear safety issues, in particular: development of regulatory requirements; analysis of design-basis and beyond-the design-basis accidents (DBA and BDBA); computation code development and verification; justification of nuclear safety when water density goes down; the use of burn-up fraction values; the necessity and possibility to experimentally study the storage facility subcriticality; development of storage norms and rules for new types of fuel assemblies with mixed fuel and burnable poison. (author)

  4. 2010 Criticality Accident Alarm System Benchmark Experiments At The CEA Valduc SILENE Facility

    International Nuclear Information System (INIS)

    Miller, Thomas Martin; Dunn, Michael E.; Wagner, John C.; McMahan, Kimberly L.; Authier, Nicolas; Jacquet, Xavier; Rousseau, Guillaume; Wolff, Herve; Piot, Jerome; Savanier, Laurence; Baclet, Nathalie; Lee, Yi-kang; Masse, Veronique; Trama, Jean-Christophe; Gagnier, Emmanuel; Naury, Sylvie; Lenain, Richard; Hunter, Richard; Kim, Soon; Dulik, George Michael; Reynolds, Kevin H.

    2011-01-01

    Several experiments were performed at the CEA Valduc SILENE reactor facility, which are intended to be published as evaluated benchmark experiments in the ICSBEP Handbook. These evaluated benchmarks will be useful for the verification and validation of radiation transport codes and evaluated nuclear data, particularly those that are used in the analysis of CAASs. During these experiments SILENE was operated in pulsed mode in order to be representative of a criticality accident, which is rare among shielding benchmarks. Measurements of the neutron flux were made with neutron activation foils and measurements of photon doses were made with TLDs. Also unique to these experiments was the presence of several detectors used in actual CAASs, which allowed for the observation of their behavior during an actual critical pulse. This paper presents the preliminary measurement data currently available from these experiments. Also presented are comparisons of preliminary computational results with Scale and TRIPOLI-4 to the preliminary measurement data.

  5. Does identity shape leadership and management practice? Experiences of PHC facility managers in Cape Town, South Africa.

    Science.gov (United States)

    Daire, Judith; Gilson, Lucy

    2014-09-01

    In South Africa, as elsewhere, Primary Health Care (PHC) facilities are managed by professional nurses. Little is known about the dimensions and challenges of their job, or what influences their managerial practice. Drawing on leadership and organizational theory, this study explored what the job of being a PHC manager entails, and what factors influence their managerial practice. We specifically considered whether the appointment of professional nurses as facility managers leads to an identity transition, from nurse to manager. The overall intention was to generate ideas about how to support leadership development among PHC facility managers. Adopting case study methodology, the primary researcher facilitated in-depth discussions (about their personal history and managerial experiences) with eight participating facility managers from one geographical area. Other data were collected through in-depth interviews with key informants, document review and researcher field notes/journaling. Analysis involved data triangulation, respondent and peer review and cross-case analysis. The experiences show that the PHC facility manager's job is dominated by a range of tasks and procedures focused on clinical service management, but is expected to encompass action to address the population and public health needs of the surrounding community. Managing with and through others, and in a complex system, requiring self-management, are critical aspects of the job. A range of personal, professional and contextual factors influence managerial practice, including professional identity. The current largely facility-focused management practice reflects the strong nursing identity of managers and broader organizational influences. However, three of the eight managers appear to self-identify an emerging leadership identity and demonstrate related managerial practices. Nonetheless, there is currently limited support for an identity transition towards leadership in this context. Better

  6. Life science experiments performed in space in the ISS/Kibo facility and future research plans.

    Science.gov (United States)

    Ohnishi, Takeo

    2016-08-01

    Over the past several years, current techniques in molecular biology have been used to perform experiments in space, focusing on the nature and effects of space radiation. In the Japanese 'Kibo' facility in the International Space Station (ISS), the Japan Aerospace Exploration Agency (JAXA) has performed five life science experiments since 2009, and two additional experiments are currently in progress. The first life science experiment in space was the 'Rad Gene' project, which utilized two human cultured lymphoblastoid cell lines containing a mutated P53 : gene (m P53 : ) and a parental wild-type P53 : gene (wt P53 : ) respectively. Four parameters were examined: (i) detecting space radiation-induced DSBs by observing γH2AX foci; (ii) observing P53 : -dependent gene expression during space flight; (iii) observing P53 : -dependent gene expression after space flight; and (iv) observing the adaptive response in the two cell lines containing the mutated and wild type P53 : genes after exposure to space radiation. These observations were completed and have been reported, and this paper is a review of these experiments. In addition, recent new information from space-based experiments involving radiation biology is presented here. These experiments involve human cultured cells, silkworm eggs, mouse embryonic stem cells and mouse eggs in various experiments designed by other principal investigators in the ISS/Kibo. The progress of Japanese science groups involved in these space experiments together with JAXA are also discussed here. The Japanese Society for Biological Sciences in Space (JSBSS), the Utilization Committee of Space Environment Science (UCSES) and the Science Council of Japan (ACJ) have supported these new projects and new experimental facilities in ISS/Kibo. Currently, these organizations are proposing new experiments for the ISS through 2024. © The Author 2016. Published by Oxford University Press on behalf of The Japan Radiation Research Society and

  7. Life science experiments performed in space in the ISS/Kibo facility and future research plans

    International Nuclear Information System (INIS)

    Ohnishi, Takeo

    2016-01-01

    Over the past several years, current techniques in molecular biology have been used to perform experiments in space, focusing on the nature and effects of space radiation. In the Japanese ‘Kibo’ facility in the International Space Station (ISS), the Japan Aerospace Exploration Agency (JAXA) has performed five life science experiments since 2009, and two additional experiments are currently in progress. The first life science experiment in space was the ‘Rad Gene’ project, which utilized two human cultured lymphoblastoid cell lines containing a mutated p53 gene (mp53) and a parental wild-type p53 gene (wtp53) respectively. Four parameters were examined: (i) detecting space radiation–induced DSBs by observing γH2AX foci; (ii) observing p53-dependent gene expression during space flight; (iii) observing p53-dependent gene expression after space flight; and (iv) observing the adaptive response in the two cell lines containing the mutated and wild type p53 genes after exposure to space radiation. These observations were completed and have been reported, and this paper is a review of these experiments. In addition, recent new information from space-based experiments involving radiation biology is presented here. These experiments involve human cultured cells, silkworm eggs, mouse embryonic stem cells and mouse eggs in various experiments designed by other principal investigators in the ISS/Kibo. The progress of Japanese science groups involved in these space experiments together with JAXA are also discussed here. The Japanese Society for Biological Sciences in Space (JSBSS), the Utilization Committee of Space Environment Science (UCSES) and the Science Council of Japan (ACJ) have supported these new projects and new experimental facilities in ISS/Kibo. Currently, these organizations are proposing new experiments for the ISS through 2024

  8. 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)

  9. The Non-Proliferation Experiment recorded at the Pinedale Seismic Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Carr, D.B. [Sandia National Laboratories, Albuquerque, NM (United States)

    1994-12-31

    The Non-Proliferation Experiment was recorded by five different seismic stations operated by Sandia National Laboratories at the Pinedale Seismic Research Facility, approximately 7.6{degrees} from the Nevada Test Site. Two stations are different versions of the Deployable Seismic Verification System developed by the Department of Energy to provide seismic data to verify compliance with a Comprehensive Test Ban Treaty. Vault and borehole versions of the Designated Seismic Stations also recorded the event. The final station is test instrumentation located at depths of 10, 40 and 1200 feet. Although the event is seen clearly at all the stations, there are variations in the raw data due to the different bandwidths and depths of deployment. One Deployable Seismic Verification System has been operating at Pinedale for over three years and in that time recorded 14 nuclear explosions and 4 earthquakes from the Nevada Test Site, along with numerous other western U.S. earthquakes. Several discriminants based on the work by Taylor et al. (1989) have been applied to this data. First the discriminants were tested by comparing the explosions only to the 4 earthquakes located on the Test Site. Only one discriminant, log(L{sub g}/P{sub g}), did not show clear separation between the earthquakes and nuclear explosions. When other western U.S. events are included, only the M{sub b} vs. M{sub s} discriminant separated the event. In all cases where discrimination was possible, the Non-Proliferation Experiment was indistinguishable from a nuclear explosion.

  10. 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)

  11. 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)

  12. 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.

  13. 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.

  14. Tokamak Physics Experiment (TPX) power supply design and development

    International Nuclear Information System (INIS)

    Neumeyer, C.; Bronner, G.; Lu, E.; Ramakrishnan, S.

    1995-01-01

    The Tokamak Physics Experiment (TPX) is an advanced tokamak project aimed at the production of quasi-steady state plasmas with advanced shape, heating, and particle control. TPX is to be built at the Princeton Plasma Physics Laboratory (PPPL) using many of the facilities from the Tokamak Fusion Test Reactor (TFTR). TPX will be the first tokamak to utilize superconducting (SC) magnets in both the toroidal field (TF) and poloidal field (PF) systems. This new feature requires a departure from the traditional tokamak power supply schemes. This paper describes the plan for the adaptation of the PPPL/FTR power system facilities to supply TPX. Five major areas are addressed, namely the AC power system, the TF, PF and Fast Plasma Position Control (FPPC) power supplies, and quench protection for the TF and PF systems. Special emphasis is placed on the development of new power supply and protection schemes

  15. Calibration of the SphinX experiment at the XACT facility in Palermo

    Science.gov (United States)

    Collura, A.; Barbera, M.; Varisco, S.; Calderone, G.; Reale, F.; Gburek, S.; Kowalinski, M.; Sylwester, J.; Siarkowski, M.; Bakala, J.; Podgorski, P.; Trzebinski, W.; Plocieniak, S.; Kordylewski, Z.

    2008-07-01

    Three of the four detectors of the SphinX experiment to be flown on the Russian mission Coronas-Photon have been measured at the XACT Facility of the Palermo Observatory at several wavelengths in the soft X-ray band. We describe the instrumental set-up and report some measurements. The analysis work to obtain the final calibration is still in progress.

  16. Experiences of a newspaper journalist with the official information policy of nuclear facilities

    International Nuclear Information System (INIS)

    Koppelstaetter, H.

    1988-01-01

    One of the biggest problems for a newspaper journalist is to communicate highly specialist statements about technical matters to the reader in comprehensible form. This calls for total confidence in the information at the nuclear facility, i.e. the press spokesman. A number of impressions of experiences as a newspaper editor attempting to obtain information following an accident, i.e. the extent and background of Chernobyl, are outlined. (DG)

  17. Nurses experiences with deaf patient and recommendations for an effective communication with deaf in medical facility

    OpenAIRE

    Boukalová, Naděžda

    2010-01-01

    This bachelor thesis whose name is Nurses experiences with deaf patient and recommendations for an effective communication with deaf in medical facility was conceived as pilot research. This thesis consists of two parts, theoretical and experimental. Theoretical part has several chapters, which deal with anatomy of ear, physiology of hearing, deaf in Czech Republic and communication. The last part of this chapter describes certain situations, where is possible to meet the deaf at medical faci...

  18. A facility for liquid-phase radiation experiments on heavy ion beams

    Energy Technology Data Exchange (ETDEWEB)

    Stuglik, Z; Zvara, I; Yakushev, A B; Timokhin, S N [Flerov Lab. of Nuclear Reactions, Dubna (Russian Federation). Joint Inst. for Nuclear Research

    1994-05-01

    The facility for liquid-phase radiation experiments installed on the beam line of the U-400 cyclotron in the Flerov Laboratory of Nuclear Reactions, JINR, Dubna, is described. The accelerator provides intermediate energy (some 10 MeV/nucleon) beams of ions ranging from Li to Xe. Preliminary results on the radiolysis of the Fricke solution and malachite green in ethanol by {sup 11}B, {sup 24}Mg and {sup 40}Ca ions are presented. (author).

  19. Safety evaluation of the NSRR facility relevant to the modification for improved pulse operation and preirradiated fuel experiments

    International Nuclear Information System (INIS)

    Inabe, Teruo; Terakado, Yoshibumi; Tanzawa, Sadamitsu; Katagiri, Hiroshi; Kobayashi, Hideo

    1988-11-01

    The Nuclear Safety Research Reactor (NSRR) is a pulse reactor for the inpile experiments to study the fuel behavior under reactivity initiated accident conditions. The present operation modes of the NSRR consist of the steady state operation up to 300 kW and the natural pulse operation in which a sharp pulsed power is generated from substantially zero power level. In addition to these, two new modes of shaped pulse operation and combined pulse operation will be conducted in the near future as the improved pulse operations. A transient power up to 10 MW will be generated in the shaped pulse operation, and a combination of a transient power up to 10 MW and a sharp pulsed power will be generated in the combined pulse operation. Furthermore, preirradiated fuel rods will be employed in the future experiments whereas the present experiments are confined to the test specimens of unirradiated fuel rods. To provide for these programs, the fundamental design works relevant to the modification of the reactor facility including the reactor instrumentation and control systems and experimental provision were developed. The reactor safety evaluation is prerequisite for confirming the propriety of the fundamental design of the reactor facility from the safety point of view. The safety evaluation was therefore conducted postulating such events that would bring about abnormal conditions in the reactor facility. As a result of the safety evaluation, it has been confirmed as to the NSRR facility after modification that the anticipated transients, the postulated accidents, the major accident and the hypothetical accident do not result respectively in any serious safety problem and that the fundamental design principles and the reactor siting are adequate and acceptable. (author)

  20. 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.

  1. 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.

  2. 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.

  3. Set of thermal neutron-scattering experiments for the Weapons Neutron Research Facility

    International Nuclear Information System (INIS)

    Brugger, R.M.

    1975-12-01

    Six classes of experiments form the base of a program of thermal neutron scattering at the Weapons Neutron Research (WNR) Facility. Three classes are to determine the average microscopic positions of atoms in materials and three are to determine the microscopic vibrations of these atoms. The first three classes concern (a) powder sample neutron diffraction, (b) small angle scattering, and (c) single crystal Laue diffraction. The second three concern (d) small kappa inelastic scattering, (e) scattering surface phonon measurements, and (f) line widths. An instrument to couple with the WNR pulsed source is briefly outlined for each experiment

  4. 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

  5. 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

  6. 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

    and two bilateral servo-manipulators and ITV (Industrial Television) systems for monitoring are installed for Maintenance and also Operation in the cell. These cranes and manipulators are mounted on the bridge to ensure the wide range of operations in the cell and also designed to be remotely maintained themselves by each other. In case of K-facility (active tests stated in 2007) the operating experiences at TVF were reflected to make some improvements on its remote handling system in order to ensure the availability and reduce the cost. There adopted the unilateral servo-manipulator and the auxiliary hoist with remote operation support system, the rack module design for periodically replaced components, and the direct contact maintenance for the in cell cranes and manipulators in the shielded parking space. The glass melter in the vitrification process is designed to be replaced every 5 years, so the remote replacement and dismantling technology for the spent melters have been also developed and installed in TVF and K-facility for 40 years’ operation. This paper describes our development experiences on the design, construction, operation, and maintenance of the remote handling systems in nuclear fuel cycle facilities in Japan. (author)

  7. A Dream Experiment in Development Economics

    Science.gov (United States)

    Singh, Prakarsh; Russo, Alexa

    2013-01-01

    In this article, the authors discuss a unique project carried out by 13 teams of four students each in the undergraduate Development Economics class during the 2012 spring semester at a private liberal arts college. The goal of the "Dream Experiment" was to think of an idea that promotes development, employs concepts from development…

  8. The Makerspace Experience and Teacher Professional Development

    Science.gov (United States)

    Paganelli, Andrea; Cribbs, Jennifer D.; Huang, Xiaoxia; Pereira, Nielsen; Huss, Jeanine; Chandler, Wanda; Paganelli, Anthony

    2017-01-01

    This study explored the use of makerspaces as a professional development activity when examined through the analysis of qualitative data reflecting participant experience. The data were gathered in the course of a professional development opportunity at a university during a conference held on campus. The researchers wanted to select an innovative…

  9. Regional Development Planning in Ethiopia: Past Experience ...

    African Journals Online (AJOL)

    Regional Development Planning in Ethiopia: Past Experience, Current Initiatives and Future Prospects. ... Eastern Africa Social Science Research Review ... The main contention of the paper is that in the past, regional development, in line with the functional integration approach, was considered a national project.

  10. Lessons from early experience in reactor development

    International Nuclear Information System (INIS)

    Allen, W.

    1976-09-01

    This paper deals with several issues in U.S. reactor development and demonstration experience. The focus is on the period between 1946 and 1963 during which the Atomic Energy Commission (AEC) guided early reactor research and development (R and D) and conducted the Power Reactor Demonstration Program

  11. Democracy and development: the Nigerian experience | Ebohon ...

    African Journals Online (AJOL)

    The conventional notions on the relationship between democracy and development are that democracy accelerates development. Based on the Nigeria experience, this paper argues that both democracy and authoritarianism are social system based political ideologies that derives their character from the wider society, ...

  12. 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)

  13. 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.

  14. 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.

  15. 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

  16. LEU-HTR critical experiment program for the PROTEUS facility in Switzerland

    International Nuclear Information System (INIS)

    Brogli, R.; Bucher, K.H.; Chawla, R.; Foskolos, K.; Luchsinger, H.; Mathews, D.; Sarlos, G.; Seiler, R.

    1990-01-01

    New critical experiments in the framework of an IAEA Coordinated Research Program on 'Validation of Safety Related Reactor Physics Calculations for Low Enriched HTRs' are planned at the PSI PROTEUS facility. The experiments are designed to supplement the experimental data base and reduce the design and licensing uncertainties for small- and medium-sized helium-cooled reactors using low-enriched uranium (LEU) and graphite high temperature fuel. The main objectives of the new experiments are to provide first-of-a-kind high quality experimental data on: 1) The criticality of simple, easy to interpret, single core region LEU HTR systems for several moderator-to-fuel ratios and several lattice geometries; 2) the changes in reactivity, neutron balance components and control rod effectiveness caused by water ingress into this type of reactor, and 3) the effects of the boron and/or hafnium absorbers that are used to modify the reactivity and the power distributions in typical HTR systems. Work on the design and licensing of the modified PROTEUS critical facility is now in progress with the HTR experiments scheduled to begin early in 1991. Several international partners will be involved in the planning, execution and analysis of these experiments in order to insure that they are relevant and cost effective with respect to the various gas cooled reactor national programs. (author)

  17. LEU-HTR critical experiment program for the PROTEUS facility in Switzerland

    Energy Technology Data Exchange (ETDEWEB)

    Brogli, R; Bucher, K H; Chawla, R; Foskolos, K; Luchsinger, H; Mathews, D; Sarlos, G; Seiler, R [Paul Scherrer Institute, Laboratory for Reactor Physics and System Technology Wuerenlingen and Villigen, Villigen PSI (Switzerland)

    1990-07-01

    New critical experiments in the framework of an IAEA Coordinated Research Program on 'Validation of Safety Related Reactor Physics Calculations for Low Enriched HTRs' are planned at the PSI PROTEUS facility. The experiments are designed to supplement the experimental data base and reduce the design and licensing uncertainties for small- and medium-sized helium-cooled reactors using low-enriched uranium (LEU) and graphite high temperature fuel. The main objectives of the new experiments are to provide first-of-a-kind high quality experimental data on: 1) The criticality of simple, easy to interpret, single core region LEU HTR systems for several moderator-to-fuel ratios and several lattice geometries; 2) the changes in reactivity, neutron balance components and control rod effectiveness caused by water ingress into this type of reactor, and 3) the effects of the boron and/or hafnium absorbers that are used to modify the reactivity and the power distributions in typical HTR systems. Work on the design and licensing of the modified PROTEUS critical facility is now in progress with the HTR experiments scheduled to begin early in 1991. Several international partners will be involved in the planning, execution and analysis of these experiments in order to insure that they are relevant and cost effective with respect to the various gas cooled reactor national programs. (author)

  18. Overview of DAQ developments for the CBM experiment

    Energy Technology Data Exchange (ETDEWEB)

    Emschermann, David [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH (Germany); Collaboration: CBM-Collaboration

    2015-07-01

    The Compressed Baryonic Matter experiment (CBM) at the future Facility for Antiproton and Ion Research (FAIR) is a a fixed-target setup operating at very high interaction rates up to 10 MHz. The high rate capability can be achieved with fast and radiation hard detectors equipped with free-streaming readout electronics. A high-speed data acquisition (DAQ) system will forward data volumes of up to 1 TB/s from the CBM cave to the first level event selector (FLES), located 400 m apart. This presentation showcases recent developments of DAQ components for CBM. We highlight the anticipated DAQ setup for beam tests scheduled for the end of 2015.

  19. 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)

  20. Natural circulation in a VVER reactor geometry: Experiments with the PACTEL facility and Cathare simulations

    Energy Technology Data Exchange (ETDEWEB)

    Raussi, P.; Kainulainen, S. [Lappeenranta Univ. of Technology, Lappeenranta (Finland); Kouhia, J. [VTT Energy, Lappeenranta (Finland)

    1995-09-01

    There are some 40 reactors based on the VVER design in use. Database available for computer code assessment for VVER reactors is rather limited. Experiments were conducted to study natural circulation behaviour in the PACTEL facility, a medium-scale integral test loop patterned after VVER pressurized water reactors. Flow behaviour over a range of coolant inventories was studied with a small-break experiment. In the small-break experiments, flow stagnation and system repressurization were observed when the water level in the upper plenum fell below the entrances to the hot legs. The cause was attributed to the hot leg loop seals, which are a unique feature of the VVER geometry. At low primary inventories, core cooling was achieved through the boiler-condenser mode. The experiment was simulated using French thermalhydraulic system code CATHARE.

  1. Results of 15 years experiments in the PMK-2 integral-type facility for VVERs

    Energy Technology Data Exchange (ETDEWEB)

    Szabados, L.; Ezsoel, G.; Perneczky, L. [KFKI Atomic Energy Research Institute, Budapest (Hungary)

    2001-07-01

    Due to the specific features of the VVER-440/213-type reactors the transient behaviour of such a reactor system is different from the usual PWR system behaviour. To provide an experimental database for the transient behaviour of VVER systems the PMK integral-type facility, the scaled down model of the Paks NPP was designed and constructed in the early 1980's. Since the start-up of the facility 48 experiments have been performed. It was confirmed through the experiments that the facility is a suitable tool for the computer code validation experiments and to the identification of basic thermal-hydraulic phenomena occurring during plant accidents. High international interest was shown by the four Standard Problem Exercises of the IAEA and by the projects financed by the EU-PHARE. A wide range of small- and medium-size LOCA sequences have been studied to know the performance and effectiveness of ECC systems and to evaluate the thermal-hydraulic safety of the core. Extensive studies have been performed to investigate the one- and two-phase natural circulation, the effect of disturbances coming from the secondary circuit and to validate the effectiveness of accident management measures like bleed and feed. The VVER-specific case, the opening of the SG collector cover was also extensively investigated. Examples given in the report show a few results of experiments and the results of calculation analyses performed for validation purposes of codes like RELAP5, ATHLET and CATHARE. There are some other white spots in Cross Reference Matrices for VVER reactors and, therefore, further experiments are planned to perform tests primarily in further support of accident management measures at low power states of plants to facilitate the improved safety management of VVER-440-type reactors. (authors)

  2. Results of 15 years experiments in the PMK-2 integral-type facility for VVERs

    International Nuclear Information System (INIS)

    Szabados, L.; Ezsoel, G.; Perneczky, L.

    2001-01-01

    Due to the specific features of the VVER-440/213-type reactors the transient behaviour of such a reactor system is different from the usual PWR system behaviour. To provide an experimental database for the transient behaviour of VVER systems the PMK integral-type facility, the scaled down model of the Paks NPP was designed and constructed in the early 1980's. Since the start-up of the facility 48 experiments have been performed. It was confirmed through the experiments that the facility is a suitable tool for the computer code validation experiments and to the identification of basic thermal-hydraulic phenomena occurring during plant accidents. High international interest was shown by the four Standard Problem Exercises of the IAEA and by the projects financed by the EU-PHARE. A wide range of small- and medium-size LOCA sequences have been studied to know the performance and effectiveness of ECC systems and to evaluate the thermal-hydraulic safety of the core. Extensive studies have been performed to investigate the one- and two-phase natural circulation, the effect of disturbances coming from the secondary circuit and to validate the effectiveness of accident management measures like bleed and feed. The VVER-specific case, the opening of the SG collector cover was also extensively investigated. Examples given in the report show a few results of experiments and the results of calculation analyses performed for validation purposes of codes like RELAP5, ATHLET and CATHARE. There are some other white spots in Cross Reference Matrices for VVER reactors and, therefore, further experiments are planned to perform tests primarily in further support of accident management measures at low power states of plants to facilitate the improved safety management of VVER-440-type reactors. (authors)

  3. Rapid Software Development for Experiment Control at OPAL

    International Nuclear Information System (INIS)

    Hathaway, P.V.; Lam, Tony; Franceschini, Ferdi; Hauser, Nick; Rayner, Hugh

    2005-01-01

    Full text: ANSTO is undertaking the parallel development of instrument control and graphical experiment interface software for seven neutron beam instruments at OPAL. Each instrument poses several challenges for a common system solution, including custom detector interfaces, a range of motion and beamline optics schema, and a spectrum of online data reduction requirements. To provide a superior system with the least development effort, the computing team have adopted proven, configurable, server-based control software (SICS)1., a highly Integrated Scientific Experimental Environment (GumTree)2. and industry-standard database management systems. The resulting graphical interfaces allow operation in a familiar experiment domain, with monitoring of data and parameters independent of control system specifics. GumTree presents the experimenter with a consistent interface for experiment management, instrument control and data reduction tasks. The facility instrument scientists can easily reconfigure instruments and add ancillaries. The user community can expect a reduced learning curve for performing each experiment. GumTree can be installed anywhere for pre-experiment familiarisation, postprocessing of acquired data sets, and integration with third party analysis tools. Instrument scientists are seeing faster software development iterations and have a solid basis to prepare for the next suite of instruments. 1. SICS from PSI (lns00.psi.ch). 2. GumTree (gumtree.sourceforge.net), new site: http://gumtree.sourceforge.net/wiki/index.php/Main_Page

  4. 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.

  5. 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.

  6. LOCA assessment experiments in a full-elevation, CANDU-typical test facility

    International Nuclear Information System (INIS)

    Ingham, P.J.; McGee, G.R.; Krishnan, V.S.

    1990-01-01

    The RD-14 thermal-hydraulics test facility, located at the Whiteshell Nuclear Research Establishment, is a full-elevation model representative of a CANDU primary heat transport system. The facility is scaled to accommodate a single, full-scale (5.0 MW, 21 kg/s), electrically heated channel per pass. The steam generators, pumps, headers, feeders and heated channels are arranged in a typical CANDU figure-of-eight geometry. The loop has an emergency coolant injection system (ECI) that may be operated in several modes, including typical features of the various ECI systems found in CANDU reactors. A series of experiments has been performed in RD-14 to investigate the thermal-hydraulic behaviour during the blowdown and injection phases of a loss-of-coolant accident (LOCA). The tests were designed to cover a full range of break sizes from feeder-sized breaks to guillotine breaks in either an inlet or an outlet header. Breaks resulting in channel flow stagnation were also investigated. This paper reviews the results of some of the LOCA tests carried out in RD-14, and discusses some of the behaviour observed. Plans for future experiments in a multiple-channel RD-14 facility, modified to contain multiple flow channels, are outlined. (orig.)

  7. SBLOCA AND LOFW EXPERIMENTS IN A SCALED-DOWN IET FACILITY OF REX-10 REACTOR

    Directory of Open Access Journals (Sweden)

    YEON-GUN LEE

    2013-06-01

    Full Text Available This paper presents an experimental investigation of the small-break loss-of-coolant accident (SBLOCA and the loss-of-feedwater accident (LOFW in a scaled integral test facility of REX-10. REX-10 is a small integral-type PWR in which the coolant flow is driven by natural circulation, and the RCS is pressurized by the steam-gas pressurizer. The postulated accidents of REX-10 include the system depressurization initiated by the break of a nitrogen injection line connected to the steam-gas pressurizer and the complete loss of normal feedwater flow by the malfunction of control systems. The integral effect tests on SBLOCA and LOFW are conducted at the REX-10 Test Facility (RTF, a full-height full-pressure facility with reduced power by 1/50. The SBLOCA experiment is initiated by opening a flow passage out of the pressurizer vessel, and the LOFW experiment begins with the termination of the feedwater supply into the helical-coil steam generator. The experimental results reveal that the RTF can assure sufficient cooldown capability with the simulated PRHRS flow during these DBAs. In particular, the RTF exhibits faster pressurization during the LOFW test when employing the steam-gas pressurizer than the steam pressurizer. This experimental study can provide unique data to validate the thermal-hydraulic analysis code for REX-10.

  8. First laser-plasma interaction and hohlraum experiments on the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Dewald, E L; Glenzer, S H; Landen, O L; Suter, L J; Jones, O S; Schein, J; Froula, D; Divol, L; Campbell, K; Schneider, M S; Holder, J; McDonald, J W; Niemann, C; Mackinnon, A J; Hammel, B A [Lawrence Livermore National Laboratory, PO Box 808, Livermore, CA 94550 (United States)

    2005-12-15

    Recently the first laser-plasma interaction and hohlraum experiments have been performed at the National Ignition Facility (NIF) in support of indirect drive inertial confinement fusion designs. The effects of laser beam smoothing by spectral dispersion and polarization smoothing on the intense (2 x 10{sup 15} W cm{sup -2}) beam propagation in gas-filled tubes has been studied at up to 7 mm plasma scales as found in indirect drive gas filled ignition hohlraum designs. These experiments have shown the expected full propagation without filamentation and beam break up when using full laser smoothing. In addition, vacuum hohlraums have been irradiated with laser powers up to 6 TW, 1-9 ns pulse lengths and energies up to 17 kJ to activate several diagnostics, to study the hohlraum radiation temperature scaling with the laser power and hohlraum size, and to make contact with hohlraum experiments performed at the Nova and Omega laser facilities. Subsequently, novel long laser pulse hohlraum experiments have tested models of hohlraum plasma filling and long pulse hohlraum radiation production. The validity of the plasma filling assessment using in analytical models and radiation hydrodynamics calculations with the code LASNEX has been proven in these studies. The comparison of these results with modelling will be discussed.

  9. Conceptual design of initial opacity experiments on the national ignition facility

    Energy Technology Data Exchange (ETDEWEB)

    Heeter, R.  F.; Bailey, J.  E.; Craxton, R.  S.; DeVolder, B.  G.; Dodd, E.  S.; Garcia, E.  M.; Huffman, E.  J.; Iglesias, C.  A.; King, J.  A.; Kline, J.  L.; Liedahl, D.  A.; McKenty, P.  W.; Opachich, Y.  P.; Rochau, G.  A.; Ross, P.  W.; Schneider, M.  B.; Sherrill, M.  E.; Wilson, B.  G.; Zhang, R.; Perry, T.  S.

    2017-01-09

    Accurate models of X-ray absorption and re-emission in partly stripped ions are necessary to calculate the structure of stars, the performance of hohlraums for inertial confinement fusion and many other systems in high-energy-density plasma physics. Despite theoretical progress, a persistent discrepancy exists with recent experiments at the Sandia Z facility studying iron in conditions characteristic of the solar radiative–convective transition region. The increased iron opacity measured at Z could help resolve a longstanding issue with the standard solar model, but requires a radical departure for opacity theory. To replicate the Z measurements, an opacity experiment has been designed for the National Facility (NIF). The design uses established techniques scaled to NIF. A laser-heated hohlraum will produce X-ray-heated uniform iron plasmas in local thermodynamic equilibrium (LTE) at temperatures${\\geqslant}150$ eV and electron densities${\\geqslant}7\\times 10^{21}~\\text{cm}^{-3}$. The iron will be probed using continuum X-rays emitted in a${\\sim}200$ ps,${\\sim}200~\\unicode[STIX]{x03BC}\\text{m}$diameter source from a 2 mm diameter polystyrene (CH) capsule implosion. In this design

  10. 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...

  11. 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)

  12. 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...

  13. 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)

  14. 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)

  15. 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.

  16. 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

  17. Monte Carlo validation experiments for the gas Cherenkov detectors at the National Ignition Facility and Omega

    Energy Technology Data Exchange (ETDEWEB)

    Rubery, M. S.; Horsfield, C. J. [Plasma Physics Department, AWE plc, Reading RG7 4PR (United Kingdom); Herrmann, H.; Kim, Y.; Mack, J. M.; Young, C.; Evans, S.; Sedillo, T.; McEvoy, A.; Caldwell, S. E. [Plasma Physics Department, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Grafil, E.; Stoeffl, W. [Physics, Lawrence Livermore National Laboratory, Livermore, California 94551 (United States); Milnes, J. S. [Photek Limited UK, 26 Castleham Road, St. Leonards-on-sea TN38 9NS (United Kingdom)

    2013-07-15

    The gas Cherenkov detectors at NIF and Omega measure several ICF burn characteristics by detecting multi-MeV nuclear γ emissions from the implosion. Of primary interest are γ bang-time (GBT) and burn width defined as the time between initial laser-plasma interaction and peak in the fusion reaction history and the FWHM of the reaction history respectively. To accurately calculate such parameters the collaboration relies on Monte Carlo codes, such as GEANT4 and ACCEPT, for diagnostic properties that cannot be measured directly. This paper describes a series of experiments performed at the High Intensity γ Source (HIγS) facility at Duke University to validate the geometries and material data used in the Monte Carlo simulations. Results published here show that model-driven parameters such as intensity and temporal response can be used with less than 50% uncertainty for all diagnostics and facilities.

  18. First radioactive beams at ACCULINNA-2 facility and first proposed experiment

    Science.gov (United States)

    Bezbakh, A. A.; Beekman, W.; Chudoba, V.; Fomichev, A. S.; Golovkov, M. S.; Gorshkov, A. V.; Grigorenko, L. V.; Kaminski, G.; Krupko, S. A.; Mentel, M.; Nikolskii, E. Yu.; Parfenova, Yu. L.; Plucinski, P.; Sidorchuk, S. I.; Slepnev, R. S.; Sharov, P. G.; Ter-Akopian, G. M.; Zalewski, B.

    2018-04-01

    New fragment separator ACCULINNA-2 was installed at the primary beam line of the U-400M cyclotron in 2016. Recently, first radioactive ion beams were obtained. The design parameters of new facility were experimentally confirmed. Intensity, purity and transverse profile of several secondary beams at the final focal plane were studied. The intensities obtained for the secondary beams of 14B, 12Be, 9;11Li, 6;8He in the fragmentation reaction 15N (49.7 AMeV) + Be (2 mm) are in average 15 times higher in comparison to the ones produced at its forerunner ACCULINNA separator. The ACCULINNA-2 separator will become a backbone facility at the FLNR for the research in the field of light exotic nuclei in the vicinity of the nuclear drip lines. The planned first experiment, aimed for the observation of the 7H nucleus at ACCULINNA-2, is outlined.

  19. Decontamination and decommissioning of the Organic Moderated Reactor Experiment facility (OMRE)

    International Nuclear Information System (INIS)

    Hine, R.E.

    1980-09-01

    This report describes the decontamination and decommissioning (D and D) of the Organic Moderated Reactor Experiment (OMRE) facility performed from October 1977 through September 1979. This D and D project included removal of all the facilities and as much contaminated soil and rock as practical. Removal of the reactor pressure vessel was an unusually difficult problem, and an extraordinary, unexpected amount of activated rock and soil was removed. After removal of all significantly contaminated material, the site consisted of a 20-ft deep excavation surrounded by backfill material. Before this excavation was backfilled, it and the backfill material were radiologically surveyed and detailed records made of these surveys. After the excavation was backfilled and graded, the site surface was surveyed again and found to be essentially uncontaminated

  20. CJSC ECOMET-S facility for reprocessing and utilisation of radioactive metal waste: operating experience

    International Nuclear Information System (INIS)

    Gelbutovsky, A.B.; Kishkin, S.A.; Mochenov, M.I.; Troshev, A.V.; Cheremisin, P.I.; Chernichenko, A.A.

    2006-01-01

    The principal objective of the paper is to present operating experience in management of radioactive metal waste, originating at nuclear power facilities of the Russian Federation. Issues of radioactive metal waste recycling by melting, with the purpose of unrestricted re-use in industry, or restricted re-use within the nuclear industry, have been considered. The necessity for using a method of melting at the final stage of radioactive metal waste recycling has been proved. Priority measures to be taken and results achieved in the implementation of the Governmental purpose-oriented programme 'Radioactive Metal Waste Reprocessing and Utilization' have been considered, the CJSC ECOMET-S being the main contractor on the Programme. Main specifications and results of operating a commercial melting facility, owned by CJSC 'ECOMET-S' and used to recycle low-level radioactive metal waste originated at the Leningrad Nuclear Power Plant, have been presented. (author)

  1. 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.

  2. Development of an active structure flight experiment

    Science.gov (United States)

    Manning, R. A.; Wyse, R. E.; Schubert, S. R.

    1993-02-01

    The design and development of the Air Force and TRW's Advanced Control Technology Experiment (ACTEX) flight experiment is described in this paper. The overall objective of ACTEX is to provide an active structure trailblazer which will demonstrate the compatibility of active structures with operational spacecraft performance and lifetime measures. At the heart of the experiment is an active tripod driven by a digitally-programmable analog control electronics subsystem. Piezoceramic sensors and actuators embedded in a graphite epoxy host material provide the sensing and actuation mechanism for the active tripod. Low noise ground-programmable electronics provide a virtually unlimited number of control schemes that can be implemented in the space environment. The flight experiment program provides the opportunity to gather performance, reliability, adaptability, and lifetime performance data on vibration suppression hardware for the next generation of DoD and NASA spacecraft.

  3. Beam studies and experimental facility for the AWAKE experiment at CERN

    CERN Document Server

    Bracco, Chiara; Petrenko, Alexey; Timko, Helga; Argyropoulos, Theodoros; Bartosik, Hannes; Bohl, Thomas; Esteban Müller, Juan; Goddard, Brennan; Meddahi, Malika; Pardons, Ans; Shaposhnikova, Elena; Velotti, Francesco M; Vincke, Helmut

    2014-01-01

    A Proton Driven Plasma Wakefield Acceleration Experiment has been proposed as an approach to eventually accelerate an electron beam to the TeV energy range in a single plasma section. To verify this novel technique, a proof of principle R&D experiment, AWAKE, is planned at CERN using 400 GeV proton bunches from the SPS. An electron beam will be injected into the plasma cell to probe the accelerating wakefield. The AWAKE experiment will be installed in the CNGS facility profiting from existing infrastructure where only minor modifications need to be foreseen. The design of the experimental area and the proton and electron beam lines are shown. The achievable SPS proton bunch properties and their reproducibility have been measured and are presented.

  4. 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...

  5. 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.

  6. 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

  7. 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.

  8. Verification of the code ATHLET by post-test analysis of two experiments performed at the CCTF integral test facility

    International Nuclear Information System (INIS)

    Krepper, E.; Schaefer, F.

    2001-03-01

    In the framework of the external validation of the thermohydraulic code ATHLET Mod 1.2 Cycle C, which has been developed by the GRS, post test analyses of two experiments were done, which were performed at the japanese test facility CCTF. The test facility CCTF is a 1:25 volume-scaled model of a 1000 MW pressurized water reactor. The tests simulate a double end break in the cold leg of the PWR with ECC injection into the cold leg and with combined ECC injection into the hot and cold legs. The evaluation of the calculated results shows, that the main phenomena can be calculated in a good agreement with the experiment. Especially the behaviour of the quench front and the core cooling are calculated very well. Applying a two-channel representation of the reactor model the radial behaviour of the quench front could be reproduced. Deviations between calculations and experiment can be observed simulating the emergency injection in the beginning of the transient. Very high condensation rates were calculated and the pressure decrease in this phase of the transient is overestimated. Besides that, the pressurization due to evaporation in the refill phase is underestimated by ATHLET. (orig.) [de

  9. The choice of park and ride facilities: an analysis using a context-dependent hierarchical choice experiment

    OpenAIRE

    Ilona D M Bos; Rob E C M Van der Heijden; Eric J E Molin; Harry J P Timmermans

    2004-01-01

    Park and ride (P & R) facilities have been proposed in several countries to alleviate the accessibility problems in cities. Despite growing accessibility problems, these facilities do not seem to attract the expected number of car drivers and are underused. In an attempt to measure consumer evaluations of the attributes of P & R facilities, a stated choice experiment, based on the method of hierarchical information integration, was conducted in the city of Nijmegen, The Netherlands. This pape...

  10. 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

  11. Social Work Experience and Development in China

    Science.gov (United States)

    Sibin, Wang

    2013-01-01

    This article presents the experience and limitations of government-run social work and the nonprofessional nature of social work, and suggests that the rapid development of social work and its professionalization are the inevitable results of the reform in the system. The author maintains that under market socialism, social work requires the…

  12. Idealism, Education and Development: The Nigerian Experience ...

    African Journals Online (AJOL)

    Education developed from the human struggle for continual existence and enlightenment and may be formal or informal. The process of informal education includes all the agencies outside the formal school system which influence the child experience or learning. Informal education can be found at home, in the church or ...

  13. The Mentoring Experience: Leadership Development Program Perspectives

    Science.gov (United States)

    Lamm, Kevan W.; Sapp, Rochelle; Lamm, Alexa J.

    2017-01-01

    Using a semi-structured interview approach, ten mentors from a leadership development program focused on building leaders in Colleges of Agriculture and Life Sciences across the nation provided insights regarding their mentoring method, process, and experiences. Mentors interviewed agreed the mentoring process was beneficial for themselves as well…

  14. The effect of facility characteristics on patient safety, patient experience, and service availability for procedures in non-hospital-affiliated outpatient settings: A systematic review.

    Science.gov (United States)

    Berglas, Nancy F; Battistelli, Molly F; Nicholson, Wanda K; Sobota, Mindy; Urman, Richard D; Roberts, Sarah C M

    2018-01-01

    Over recent decades, numerous medical procedures have migrated out of hospitals and into freestanding ambulatory surgery centers (ASCs) and physician offices, with possible implications for patient outcomes. In response, states have passed regulations for office-based surgeries, private organizations have established standards for facility accreditation, and professional associations have developed clinical guidelines. While abortions have been performed in office setting for decades, states have also enacted laws requiring that facilities that perform abortions meet specific requirements. The extent to which facility requirements have an impact on patient outcomes-for any procedure-is unclear. We conducted a systematic review to examine the effect of outpatient facility type (ASC vs. office) and specific facility characteristics (e.g., facility accreditation, emergency response protocols, clinician qualifications, physical plant characteristics, other policies) on patient safety, patient experience and service availability in non-hospital-affiliated outpatient settings. To identify relevant research, we searched databases of the published academic literature (PubMed, EMBASE, Web of Science) and websites of governmental and non-governmental organizations. Two investigators reviewed 3049 abstracts and full-text articles against inclusion/exclusion criteria and assessed the quality of 22 identified articles. Most studies were hampered by methodological challenges, with 12 of 22 not meeting minimum quality criteria. Of 10 studies included in the review, most (6) examined the effect of facility type on patient safety. Existing research appears to indicate no difference in patient safety for outpatient procedures performed in ASCs vs. physician offices. Research about specific facility characteristics is insufficient to draw conclusions. More and higher quality research is needed to determine if there is a public health problem to be addressed through facility

  15. Experiments to determine the migration potential for water and contaminants in shallow land burial facilities design, emplacement, and preliminary results

    International Nuclear Information System (INIS)

    DePoorter, G.L.; Abeele, W.V.; Burton, B.W.

    1982-01-01

    Leaching and transport of radionuclides by water has been a primary mode of radioactive contamination from low-level radioactive waste disposal facilities. Similarly, the infiltration of water into nonradioactive hazardous waste disposal facilities has resulted in the movement of contaminants out of these disposal facilities. Although there have been many laboratory studies on water movement and contaminant transport, there is a need for more large scale field experiments. Large scale field experiments are necessary to (1) measure hydraulic conductivities on a scale typical of actual shallow land burial facilities and hazardous waste disposal facilities, (2) allow comparisons to be made between full scale and laboratory measurements, (3) verify the applicability of calculational methods for determining unsaturated hydraulic conductivities from water retention curves, and (4) for model validation. Experiments that will provide the information to do this are described in this paper

  16. 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)

  17. Periodic Safety Review in Interim Storage Facilities - Current Regulation and Experiences in Germany

    International Nuclear Information System (INIS)

    Neles, Julia Mareike; Schmidt, Gerhard

    2014-01-01

    Periodic safety reviews in nuclear power plants in Germany have been performed since the end of the 1980's as an indirect follow-up of the accident in Chernobyl and, in the meantime, are formally required by law. During this process the guidelines governing this review were developed in stages and reached their final form in 1996. Interim storage facilities and other nuclear facilities at that time were not included, so the guidelines were solely focused on the specific safety issues of nuclear power plants. Following IAEA's recommendations, the Western European Nuclear Regulator Association (WENRA) introduced PSRs in its safety reference levels for storage facilities (current version in WGWD report 2.1 as of Feb 2011: SRLs 59 - 61). Based on these formulations, Germany improved its regulation in 2010 with a recommendation of the Nuclear Waste Management Commission (Entsorgungskommission, ESK), an expert advisory commission for the federal regulatory body BMU. The ESK formulated these detailed requirements in the 'ESK recommendation for guides to the performance of periodic safety reviews for interim storage facilities for irradiated fuel elements and heat-generating radioactive waste'. Before finalization of the guideline a test phase was introduced, aimed to test the new regulation in practice and to later include the lessons learned in the final formulation of the guideline. The two-year test phase started in October 2011 in which the performance of a PSR will be tested at two selected interim storage facilities. Currently these recommendations are discussed with interested/concerned institutions. The results of the test phase shall be considered for improvements of the draft and during the final preparation of guidelines. Currently the PSR for the first ISF is in an advanced stage, the second facility just started the process. Preliminary conclusions from the test phase show that the implementation of the draft guideline requires interpretation. The aim of a

  18. State-of-the-Art Report for the Deep URL Facility Development : Aspo Hard Rock Laboratory, Grimsel Test Site

    International Nuclear Information System (INIS)

    Kim, Kyung Su; Bae, Dae Seok; Kim, Geon Young

    2012-01-01

    This report analysed the development status on the SKB's Hard Rock Laboratory and Nagra's Grimsel Test Site facilities to investigate their facility overview, operation system, site condition, project history and procedure, and current experiment programmes of underground research laboratory. SKB and Nagra had launched high level radioactive waste disposal project around 1970's. Actual site investigation activities were initiated since 1990's and the time schedule for siting programmes to determine the final disposal site were taken fifteen to thirty years. Furthermore, ten to twenty years will be needed to site characterization, facility design, construction, and operation commissioning. Nagra had constructed Grimsel Test Site facility in southern Switzerland Apls with the collaboration of KWO electrical company in early 1980's. This facility is characterized of a centre of excellence for underground Research and Development (R and D) to support projects for the disposal of radioactive and chemo-toxic waste and not a potential repository site. The SKB's Aspo HRL constructed in outside Oskarshamn is a unique PBG-URL facility. SKB is conducting full-scale research and development here in preparation for the construction of a final repository for spent nuclear fuel. The research programmes for the development of disposal technologies is performed over thirty to fifty years prior to repository operation. In 2000's, research on long-term phenomena, i.e., optimization of disposal concept, understanding of coupling process, validation of mathematical model, test and development of safety assessment models, characterization of deep geochemical environment, and long-term demonstration experiments have been leading the issues of research and development

  19. French experience of regulation and operation on reprocessing facilities of LWR spent fuels

    Energy Technology Data Exchange (ETDEWEB)

    Mercier, J P [DES/SESUL (France)

    1992-02-01

    This presentation describes the French experience of regulation and operation on reprocessing facilities: how the safety assessment was made of UP3-A plant of the La Hague establishment for the building permit and operating license within the context of French nuclear regulations and the national debate on the need for reprocessing. Other factors discussed are how the public was involved, how the regulations were improved in the process and what the different stages of commissioning consisted of. In the design studies of a reprocessing facility, three complementary approaches are used: - observance of regulations born of technical considerations, and good practice, - analysis of the hazards, using deterministic and probabilistic methods, within the framework of a safety report, - review of experience feedback from such a facility or like plants. The design of the facility must permit the prevention of accidents and limit their consequences. Moreover, during all foreseeable cases (normal operating, incidents and accidents), the safety of the staff, the public and the environment with regard to consequences of radioactive releases and ionising radiations must be ensured. In the evaluation of these consequences, the approach used is voluntarily pessimistic in order to take into account every possible case. It is based on the main following principles: definition of the events considered for the dimensioning of the facility; redundancy and diversification; defense in depth which consists of the multiplication of the barriers. The experience feedback comes, on the one hand from operator's findings aiming at improving its facility, on the other hand from incidents, the lessons of which being taken into account after careful analysis. These incidents are analyzed by the Safety Authority upon presentation of the data by the operator and on site findings of inspections. In other respects, the aim of inspections is to check that the plant and its operating practices are

  20. What's your opinion? The experience of therapeutic climate in a treatment facility for adults with mild intellectual disability and severe challenging behavior

    NARCIS (Netherlands)

    Helmond, P.; Vermaes, I.P.R.; Helm, G.H.P. van der

    2014-01-01

    Aim: A therapeutic climate is important so that clients can optimally develop themselves. In a treatment facility for adults with mild intellectual disability and severe challenging behavior we assessed clients’ experiences of therapeutic climate in relation to their internalizing and externalizing