WorldWideScience

Sample records for control facility installation

  1. ACP Facility Safety Surveillance System Installation

    International Nuclear Information System (INIS)

    You, Gil Sung; Kook, D. H.; Choung, W. M.; Ku, J. H.; Cho, I. J.; You, G. S.; Kwon, K. C.; Lee, W. K.; Lee, E. P.

    2006-10-01

    The Advanced spent fuel Conditioning Process is under development for effective management of spent fuel by converting UO 2 into U-metal. For demonstration of this process, α-γ type new hotcell was built in the IMEF basement. All facilities which treat radioactive materials must manage CCTV system which is under control of Health Physics department. Three main points (including hotcell rear door area) have each camera, but operators who are in charge of facility management need to check the safety of the facility immediately through the network in his office. This needs introduce additional network cameras installation and this new surveillance system is expected to update the whole safety control ability with existing system

  2. The control of base nuclear facilities (I.N.B.); Le controle des installations nucleaires de base (INB)

    Energy Technology Data Exchange (ETDEWEB)

    Anon

    2009-02-15

    The Authority of Nuclear Safety ( A.S.N). presents in this column the current events of the control of the nuclear basic installations during august, september, october 2008, classified by nuclear site. This information is also available in real-time on the A.S.N. web site, www.asn.fr, in the column 'news'. We can consult all the notices of significant incident published as well as the following letters of inspection, the notices of information about the reactors shutdown, press releases and the A.S.N. information notes. (N.C.)

  3. Survey report for fiscal 1999. Report on basic survey on joint implementation of installing coal moisture control (CMC) facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    For the purpose of the COP3 joint implementation in fiscal 1999, a survey and discussions were given on installing coal moisture control (CMC) facilities in China. The possibility was discussed with the Jinan Steel Group Company and Shougang Company. The subject is a beehive coke furnace, in which coal containing 11% of water is sent to a fluidized bed dryer, and dried up to 6.6%. Stack gas in the coke furnace is used mainly as the drying heat source. The facility consists of a fluidized bed dryer, a dust collector, a coal transporter, and a stack gas recovering device. The energy saving effects made available to the above two companies are as remarkable as 19,868 tons/year and 12,189 tons/year, respectively, as converted to crude oil, and the greenhouse effect gas reduction effect as 61,476 tons/year and 37,715 tons/year, respectively. Because energy price is low in China, the investment recovery time period is set at six years or less as the limit for economic performance evaluation. As a result of the calculation, the recovery time periods for the above two companies were found to be 4.2 and 4.7 years, proving the CMC project highly promising. It is desired that the project will be moved forward once the issues of the fund raising and the discharge right of global warming gas are made clear. (NEDO)

  4. Facility design, installation and operation

    International Nuclear Information System (INIS)

    Fleischmann, A.W.

    1985-01-01

    Problems that may arise when considering the design, construction and use of a facility that could contain up to tens of petabecquerel of either cobalt-60 or caesium-137 are examined. The safe operation of an irradiation facility depends on an appreciation of the in built safety systems, adequate training of personnel and the existence of an emergency system

  5. Design, fabrication and installation of irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Bong Shick; Kim, Y. S.; Lee, C. Y. and others

    1999-03-01

    The principal contents of this project are to design, fabricate and install the steady-state fuel test loop in HANARO for nuclear technology development. Procurement and fabrication of main equipment, licensing and technical review for fuel test loop have been performed during 2 years(1997, 1998) for this project. Following contents are described in the report. - Procurement and fabrication of the equipment, piping for OPS - IPS manufacture - License - Technical review and evaluation of the FTL facility. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and review ofHANARO interface have been performed respectively. (author)

  6. Design, fabrication and installation of irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yong Sung; Lee, C. Y.; Kim, J. Y.; Chi, D. Y.; Kim, S. H.; Ahn, S. H.; Kim, S. J.; Kim, J. K.; Yang, S. H.; Yang, S. Y.; Kim, H. R.; Kim, H.; Lee, K. H.; Lee, B. C.; Park, C.; Lee, C. T.; Cho, S. W.; Kwak, K. K.; Suk, H. C. [and others

    1997-07-01

    The principle contents of this project are to design, fabricate and install the steady-state fuel test loop and non-instrumented capsule in HANARO for nuclear technology development. This project will be completed in 1999, the basic and detail design, safety analysis, and procurement of main equipment for fuel test loop have been performed and also the piping in gallery and the support for IPS piping in reactor pool have been installed in 1994. In the area of non-instrumented capsule for material irradiation test, the fabrication of capsule has been completed. Procurement, fabrication and installation of the fuel test loop will be implemented continuously till 1999. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and safety analysis report has been submitted to KINS to get a license and review of HANARO interface have been performed respectively. (author). 39 refs., 28 tabs., 21 figs.

  7. Design, fabrication and installation of irradiation facilities

    International Nuclear Information System (INIS)

    Kim, Yong Sung; Lee, C. Y.; Kim, J. Y.; Chi, D. Y.; Kim, S. H.; Ahn, S. H.; Kim, S. J.; Kim, J. K.; Yang, S. H.; Yang, S. Y.; Kim, H. R.; Kim, H.; Lee, K. H.; Lee, B. C.; Park, C.; Lee, C. T.; Cho, S. W.; Kwak, K. K.; Suk, H. C.

    1997-07-01

    The principle contents of this project are to design, fabricate and install the steady-state fuel test loop and non-instrumented capsule in HANARO for nuclear technology development. This project will be completed in 1999, the basic and detail design, safety analysis, and procurement of main equipment for fuel test loop have been performed and also the piping in gallery and the support for IPS piping in reactor pool have been installed in 1994. In the area of non-instrumented capsule for material irradiation test, the fabrication of capsule has been completed. Procurement, fabrication and installation of the fuel test loop will be implemented continuously till 1999. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and safety analysis report has been submitted to KINS to get a license and review of HANARO interface have been performed respectively. (author). 39 refs., 28 tabs., 21 figs

  8. Clean room installations in a radiopharmaceutical facility

    International Nuclear Information System (INIS)

    2000-01-01

    The standards of radiopharmaceuticals on the facility, working environment and preparation control strategy are yet to be generated. In general, radiopharmaceuticals have short half-lives and emit gamma radiation. Due to its unique characteristics, its preparation has to be made in the fume hood and hot cell to avoid radiation exposure to workers. Considering radiation protection, the working environment has to be maintained under negative pressure so that dispersion of radiopharmaceuticals should be avoided. On the contrary, a positively pressurized working environment gives clean atmosphere and prevents contamination with harmful microorganisms during preparation. Hence, it is required to harmonize for mentioned contradictory conditions in preparation of radiopharmaceuticals for the safety of workers and its quality assurance as well. Therefore, it is reasonable that good manufacturing practice for radiopharmaceutical production facility should be constituted according to the standards for production of biological agents accompanied with a radiation shielding

  9. Radiation control at the Continuous Electron Beam Accelerator Facility (CEBAF), a new high power CW electron accelerator installation

    International Nuclear Information System (INIS)

    Stapleton, G.B.; Thomas, R.H.

    1989-01-01

    A description is given of the design goals and radiation control measures, for a new 4 GeV, 1 MW electron accelerator under construction in the USA. The paper illustrates the importance of cooperation between designers and regulators. 15 refs., 1 fig., 3 tabs

  10. Fuel followed control rod installation at AFRRI

    International Nuclear Information System (INIS)

    Moore, Mark; Owens, Chris; Forsbacka, Matt

    1992-01-01

    Fuel Followed Control Rods (FFCRs) were installed at the Armed Forces Radiobiology Research Institute's 1 MW TRIGA Reactor. The procedures for obtaining, shipping, and installing the FFCRs is described. As part of the FFCR installation, the transient rod drive was relocated. Core performance due to the addition of the fuel followed control rods is discussed. (author)

  11. Installation of concrete expansion anchors at the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Clark, G.L.

    1980-01-01

    Installation criteria utilized at the Fast Flux Test Facility for concrete expansion anchors are presented. Static and dynamic load capabilities of various anchor types are discussed in relation to design loads, with particular emphasis placed on the yield load (the proportional limit). Effects of several variables (i.e., installation torque, hole diameter) are also investigated. Resolution and documentation of field problems (e.g., improper spacing, embedment, angularity) are also described. Recommendations for improving and controlling future installations are given

  12. Computer systems for nuclear installation data control

    International Nuclear Information System (INIS)

    1987-09-01

    The computer programs developed by Divisao de Instalacoes Nucleares (DIN) from Brazilian CNEN for data control on nuclear installations in Brazil are presented. The following computer programs are described: control of registered companies, control of industrial sources, irradiators and monitors; control of liable person; control of industry irregularities; for elaborating credence tests; for shielding analysis; control of waste refuge [pt

  13. Installation of Tc-99m generator manufacturing facilities

    International Nuclear Information System (INIS)

    Shin, B. C.; Choung, W. M.; Park, J. H.; Park, S. H.; Kim, S. J.; Park, K. B.

    2004-01-01

    For the characteristics of radiopharmaceuticals, the manufacturing facility should be complied with the radiation safety standards for operators as well as GMP (Good Manufacturing Practice) cleanness standards for production. We intensively modified the existing Radioisotope production facilities, which were installed only in radiation safety points of view, to meet cleanness criteria. And the concept of multi-barrier buffer zones was introduced to apply negative air pressure for hot cell with first priority and to continue relative positive air pressure for clean room. The manufacturing area for Tc-99m Generator can be entered only through a second change. The doors of each change area are interlocked to maintain air pressure differentials. The pass box for material transfer are also interlocked so that only one side may be opened at any one time to keep cleanness. Two door-type autoclave was installed crossing the wall between preparing room and aseptic room to keep cleanness after sterilization. Three lead hot cells were installed and final inspection including gamma survey test were performed. The clean room was installed and TAB for this facility was performed in order to acquire the necessary air flow. The filter bank for filtration of exhausted radiation air was installed and its efficiency test was performed. In this facility, radiation shielding utilities and manufacturing instruments were set up and their operating manuals were documented. Efficiency tests for every utilities and instruments were satisfied and the approval for use of the facilities was achieved from MOST (Ministry of Science and Technology). The Sam Young Unitech, the lessee of the facilities set up the equipment in the hot cell, which is needed to produce Tc-99m Generator, supported by IPPE in Russia. They are composing the systems complied with the guidelines and the regulations, and keep in contact to KFDA for acquiring its approval. It is expected to produce Tc-99m Generator within

  14. Emission Facilities - Erosion & Sediment Control Facilities

    Data.gov (United States)

    NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

  15. Irradiation facilities for materials research: IFMIF and small scale installations

    International Nuclear Information System (INIS)

    Perlado, J. M.; Victoria, M.

    2007-01-01

    The research of advance materials in nuclear fields such as new fission reactors (Generation-IV), Accelerator Driven Systems for Transmutation of Radioactive Wastes and Nuclear Fusion, is becoming very much common in the types of low activation and radiation resistant Materials. Ferritic-Martensitic Steels (based in 9-12 Cr) with or without Oxide Dispersion Techniques (Ytria Nanoparticles), Composites materials are becoming the new generation to answer requirements of high temperature, high radiation resistance of structural materials. Special dedication is appearing in general research programmes to this area of Materials. The understanding of their final performance needs a wider knowledge of the mechanisms of radiation damage in these materials from the atomistic scale to the macroscopic responses. New extensive campaigns are being funded to irradiate from simple elements to model alloys and finally the complex materials themselves. That sequence and its state of art will be presented One clear technique for that understanding is the Multi scale Modelling which includes simulation techniques from quantum mechanics, molecular dynamics, defects diffusion, mesoscopic modelling and finally the macroscopic constitutive relations for macroscopic analysis. However, in each one of these steps is necessary a systematic and well established program of experiments that combines the irradiation and the very detailed analysis with techniques such as Transmission Electron Microscope, Positron Annihilation, SIMS, Atom Probe, Nanoindebntation. A key aspect that wants to be presented in this work is the state of art and discussion of Irradiation Facilities for Materials studies. Those facilities goes from ion implantation sources, small accelerator, Experimental Reactors such High Flux Reactor, sophisticated Triple Beams Sources as JANNUS in France to generate at the same time displacements-hydrogen-helium, and projected very large neutron installation such as IFMIF. The role to

  16. Two passive groundwater treatment installations at DOE facilities

    International Nuclear Information System (INIS)

    Barton, W.D.; Craig, P.M.; Stone, W.C.

    1997-01-01

    Groundwater is being successfully treated by reactive media at two DOE sites. Passive treatment utilizing containerized treatment media has been installed on a radioactive groundwater seep at Oak Ridge National Lab, Oak Ridge, Tennessee, and on a TCE plume at the Portsmouth Gaseous Diffusion Plant in Piketon, Ohio. In both applications, flow is conducted by gravity through canisters of reactive treatment media. The canister-based treatment installation at ORNL utilizes a natural sodium-chabazite zeolite to remove radiological cations (Sr, Cs) from contaminated groundwater at greater than 99.9% efficiency. Portsmouth is currently conducting tests on three different types of treatment media for reductive dehalogenation of TCE

  17. 78 FR 72794 - Revisions to Auxiliary Installations, Replacement Facilities, and Siting and Maintenance Regulations

    Science.gov (United States)

    2013-12-04

    ... company's reliance on section 2.55(a) to install an air stabilization unit was unwarranted because the... coolers, a transformer, field inlet separation facilities, and pigging equipment). [[Page 72796

  18. Generic description of facilities at the shaft head (auxiliary entrance installations) of deep geological repositories

    International Nuclear Information System (INIS)

    2016-10-01

    In a deep geological repository, the access structures function as the link between the surface and the installations and structures at the disposal level. In the planned implementation scenarios, at least two access structures will be in operation up to the time of closure of the repository. The radioactive waste will be transported via the main access from the surface to the disposal level during emplacement operations. For the construction and operation of a deep geological repository, additional access structures are required. These auxiliary accesses and the associated surface infrastructure (e.g. shaft head installations) form the subject of this report. To provide as broad and comprehensive a description as possible, seven types of auxiliary access facilities are defined; these are characterised in line with the current status of planning and their functions and impacts are described. During construction, operation and dismantling of auxiliary access facilities, the usual conventional safety measures (inter alia) have to be observed (e.g. groundwater protection, fire prevention, facility security, accident prevention). Regarding the 'Ordinance on Protection against Major Accidents' no large quantities of hazardous materials, i.e. above the corresponding threshold quantities, are to be expected in the auxiliary access facilities. Proper handling and compliance with applicable regulations in all phases will ensure no hazard to humans and the environment. As no handling of radioactive materials is foreseen in the auxiliary access facilities, and because exhaust air and waste water from the controlled zones of a repository will, in principle, be removed via the main access and not the auxiliary accesses, a safety-relevant emission of radioactive substances and transport of contaminated material can be ruled out for the auxiliary access facilities during both normal operation and also in the case of an accident. Based on the information presented in

  19. The control of base nuclear installations; Le controle des installations nucleaires de base (INB)

    Energy Technology Data Exchange (ETDEWEB)

    Anon

    2009-04-15

    The Authority of Nuclear Safety ( A.S.N). presents in this column the current events of the control of the nuclear base installations during november, december 2008 and january 2009, classified by nuclear site. This information is also available in real-time on the A.S.N. web site, www.asn.fr, in the column 'news'. We can consult all the notices of significant incident published as well as the following letters of inspection, the notices of information about the reactors shutdown, press releases and the A.S.N. information notes. (N.C.)

  20. 30 CFR 75.1600-2 - Communication facilities; working sections; installation and maintenance requirements; audible or...

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Communication facilities; working sections; installation and maintenance requirements; audible or visual alarms. 75.1600-2 Section 75.1600-2 Mineral... SAFETY STANDARDS-UNDERGROUND COAL MINES Communications § 75.1600-2 Communication facilities; working...

  1. Power Consumption Analysis of Electrical Installations at Healthcare Facility

    Directory of Open Access Journals (Sweden)

    Emmanuel Guillen-Garcia

    2017-01-01

    Full Text Available This paper presents a methodology for power consumption estimation considering harmonic and interharmonic content and then it is compared to the power consumption estimation commonly done by commercial equipment based on the fundamental frequency, and how they can underestimate the power consumption considering power quality disturbances (PQD. For this purpose, data of electrical activity at the electrical distribution boards in a healthcare facility is acquired for a long time period with proprietary equipment. An analysis in the acquired current and voltage signals is done, in order to compare the power consumption centered in the fundamental frequency with the generalized definition of power consumption. The results obtained from the comparison in the power consumption estimation show differences between 4% and 10% of underestimated power consumption. Thus, it is demonstrated that the presence of harmonic and interharmonic content provokes a significant underestimation of power consumption using only the power consumption centered at the fundamental frequency.

  2. Use and regulatory control of dental X-ray installations

    International Nuclear Information System (INIS)

    1999-01-01

    In the guide the safety requirements concerning dental X-ray installations and their use, prerequisities for exemption from a safety licence, and regulatory control are presented. The guide applies to conventional dental X-ray installations, by which an image is created on an X-ray film or other image receptor placed inside the mouth, and panorama tomography installations for dentition and the cephalostats associated with these. The guide does not apply to multitechnique tomography installations intended for the special imaging of the skull or jaws

  3. Operation and maintenance manual of the accelerator installed in the facility of radiation standards

    International Nuclear Information System (INIS)

    Fujii, Katsutoshi; Kawasaki, Katsuya; Kowatari, Munehiko; Tanimura, Yoshihiko; Kajimoto, Yoichi; Shimizu, Shigeru

    2006-08-01

    4MV Van de Graff accelerator was installed in the Facility of Radiation Standards (FRS) in June 2000, and monoenergetic neutron calibration fields and high energy γ-ray calibration fields have been developed. The calibration fields are provided for R and D on dosimetry, and for the calibration and type-test of radiation protection instruments. This article describes the operational procedure, the maintenance work and the operation of the related apparatuses of the accelerator. This article focuses on the sufficient safety and radiation control for the operators, the maintenance performance of the accelerator, and on the prevention of the malfunction due to the mistakes of the operators. This article targets the unexperienced engineers in charge of operation and maintenance of the accelerator. (author)

  4. Preliminary assessment report for Army Aviation Support Facility No. 3, Installation 13307, Hunter Army Airfield, Savannah, Georgia. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Kolpa, R.; Smith, K.

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Georgia Army National Guard property located on Hunter Army Airfield (HAA) near Savannah, Georgia, known as Army Aviation Support Facility (AASF) No. 3. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, types and quantities of hazardous substances utilized, the nature and amounts of wastes generated or stored at the facility, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the AASF No. 3 property, requirements of the Department of Defense Installation Restoration Program (IRP). The scope of this assessment is limited to the facilities and past activities contained within the area now occupied by AASF No. 3. However, this assessment report is intended to be read in conjunction with a previous IRP assessment of HAA completed in 1992 (USATHAMA 1992) and to provide comprehensive information on AASF No. 3 for incorporation with information contained in that previous assessment for the entirety of HAA.

  5. Installation of a Low Flow Unit at the Abiquiu Hydroelectric Facility

    Energy Technology Data Exchange (ETDEWEB)

    Jack Q. Richardson

    2012-06-28

    Final Technical Report for the Recovery Act Project for the Installation of a Low Flow Unit at the Abiquiu Hydroelectric Facility. The Abiquiu hydroelectric facility existed with two each 6.9 MW vertical flow Francis turbine-generators. This project installed a new 3.1 MW horizontal flow low flow turbine-generator. The total plant flow range to capture energy and generate power increased from between 250 and 1,300 cfs to between 75 and 1,550 cfs. Fifty full time equivalent (FTE) construction jobs were created for this project - 50% (or 25 FTE) were credited to ARRA funding due to the ARRA 50% project cost match. The Abiquiu facility has increased capacity, increased efficiency and provides for an improved aquatic environment owing to installed dissolved oxygen capabilities during traditional low flow periods in the Rio Chama. A new powerhouse addition was constructed to house the new turbine-generator equipment.

  6. PLC based control system for RAM assembly test facility

    International Nuclear Information System (INIS)

    Kulkarni, S.S.; Kumar, Vinaya; Chandra, Umesh

    1994-01-01

    The flexibility, expandability, ease of programming and diagnostic features makes the programmable logic controller (PLC) suitable for a variety of control applications in engineering system test facilities. A PLC based control system for RAM assembly test facility (RATF) and for testing the related hydraulic components is being developed and installed at BARC. This paper describes the approach taken for meeting the control requirements and illustrates the PLC software that has been developed. (author). 1 fig

  7. 78 FR 679 - Revisions to the Auxiliary Installations, Replacement Facilities, and Siting and Maintenance...

    Science.gov (United States)

    2013-01-04

    ... process, see the Comment Procedures Section of this document. FOR FURTHER INFORMATION CONTACT: Katherine... existing facilities.\\14\\ The Commission reasoned that section 2.55(b) replacements ``should only involve... when an installation can qualify for section 157.203(b) automatic authorization). Further, to alleviate...

  8. Fatigue damage of nuclear facilities; Endommagement par fatigue des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The conference on the fatigue damage of nuclear facilities, organized by the SFEN (french society of nuclear energy), took place at Paris the 23. of november 2000. Eleven papers were presented, showing the state of the art and the research programs in the domain of the sizing rules, safety, installations damage, examination and maintenance. (A.L.B.)

  9. 30 CFR 71.500 - Sanitary toilet facilities at surface work sites; installation requirements.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Sanitary toilet facilities at surface work sites; installation requirements. 71.500 Section 71.500 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND...

  10. Assembly and installation of the large coil test facility test stand

    International Nuclear Information System (INIS)

    Queen, C.C. Jr.

    1983-01-01

    The Large Coil Test Facility (LCTF) was built to test six tokamak-type superconducting coils, with three to be designed and built by US industrial teams and three provided by Japan, Switzerland, and Euratom under an international agreement. The facility is designed to test these coils in an environment which simulates that of a tokamak. The heart of this facility is the test stand, which is made up of four major assemblies: the Gravity Base Assembly, the Bucking Post Assembly, the Torque Ring Assembly, and the Pulse Coil Assembly. This paper provides a detailed review of the assembly and installation of the test stand components and the handling and installation of the first coil into the test stand

  11. Performance evaluation on force control for ITER blanket installation

    Energy Technology Data Exchange (ETDEWEB)

    Aburadani, A., E-mail: aburadani.atsushi@jaea.go.jp [Japan Atomic Energy Agency, Mukouyama 801-1, Naka, Ibaraki 311-0193 (Japan); Takeda, N.; Shigematsu, S.; Murakami, S.; Tanigawa, H.; Kakudate, S. [Japan Atomic Energy Agency, Mukouyama 801-1, Naka, Ibaraki 311-0193 (Japan); Nakahira, M.; Hamilton, D.; Tesini, A. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)

    2013-10-15

    Highlights: ► It is crucial issues to avoid any jamming between the blanket modules and the keys. ► Force control for AC servo motor was developed to reduce excessive loads. ► This jam prevention force control method is directly measured and controlled by AC servo motor controllers. ► In the recent test, the module was passively positioned onto keys using the torque control method. -- Abstract: The most critical issue for the ITER blanket installation is to avoid any jamming between the blanket modules and the keys as a result of excessive loading during the module installation process. This is complicated by the limited clearance of 0.5 mm between the modules and the keys. To solve these technical issues, force control, such as controlling the torque for the AC servo motors, was developed to reduce excessive loads which may have an impact on the end-effector and to defer the forces acting on the groove of the blanket. This jam prevention force control method is directly measured and controlled by AC servo motor controllers. The AC servo motors are equipped to move the manipulator and end-effector during module installation.

  12. Performance evaluation on force control for ITER blanket installation

    International Nuclear Information System (INIS)

    Aburadani, A.; Takeda, N.; Shigematsu, S.; Murakami, S.; Tanigawa, H.; Kakudate, S.; Nakahira, M.; Hamilton, D.; Tesini, A.

    2013-01-01

    Highlights: ► It is crucial issues to avoid any jamming between the blanket modules and the keys. ► Force control for AC servo motor was developed to reduce excessive loads. ► This jam prevention force control method is directly measured and controlled by AC servo motor controllers. ► In the recent test, the module was passively positioned onto keys using the torque control method. -- Abstract: The most critical issue for the ITER blanket installation is to avoid any jamming between the blanket modules and the keys as a result of excessive loading during the module installation process. This is complicated by the limited clearance of 0.5 mm between the modules and the keys. To solve these technical issues, force control, such as controlling the torque for the AC servo motors, was developed to reduce excessive loads which may have an impact on the end-effector and to defer the forces acting on the groove of the blanket. This jam prevention force control method is directly measured and controlled by AC servo motor controllers. The AC servo motors are equipped to move the manipulator and end-effector during module installation

  13. Engine Installation Effects of Four Civil Transport Airplanes: Wallops Flight Facility Study

    Science.gov (United States)

    Fleming, Gregg G.; Senzig, David A.; McCurdy, David A.; Roof, Christopher J.; Rapoza, Amanda S.

    2003-01-01

    The National Aeronautics and Space Administration (NASA), Langley Research Center (LaRC), the Environmental Measurement and Modeling Division of the United States Department of Transportation s John A. Volpe National Transportation Systems Center (Volpe), and several other organizations (see Appendix A for a complete list of participating organizations and individuals) conducted a noise measurement study at NASA s Wallops Flight Facility (Wallops) near Chincoteague, Virginia during September 2000. This test was intended to determine engine installation effects on four civil transport airplanes: a Boeing 767-400, a McDonnell-Douglas DC9, a Dassault Falcon 2000, and a Beechcraft King Air. Wallops was chosen for this study because of the relatively low ambient noise of the site and the degree of control over airplane operating procedures enabled by operating over a runway closed to other uses during the test period. Measurements were conducted using a twenty microphone U-shaped array oriented perpendicular to the flight path; microphones were mounted such that ground effects were minimized and low elevation angles were observed.

  14. Automated installation for several photomultiplier photocathode activation by means of one vacuum facility

    International Nuclear Information System (INIS)

    Beschastnov, P.M.; Peryshkin, A.I.; Pyata, E.Eh.; Usov, Yu.V.

    1989-01-01

    An automated installation for simultaneous activation of up to four photocathodes of several photomultipliers by means of one vacuum station with the common furnace is described. Production technology of producing multialkaline photocathode makes up the basis for creating automated technology. The installation is produced on the base of the R110B industrial station and the Electronica-60 microcomputer. Software written in FORTRAN providing for control over all process stages is developed. 6 refs.; 2 figs

  15. Work control in separations facilities

    International Nuclear Information System (INIS)

    Olson, L.D.

    1990-01-01

    The topic addressed in this technical review is the development and implementation of a work control program in one of the chemical separations facilities at the Savannah River Site (SRS) in Aiken, SC. This program will be used as a pilot for the Nuclear Materials Processing Division at the site. The SRS Work Control Pilot program is based on the Institute of Nuclear Power Operations (INPO) good practices and guidelines for the conduct of maintenance and complies with SRS quality assurance and DOE orders on maintenance management. The program follows a ten-step process for control of maintenance and maintenance-related activities in a chemical separations facility. The program took the existing maintenance planning and scheduling system and upgraded it to comply with all INPO work control and related guidelines for histories, post-maintenance testing and scheduling. The development process of adapting a nuclear-related- based plan to a batch/continuous chemical separations plant was a challenge. There were many opportunities to develop improvements in performance while being creative and realistic in applying reactor maintenance technology to chemical plant maintenance. This pilot program for work control in a nonreactor nuclear facility will provide valuable information for applying a controlled maintenance process to a multiphase chemical operating plant environment

  16. Air ventilation/controlling facility

    Energy Technology Data Exchange (ETDEWEB)

    Yoshikawa, Kazuhiro; Kinoshita, Shoichiro

    1997-12-12

    When all electricity supply from the outside of a power plant are lost, a power generator directly connected to an emergency steam turbine which is driven by steams introduced from a nuclear reactor is driven to supply electricity required in the power plant. Cool water prepared by a refrigerator is used as cooling water in an air ventilation/controlling facility of a room equipped with the power generating facility. As the refrigerator, a refrigerator of an existent emergency air cooling water system for an auxiliary air ventilation/controlling equipment is used. This can extend the period of time till the temperature of the room where the power generator is disposed exceeds the temperature range capable of keeping the integrity of the power generator even when all the AC power supply are lost to inactivate the function of the air ventilation/controlling system. (I.S.)

  17. Safety in connection with the request for approval of the installation alteration in the fuel reprocessing facilities of Power Reactor and Nuclear Fuel Development Corporation (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report to the Prime Minister by the Nuclear Safety Commission was presented concerning the safety in the installation alteration of the fuel reprocessing facilities, as PNC had requested its approval to the Prime Minister. The safety was confirmed. The items of examination on the safety made by the committee on Examination of Nuclear Fuel Safety of NSC were the aseismic design of liquid waste storage, uranium denitration facility, intermediate gate and radioactive solid waste storage; the criticality safety design of the denitration facility; the radiation shielding design of the liquid waste storage, denitration facility and solid waste storage; the function of radioactive material containment of the liquid waste storage and denitration facility; the radiation control in the liquid waste storage, denitration facility and solid waste storage; the waste management in the liquid waste storage and denitration facility; fire and explosion prevention in the liquid waste storage; exposure dose from the liquid waste storage and denitration facility. (Mori, K.)

  18. Remote system for monitoring and control of controlled area of nuclear installation

    International Nuclear Information System (INIS)

    Assuncao, Daniel Gomes de; Minhoni, Danilo Carlos Rossetto; Farias, Marcos Sant'anna de; Santos, Isaac J.A. Luquetti dos

    2011-01-01

    The maintenance activities in controlled areas of nuclear facilities require adequate planning and control so that these activities do not cause to the worker an undue exposure to radioactivity. For maximum safety of workers from these places, there are standards that determine the maximum radiation dose that a worker can receive. From this context, the objective of this research is to develop a remote system that shows remotely the maintenance tasks being carried out in this work environment; monitors information provided by radiation monitoring devices installed at workplace; tracks the time to carry out scheduled maintenance, reporting alarm if this time is exceeded or not. The system has video camera, radiation monitoring device, interface card to transmit data via ethernet and graphical user interface, developed using the LABVIEW application. The principal objective is to improve the safety and to preserve the worker's health. (author)

  19. Remote system for monitoring and control of controlled area of nuclear installation

    Energy Technology Data Exchange (ETDEWEB)

    Assuncao, Daniel Gomes de; Minhoni, Danilo Carlos Rossetto [Departamento de Ciencias da Administracao e Tecnologia. Centro Universitario de Araraquara (UNIARA) Araraquara, SP (Brazil); Farias, Marcos Sant' anna de; Santos, Isaac J.A. Luquetti dos, E-mail: luquetti@ien.gov.br [Instituto Engenharia Nuclear (IEN/CNEN-RJ), Rio Janeiro, RJ (Brazil). Divisao de Instrumentacao e Confiabilidade Humana

    2011-07-01

    The maintenance activities in controlled areas of nuclear facilities require adequate planning and control so that these activities do not cause to the worker an undue exposure to radioactivity. For maximum safety of workers from these places, there are standards that determine the maximum radiation dose that a worker can receive. From this context, the objective of this research is to develop a remote system that shows remotely the maintenance tasks being carried out in this work environment; monitors information provided by radiation monitoring devices installed at workplace; tracks the time to carry out scheduled maintenance, reporting alarm if this time is exceeded or not. The system has video camera, radiation monitoring device, interface card to transmit data via ethernet and graphical user interface, developed using the LABVIEW application. The principal objective is to improve the safety and to preserve the worker's health. (author)

  20. Optimal control of hydroelectric facilities

    Science.gov (United States)

    Zhao, Guangzhi

    This thesis considers a simple yet realistic model of pump-assisted hydroelectric facilities operating in a market with time-varying but deterministic power prices. Both deterministic and stochastic water inflows are considered. The fluid mechanical and engineering details of the facility are described by a model containing several parameters. We present a dynamic programming algorithm for optimizing either the total energy produced or the total cash generated by these plants. The algorithm allows us to give the optimal control strategy as a function of time and to see how this strategy, and the associated plant value, varies with water inflow and electricity price. We investigate various cases. For a single pumped storage facility experiencing deterministic power prices and water inflows, we investigate the varying behaviour for an oversimplified constant turbine- and pump-efficiency model with simple reservoir geometries. We then generalize this simple model to include more realistic turbine efficiencies, situations with more complicated reservoir geometry, and the introduction of dissipative switching costs between various control states. We find many results which reinforce our physical intuition about this complicated system as well as results which initially challenge, though later deepen, this intuition. One major lesson of this work is that the optimal control strategy does not differ much between two differing objectives of maximizing energy production and maximizing its cash value. We then turn our attention to the case of stochastic water inflows. We present a stochastic dynamic programming algorithm which can find an on-average optimal control in the face of this randomness. As the operator of a facility must be more cautious when inflows are random, the randomness destroys facility value. Following this insight we quantify exactly how much a perfect hydrological inflow forecast would be worth to a dam operator. In our final chapter we discuss the

  1. Manufacture and installation of reactor auxiliary facilities for advanced thermal prototype reactor 'Fugen'

    International Nuclear Information System (INIS)

    Kawahara, Toshio; Matsushita, Tadashi

    1977-01-01

    The facilities of reactor auxiliary systems for the advanced thermal prtotype reactor ''Fugen'' were manufactured in factories since 1972, and the installation at the site began in November, 1974. It was almost completed in March, 1977, except a part of the tests and inspections, therefore the outline of the works is reported. The ATR ''Fugen'' is a heavy water-moderated, boiling light water reactor, and its reactor auxiliary systems comprise mainly the facilities for handling heavy water, such as heavy water cooling system, heavy water cleaning system, poison supplying system, helium circulating system, helium cleaning system, and carbon dioxide system. The poison supplying system supplies liquid poison to the heavy water cooling system to absorb excess reactivity in the initial reactor core. The helium circulating system covers heavy water surface with helium to prevent the deterioration of heavy water and maintains heavy water level by pressure difference. The carbon dioxide system flows highly pure CO 2 gas in the space of pressure tubes and carandria tubes, and provides thermal shielding. The design, manufacture and installation of the facilities of reactor auxiliary systems, and the helium leak test, synthetic pressure test and total cleaning are explained. (Kako, I.)

  2. QLab 3 show control projects for live performances & installations

    CERN Document Server

    Hopgood, Jeromy

    2013-01-01

    Used from Broadway to Britain's West End, QLab software is the tool of choice for many of the world's most prominent sound, projection, and integrated media designers. QLab 3 Show Control: Projects for Live Performances & Installations is a project-based book on QLab software covering sound, video, and show control. With information on both sound and video system basics and the more advanced functions of QLab such as MIDI show control, new OSC capabilities, networking, video effects, and microphone integration, each chapter's specific projects will allow you to learn the software's capabilitie

  3. The decommissioning of nuclear facilities; Le demantelement des installations nucleaires de base

    Energy Technology Data Exchange (ETDEWEB)

    Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R

    2008-11-15

    This file includes five parts: the first part is devoted to the strategies of the different operators and includes the following files: the decommissioning of nuclear facilities Asn point of view, decommissioning of secret nuclear facilities, decommissioning at the civil Cea strategy and programs, EDF de-construction strategy, Areva strategy for decommissioning of nuclear facilities; the second one concerns the stakes of dismantling and includes the articles as follow: complete cleanup of buildings structures in nuclear facilities, decommissioning of nuclear facilities and safety assessment, decommissioning wastes management issues, securing the financing of long-term decommissioning and waste management costs, organizational and human factors in decommissioning projects, training for the decommissioning professions: the example of the Grenoble University master degree; the third part is devoted to the management of dismantling work sites and includes the different articles as follow: decommissioning progress at S.I.C.N. plant, example of decommissioning work site in Cea Grenoble: Siloette reactor decommissioning, matters related to decommissioning sites, decommissioning of french nuclear installations: the viewpoint of a specialist company, specificities of inspections during decommissioning: the Asn inspector point of view; the fourth part is in relation with the international approach and includes as follow: IAEA role in establishing a global safety regime on decommissioning, towards harmonization of nuclear safety practices in Europe: W.E.N.R.A. and the decommissioning of nuclear facilities, EPA superfund program policy for decontamination and decommissioning, progress with remediation at Sellafield, progress and experiences from the decommissioning of the Eurochemic reprocessing plant in Belgium, activities of I.R.S.N. and its daughter company Risk-audit I.r.s.n./G.r.s. international in the field of decommissioning of nuclear facilities in eastern countries

  4. Air pollution control at a DOE facility

    International Nuclear Information System (INIS)

    Curn, B.L.

    1995-11-01

    The Department of Energy (DOE) plutonium production program Produced some of the greatest scientific and engineering accomplishments of all time. It is remarkable to consider the accomplishments of the Manhattan Project. The Reactor on the Hanford Site, the first production reactor in the world, began operation only 13 months after the start of construction. The DOE nuclear production program was also instrumental in pioneering other fields such as health physics an radiation monitoring. The safety record of these installations is remarkable considering that virtually every significant accomplishment was on the technological threshold of the time. One other area that the DOE Facilities pioneered was the control of radioactive particles and gases emitted to the atmosphere. The high efficiency particulate air filter (HEPA) was a development that provided high collection efficiencies of particulates to protect workers and the public. The halogen and noble gases also were of particular concern. Radioactive iodine is captured by adsorption on activated carbon or synthetic zeolites. Besides controlling radioncuclide air pollution, DOE facilities are concerned with other criteria pollutants and hazardous air pollutant emissions. The Hanford Site encompasses all those air pollution challenges

  5. Technical review and evaluation for the installation of cold neutron source facility at HANARO

    International Nuclear Information System (INIS)

    Choi, Chang Woong; Kim, Dong Hoon; Lee, Mu Woong; Cho, Man Soon; Oh, Yun Woo; Park, Sun Hee; Park, Kuk Nam; Lee, Chang Hee

    1996-01-01

    The principle subjects of this study are to analyze the technical characteristics of cold neutron source(CNS) and take measures to cope with the matters regarding the installation of CNS facility at HANARO. This report, thus, reviews the current status of the CNS facilities that are now in operation worldwide and classifies the system and equipment to select the appropriate type for HANARO and provides advice and guidance for the future basic and detail design. As we have none of CNS facility here and very few experienced persons yet, this report provides some information for domestic users through the investigation of the utilization fields and experimental facilities of CNS, and presents the estimated total cost for the project based on JRR-3M. In addition, the work scope of the conceptual design, which will be performed in advance of the basic and detail design, and cooperative program with the countries having the advanced technology of CNS is presented in this report. 43 tabs., 57 figs., 22 refs. (Author)

  6. Designing and constructing/installing technical security countermeasures (TSCM) into supersensitive facilities

    International Nuclear Information System (INIS)

    Davis, D.L.

    1988-01-01

    The design and construction of supersensitive facilities and the installation of systems secure from technical surveillance and sabotage penetration involve ''TSCM'' in the broad sense of technical ''security'' countermeasures. When the technical threat was at a lower level of intensity and sophistication, it was common practice to defer TSCM to the future facility occupant. However, the New Moscow Embassy experience has proven this course of action subject to peril. Although primary concern with the embassy was audio surveillance, elsewhere there are other threats of equal or greater concern, e.g., technical implants may be used to monitor readiness status or interfere with the operation of C3I and weapons systems. Present and future technical penetration threats stretch the imagination. The Soviets have committed substantial hard scientific resources to a broad range of technical intelligence, even including applications or parapsychology. Countering these threats involves continuous TSCM precautions from initial planning to completion. Designs and construction/installation techniques must facilitate technical inspections and preclude the broadest range of known and suspected technical penetration efforts

  7. Designing and constructing/installing technical security countermeasures (TSCM) into supersensitive facilities

    Energy Technology Data Exchange (ETDEWEB)

    Davis, D.L.

    1988-01-01

    The design and construction of supersensitive facilities and the installation of systems secure from technical surveillance and sabotage penetration involve ''TSCM'' in the broad sense of technical ''security'' countermeasures. When the technical threat was at a lower level of intensity and sophistication, it was common practice to defer TSCM to the future facility occupant. However, the New Moscow Embassy experience has proven this course of action subject to peril. Although primary concern with the embassy was audio surveillance, elsewhere there are other threats of equal or greater concern, e.g., technical implants may be used to monitor readiness status or interfere with the operation of C3I and weapons systems. Present and future technical penetration threats stretch the imagination. The Soviets have committed substantial hard scientific resources to a broad range of technical intelligence, even including applications or parapsychology. Countering these threats involves continuous TSCM precautions from initial planning to completion. Designs and construction/installation techniques must facilitate technical inspections and preclude the broadest range of known and suspected technical penetration efforts.

  8. Monitoring commercial conventional facilities control with the APS control system: The Metasys-to-EPICS interface

    International Nuclear Information System (INIS)

    Nawrocki, G.J.; Seaver, C.L.; Kowalkowski, J.B.

    1995-01-01

    As controls needs at the Advanced Photon Source matured from an installation phase to an operational phase, the need to monitor the existing conventional facilities control system with the EPICS-based accelerator control system was realized. This existing conventional facilities control network is based on a proprietary system from Johnson Controls called Metasys. Initially read-only monitoring of the Metasys parameters will be provided; however, the ability for possible future expansion to full control is available. This paper describes a method of using commercially available hardware and existing EPICS software as a bridge between the Metasys and EPICS control systems

  9. Release of radioisotopes and activated materials from nuclear installations and facilities

    International Nuclear Information System (INIS)

    Manfredi, P.F.; Millaud, J. E.

    2001-01-01

    This report discusses the problems of release of items from facilities and installations where radiation-based activities have been carried out. Several situations are reviewed and their release problems are discussed in detail. Particular attention is devoted to the assessment of the activity of the items to be released. A correct assessment of the activity will help the decision about the final use of the items removed from the radiation-related facility, either re-use, entering the public market, recycling, disposal and storage under different procedures. Even the final destination of the building which hosted the facility needs to be decided on the basis of an accurate assessment of the residual activity. The assessment of the activity, besides being fundamental in guaranteeing a safe approach to the procedures related to the release may result in a substantial profit. This is the case of items whose level of activity is so low that they can be put on the public market, reused or recycled for final product subject to very stringent radiation safety requirements. It will be shown that detector techniques play a fundamental role in the release process. In particular, the low-level counting techniques are fundamental in establishing whether or not the unrestrained release is feasible or not

  10. Control of occupational exposure in nuclear facilities for terrestrial support to marine vessels

    International Nuclear Information System (INIS)

    Lara, E.G.; Pinheiro, A.R.M.; Borsoi, S.S.; Silva, T.P.; Baroni, D.B.; Santos, F.C.

    2017-01-01

    This study addresses some basic requirements for exposure control of occupational exposure during the design phase of ground-based nuclear facilities for marine vessels. US regulatory guidelines, CNEN standards and experiences acquired in conventional nuclear installations were used. The installation design should consider the provision of mobile devices for monitoring and decontamination. Finally, it is observed that the establishment of additional exposure control criteria can directly impact the civil, architectural and electromechanical projects of the facility, from the conceptual phase

  11. 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)

  12. eHXI: a permanently installed, hard x-ray imager for the National Ignition Facility

    International Nuclear Information System (INIS)

    Döppner, T.; Bachmann, B.; Albert, F.; Bell, P.; Burns, S.; Celeste, J.; Chow, R.; Divol, L.; Dewald, E.L.; Huntington, C.M.; Izumi, N.; LaCaille, G.; Landen, O.L.; Palmer, N.; Park, H.-S.; Thomas, C.A.; Hohenberger, M.

    2016-01-01

    We have designed and built a multi-pinhole imaging system for high energy x-rays (≥ 50 keV) that is permanently installed in the equatorial plane outside of the target chamber at the National Ignition Facility (NIF). It records absolutely-calibrated, time-integrated x-ray images with the same line-of-sight as the multi-channel, spatially integrating hard x-ray detector FFLEX [McDonald et al., Rev. Sci. Instrum. 75 (2004) 3753], having a side view of indirect-drive inertial confinement fusion (ICF) implosion targets. The equatorial hard x-ray imager (eHXI) has recorded images on the majority of ICF implosion experiments since May 2011. eHXI provides valuable information on hot electron distribution in hohlraum experiments, target alignment, potential hohlraum drive asymmetries and serves as a long term reference for the FFLEX diagnostics.

  13. Installation places of criticality accident detectors in the plutonium conversion development facility

    International Nuclear Information System (INIS)

    Sanada, Yukihisa; Tsujimura, Norio; Shimizu, Yoshio; Izaki, Kenji; Furuta, Sadaaki

    2008-01-01

    At the Plutonium Conversion Development Facility (PCDF) in the Nuclear Fuel Cycle Engineering Laboratories, the co-conversion technologies to purify the mixed plutonium and uranium nitrate solution discharged from a reprocessing plant have been developed. The probability of a criticality accident in PCDF is extremely low. However, the criticality accident alarm system (CAAS) has been in place since 1982 to reduce the radiation dose to workers in case of such a rare criticality accident. The CAAS contains criticality accident detector units (CADs), one unit consisting of three plastic scintillation detectors, and using the 2 out of 3 voting system for the purpose of high reliability. Currently, eight CADs are installed in PCDF evaluating the dose using a simple equation allowing for a safety margin. The purpose of this study is to show the determination procedures for the adequate relocation of the CADs which adequately ensures safety in PCDF. (author)

  14. Simulation of closed loop controlled boost converter for solar installation

    Directory of Open Access Journals (Sweden)

    Kalirasu Athimulam

    2010-01-01

    Full Text Available With the shortage of the energy and ever increasing of the oil price, research on the renewable and green energy sources, especially the solar arrays and the fuel cells, becomes more and more important. How to achieve high stepup and high efficiency DC/DC converters is the major consideration in the renewable power applications due to the low voltage of PV arrays and fuel cells. In this paper digital simulation of closed loop controlled boost converter for solar installation is presented. Circuit models for open loop and closed loop controlled systems are developed using the blocks of simulink. The simulation results are compared with the theoretical results. This converter has advantages like improved power factor, fast response and reduced hardware. .

  15. Modernization Of Electrical Installation By Using Wireless Remote Control

    Directory of Open Access Journals (Sweden)

    Mawlood M Al – Hamad

    2013-05-01

    Full Text Available Great benefits can be achieved by using wireless remote control in electrical wiring systems of buildings.     Probably the main advantage of this application is the drastic saving in wiring installations, which in turn will give higher reliability, safety and economy.     The idea of this application can be summarized in the following explanation. '' Instead off connecting each point of electrical system to individual switch by wires, a remote receiver can be situated in a place near to the point. The transmitter is used to operate the point remotely. The mains are connected to the receiver which will connect or disconnect the load as required. Many points can be connected to one receiver and can be operated by one or more transmitter.

  16. Performance confirmation operation of water environment control facility

    International Nuclear Information System (INIS)

    Magome, Hirokatsu; Okada, Yuji; Tomita, Kenji; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Hanawa, Hiroshi; Kanno, Masaru; Sakuta, Yoshiyuki

    2015-09-01

    In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. The material irradiation test facility is used for IASCC study, and consists of mainly three equipments. This report described performance operating test of the water environmental control facilities for IASCC study carried out 2013 fiscal year. (author)

  17. Cabin fuselage structural design with engine installation and control system

    Science.gov (United States)

    Balakrishnan, Tanapaal; Bishop, Mike; Gumus, Ilker; Gussy, Joel; Triggs, Mike

    1994-01-01

    Design requirements for the cabin, cabin system, flight controls, engine installation, and wing-fuselage interface that provide adequate interior volume for occupant seating, cabin ingress and egress, and safety are presented. The fuselage structure must be sufficient to meet the loadings specified in the appropriate sections of Federal Aviation Regulation Part 23. The critical structure must provide a safe life of 10(exp 6) load cycles and 10,000 operational mission cycles. The cabin seating and controls must provide adjustment to account for various pilot physiques and to aid in maintenance and operation of the aircraft. Seats and doors shall not bind or lockup under normal operation. Cabin systems such as heating and ventilation, electrical, lighting, intercom, and avionics must be included in the design. The control system will consist of ailerons, elevator, and rudders. The system must provide required deflections with a combination of push rods, bell cranks, pulleys, and linkages. The system will be free from slack and provide smooth operation without binding. Environmental considerations include variations in temperature and atmospheric pressure, protection against sand, dust, rain, humidity, ice, snow, salt/fog atmosphere, wind and gusts, and shock and vibration. The following design goals were set to meet the requirements of the statement of work: safety, performance, manufacturing and cost. To prevent the engine from penetrating the passenger area in the event of a crash was the primary safety concern. Weight and the fuselage aerodynamics were the primary performance concerns. Commonality and ease of manufacturing were major considerations to reduce cost.

  18. Installation of the water environment irradiation facility for the IASCC research under the BWR irradiation environment (1)

    International Nuclear Information System (INIS)

    Okada, Yuji; Magome, Hirokatsu; Hanawa, Hiroshi; Ohmi, Masao; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Shibata, Mitsunobu; Yonekawa, Akihisa; Ueda, Haruyasu

    2013-10-01

    In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material is advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. This material irradiation test facility and power ramping test facility for doing the neutron irradiation test of the fuel and material for light water reactors is scheduled to be manufactured and installed between the 2008 fiscal year and the 2012 fiscal year. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from the 2008 fiscal year to the 2010 fiscal year. (author)

  19. Control system considerations for the AHF [Advanced Hadron Facility

    International Nuclear Information System (INIS)

    Butler, H.S.

    1989-01-01

    This paper identifies some of the more important issues related to the design of a control system for the Advanced Hadron Facility (AHF). It begins with a brief description of the site layout and how the various accelerators operate in tandem to deliver beam to several experimental areas. Then it focuses on the control system by estimating from existing installations the number of data and control channels to be expected for the AHF. The total comes to 50,000. This channel count is converted to manpower and cost estimates for the control system by extrapolating from other accelerator facilities. Finally, special attention is given to two subsystems -- magnets and diagnostic equipment -- and the impact they will have on the control system. 11 refs., 5 figs., 6 tabs

  20. Safety analysis report for the cold vacuum drying facility, phase 2, supporting installation of process systems

    International Nuclear Information System (INIS)

    Pili-Vincens, C.

    1998-01-01

    SNF Project emergencies span the spectrum of identified emergencies for SNF Project facilities, from worker injury to general emergencies with potential public impact. Facility events include fire and/or explosion, radioactive material release, chlorine gas release, hazardous material release, loss of water in the fuel basins, and loss of electrical power. Natural events include seismic events, high winds, range fires, flooding, lightning strikes, tornado, and an aircraft crash. Security contingencies include bomb threat and/or explosive device, sabotage, and hostage situation and/or armed intruder as described in DOE/RL-94-02 (DOE 1997 b). This Chapter 15.0 applies to all operations, facilities, and personnel, including subcontractors, vendors, visitors, and any non-contractor tenants in SNF Project-controlled facilities. The EPP addresses both individual and organizational graded responses to the spectrum of emergencies, which includes hypothetical accidents with very low occurrence frequencies. The planning, accomplished in the EPP and the BEPs, provides the response actions for these emergencies. This chapter links the SNF Project EPP to DOE/RL-94-02 (DOE 1997 b), which provides the link to subsequent state and local off site EPPs. Integration of these programs links potential onsite events with onsite and offsite impacts. This integration assists in mitigation and recovery and provides for protection of the health and safety of the workers, the public, and the environment

  1. First 10 kg of naked Germanium detectors in liquid nitrogen installed in the GENIUS-Test-Facility

    International Nuclear Information System (INIS)

    Klapdor-Kleingrothaus, H.V.; Chkvorets, O.; Krivosheina, I.V.; Strecker, H.; Tomei, C.

    2003-01-01

    The first four naked high-purity Germanium detectors were installed successfully in liquid nitrogen in the GENIUS-Test-Facility in the GRAN SASSO Underground Laboratory on May 5, 2003. This is the first time ever that this novel technique aiming at extreme background reduction in search for rare decays is going to be tested underground. First operational parameters are presented

  2. Preliminary assessment report for Redmond Army National Guard Facility, Installation 53120, Redmond, Washington

    International Nuclear Information System (INIS)

    Ketels, P.; Aggarwal, P.

    1993-08-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Washington Army National Guard (WAARNG) property in Redmond, Washington. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the Redmond ARNG property, Phase I of the Department of Defense Installation Restoration Program. The environmentally significant operations (ESOs) associated with the property are (1) supply/storage of hazardous materials, (2) weapons cleaning, (3) the underground storage tanks (USTs), and (4) the use of herbicides. These ESOs are no longer active because of the closure of OMS 10 activities in 1988

  3. Experimental engineering section off-gas decontamination facility's fractionator column: installation and performance

    International Nuclear Information System (INIS)

    Gilliam, T.M.; Fowler, V.L.; Inman, D.J.

    1978-03-01

    A detailed description of the third column recently installed in the Experimental Engineering Section Off-Gas Decontamination Facility (EES-ODF) is presented. The EES-ODF is being used to provide engineering-scale experiments (nominal gas and liquid flows of 5 scfm and 0.5 gpm, respectively) in the development of the Krypton Absorption in Liquid CO 2 (KALC) process. A detailed discussion of the column's construction is provided. This discussion includes the peripherals associated with the column, such as refrigeration, heat exchangers, instrumentation, etc. The compressibility of Goodloe packing (the packing in the other columns) and the possible reduced throughput due to this compression have revealed the desirablility of a random (i.e., noncompressible) packing. Toward this end, the third column is packed with a new random packing (PRO-PAK). A preliminary comparison between this packing and the woven wire mesh packing (Goodloe) used in the other two columns has been made. Experiments comparing the throughput capacity indicate that the PRO-PAK packing has approximately 60% the capacity of Goodloe for a CO 2 system. When used as a fractionator or stripper with the basic O 2 -Kr-CO 2 KALC system, the PRO-PAK column produced HTU values less than or equal to the GOODLOE columns under similar operating conditions

  4. Regulatory system for control of nuclear facilities in Bangladesh

    International Nuclear Information System (INIS)

    Mollah, A.S.

    2005-01-01

    All human activities have associated risks. Nuclear programme is no exception. The Bangladesh Atomic Energy Commission (BAEC), constituted in February 1973 through the promulgation of the Presidential order 15 of 1973. Functions of BAEC include research and development in peaceful application of atomic energy, generation of electricity and promotion of international relations congenial to implementation of its programmes and projects. In 1993 the Government of Bangladesh promulgated the law on Nuclear Safety and Radiation Control. Considering the human resources, expertise and facilities needed for implementation of the provisions of the NSRC law, BAEC was entrusted with the responsibility to enforce it. The responsibilities of the BAEC cover nuclear and radiological safety within the installations of BAEC and radiological safety in the manifold applications of radioisotopes and radiation sources within the country. An adequate and competent infrastructure has been built to cater to the diverse nuclear and radiation protection requirements of all nuclear facilities in Bangladesh, arising at different stages from site selection to day-to-day operation. In addition, periodic inspections of the nuclear facilities are carried out. The licensing and regulatory inspection systems for controlling of nuclear installations and radiation sources are established. The paper describes the legal provisions, responsibilities and organization of BAEC with special emphasis on nuclear safety and radiation protection of nuclear facilities in Bangladesh. (author)

  5. Evaluation of the impact and the releases of operating nuclear facilities; Evaluation de l'impact et des rejets des installations nucleaires en fonctionnement normal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The monitoring of nuclear installations releases, the associated impacts evaluation and the radiation monitoring of the environment are of an increase interest since the last ten years. Theses two days, organized by the environment section of the SFRP (French Society of Radiation Protection), aim to discuss the following topics: the development of the methods to improve radioactive elements and toxic substances releases in the environment; the structure of the environment control and the objectives of this control; the association of the local actors to the releases monitoring and to the environment control; the perspectives of evolution in matter of nuclear facilities releases management. (A.L.B.)

  6. Installation of the water environment irradiation facility for the IASCC research under the BWR/PWR irradiation environment (2)

    International Nuclear Information System (INIS)

    Magome, Hirokatsu; Okada, Yuji; Hanawa, Hiroshi; Sakuta, Yoshiyuki; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Shibata, Mitsunobu

    2014-07-01

    In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from 2012 to 2014 in the follow-up report reported before (JAEA-Technology 2013-019). (author)

  7. The Field Lysimeter Test Facility (FLTF) at the Hanford Site: Installation and initial tests

    International Nuclear Information System (INIS)

    Gee, G.W.; Kirkham, R.R.; Downs, J.L.; Campbell, M.D.

    1989-02-01

    The objectives of this program are to test barrier design concepts and to demonstrate a barrier design that meets established performance criteria for use in isolating wastes disposed of near-surface at the Hanford Site. Specifically, the program is designed to assess how well the barriers perform in controlling biointrusion, water infiltration, and erosion, as well as evaluating interactions between environmental variables and design factors of the barriers. To assess barrier performance and design with respect to infiltration control, field lysimeters and small- and large-scale field plots are planned to test the performance of specific barrier designs under actual and modified (enhanced precipitation) climatic conditions. The Field Lysimeter Test Facility (FLTF) is located in the 600 Area of the Hanford Site just east of the 200 West Area and adjacent to the Hanford Meteorological Station. The FLTF data will be used to assess the effectiveness of selected protective barrier configurations in controlling water infiltration. The facility consists of 14 drainage lysimeters (2 m dia x 3 m deep) and four precision weighing lysimeters (1.5 m x 1.5 m x 1.7 m deep). The lysimeters are buried at grade and aligned in a parallel configuration, with nine lysimeters on each side of an underground instrument chamber. The lysimeters were filled with materials to simulate a multilayer protective barrier system. Data gathered from the FLTF will be used to compare key barrier components and to calibrate and test models for predicting long-term barrier performance

  8. Cost Control Guide For Decommissioning Of Nuclear Installations

    International Nuclear Information System (INIS)

    2013-01-01

    This cost control guide was prepared in response to the request from the OECD/NEA Working Party on Decommissioning and Dismantling (WPDD) - Decommissioning Cost Estimation Group (DCEG) to offer the industry guidance in preparing and implementing cost and schedule controls during decommissioning. The DCEG sent out a survey questionnaire in 2010 soliciting comments from OECD member states on their use of cost controls during decommissioning. While the response was limited, the consensus was to proceed with the preparation of this guide. Cost and schedule control systems have been in use for more than 30 years, and in the last 10 years or so have evolved into a more formalised earned value management system (EVMS). This guide is based on the internationally recognised standard, Earned Value Management Systems (ANSI, 2007). The EVMS is built on a work breakdown structure (WBS) of decommissioning activities, and a defined process for controlling a project. The EVMS not only provides measurement of project status and future performance, but also builds a structure and culture for accountability on project performance. This guide describes the performance metrics used to determine the value earned based on what was planned to be done, what was actually accomplished and what it actually cost. Variances measured monthly at a minimum indicate where potential problems are arising and raise a flag for the project manager to implement corrective actions for the next reporting period. The success of the EVMS programme depends on management commitment to implement a culture change for its employees, and to impose the EVMS on potential future contractors performing decommissioning work at a facility. Formal training is required to ensure all elements of the process are understood and put into action. It is recommended to begin with a small project, and graduate to larger projects as the staff learns how to use the system. The EVMS process has been used internationally for small

  9. Advanced Control Test Operation (ACTO) facility

    International Nuclear Information System (INIS)

    Ball, S.J.

    1987-01-01

    The Advanced Control Test Operation (ACTO) project, sponsored by the US Department of Energy (DOE), is being developed to enable the latest modern technology, automation, and advanced control methods to be incorporated into nuclear power plants. The facility is proposed as a national multi-user center for advanced control development and testing to be completed in 1991. The facility will support a wide variety of reactor concepts, and will be used by researchers from Oak Ridge National Laboratory (ORNL), plus scientists and engineers from industry, other national laboratories, universities, and utilities. ACTO will also include telecommunication facilities for remote users

  10. 30 CFR 285.700 - What reports must I submit to MMS before installing facilities described in my approved SAP, COP...

    Science.gov (United States)

    2010-07-01

    ... installing facilities described in my approved SAP, COP, or GAP? 285.700 Section 285.700 Mineral Resources... § 285.700 What reports must I submit to MMS before installing facilities described in my approved SAP... in your approved COP (§ 285.632(a)) and, when required by this part, your SAP (§ 285.614(b)) or GAP...

  11. Technical Cybersecurity Controls for Nuclear Facilities

    International Nuclear Information System (INIS)

    Oh, Jinseok; Ryou, Jaecheol; Kim, Youngmi; Jeong, Choonghei

    2014-01-01

    To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility

  12. Technical Cybersecurity Controls for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Jinseok; Ryou, Jaecheol [Chungnam National Univ., Daejeon (Korea, Republic of); Kim, Youngmi; Jeong, Choonghei [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-05-15

    To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility.

  13. Quality control of conventional radiographic facilities in Kinshasa

    International Nuclear Information System (INIS)

    Woto, M.L.; Lukanda, M.V.; Mulumba, L.C.P.; Palangu

    2009-01-01

    The continuous development of medical applications of ionizing radiation, due to the benefit derived by diagnostic or therapeutic patients, their diversity, ease of implementation, explains the importance of medical exposure. The latter is currently the leading cause of human exposure to artificial origin. The purpose of this study is to contribute to the optimization of radiographic facilities in the city of Kinshasa. This study has revealed that city of Kinshasa has an average of 122 medical training with conventional radiology facilities distributed in six districts of health. Of the 122 facilities, only 30 (or 24.59%) are controlled from the point of view of quality assurance. Some generators and X-ray tubes are respectively controlled adjustment and de centered, and other devices are cannibalized. So, nationally and particularly in Kinshasa, quality control equipment and diagnostic facilities is at a generally delayed compared with international recommendations of X W. Major efforts must be made at government level to raise awareness and establish a quality assurance program in diagnostic radiology. An awareness of the entire medical profession and the competent administrative authorities of medical devices could be beneficial to the quality of care delivered to patients, limiting radiation exposure and improving image quality and only the financial balance of the health sector. The delivery of quality care passes through the justification of acts, the development and dissemination of good practice references and the establishment of quality control radiological installations.

  14. The effect of cleanliness control during installation work on the amount of accumulated dust in ducts of new HVAC installations.

    Science.gov (United States)

    Holopainen, R; Tuomainen, M; Asikainen, V; Pasanen, P; Säteri, J; Seppänen, O

    2002-09-01

    The aim of this study was to evaluate the amount of dust in supply air ducts in recently installed ventilation systems. The samples for the determination of dust accumulation were collected from supply air ducts in 18 new buildings that have been constructed according to two different cleanliness control levels classified as category P1 (low oil residues and protected against contaminations) and category P2, as defined in the Classification of Indoor Climate, Construction and Building Materials. In the ducts installed according to the requirements of cleanliness category P1 the mean amount of accumulated dust was 0.9 g/m2 (0.4-2.9 g/m2), and in the ducts installed according to the cleanliness category P2 it was 2.3 g/m2 (1.2-4.9 g/m2). A significant difference was found in the mean amounts of dust between ducts of categories P1 and P2 (P < 0.008). The cleanliness control procedure in category P1 proved to be a useful and effective tool for preventing dust accumulation in new air ducts during the construction process. Additionally, the ducts without residual oil had lower amounts of accumulated dust indicating that the demand for oil free components in the cleanliness classification is reasonable.

  15. Use of the TACL [Thaumaturgic Automated Control Logic] system at CEBAF [Continuous Electron Beam Accelerator Facility] for control of the Cryogenic Test Facility

    International Nuclear Information System (INIS)

    Navarro, E.; Keesee, M.; Bork, R.; Grubb, C.; Lahti, G.; Sage, J.

    1989-01-01

    A logic-based control software system, called Thaumaturgic Automated Control Logic (TACL), is under development at the Continuous Electron Beam Accelerator Facility in Newport News, VA. The first version of the software was placed in service in November, 1987 for control of cryogenics during the first superconducting RF cavity tests at CEBAF. In August, 1988 the control system was installed at the Cryogenic Test Facility (CTF) at CEBAF. CTF generated liquid helium in September, 1988 and is now in full operation for the current round of cavity tests. TACL is providing a powerful and flexible controls environment for the operation of CTF. 3 refs

  16. 14 CFR Appendix I to Part 25 - Installation of an Automatic Takeoff Thrust Control System (ATTCS)

    Science.gov (United States)

    2010-01-01

    ... Appendix I to Part 25—Installation of an Automatic Takeoff Thrust Control System (ATTCS) I25.1General. (a... crew to increase thrust or power. I25.2Definitions. (a) Automatic Takeoff Thrust Control System (ATTCS... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Installation of an Automatic Takeoff Thrust...

  17. The BNL Accelerator Test Facility control system

    International Nuclear Information System (INIS)

    Malone, R.; Bottke, I.; Fernow, R.; Ben-Zvi, I.

    1993-01-01

    Described is the VAX/CAMAC-based control system for Brookhaven National Laboratory's Accelerator Test Facility, a laser/linac research complex. Details of hardware and software configurations are presented along with experiences of using Vsystem, a commercial control system package

  18. Status of safety at Areva group facilities. 2006 annual report; Etat de surete des installations nucleaires. Rapport annuel 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This report presents a snapshot of nuclear safety and radiation protection conditions in the AREVA group's nuclear installations in France and abroad, as well as of radiation protection aspects in service activities, as identified over the course of the annual inspections and analyses program carried out by the General Inspectorate in 2006. This report is presented to the AREVA Supervisory Board, communicated to the labor representation bodies concerned, and made public. In light of the inspections, appraisals and coordination missions it has performed, the General Inspectorate considers that the nuclear safety level of the AREVA group's nuclear installations is satisfactory. It particularly noted positive changes on numerous sites and efforts in the field of continuous improvement that have helped to strengthen nuclear safety. This has been possible through the full involvement of management teams, an improvement effort initiated by upper management, actions to increase personnel awareness of nuclear safety culture, and supervisors' heightened presence around operators. However, the occurrence of certain events in facilities has led us to question the nuclear safety repercussions that the changes to activities or organization on some sites have had. In these times of change, drifts in nuclear safety culture have been identified. The General Inspectorate considers that a preliminary analysis of the human and organizational factors of these changes, sized to match the impact the change has on nuclear safety, should be made to ensure that a guaranteed level of nuclear safety is maintained (allowance for changes to references, availability of the necessary skills, resources of the operating and support structures, etc.). Preparations should also be made to monitor the changes and spot any telltale signs of drift in the application phase. Managers should be extra vigilant and the occurrence of any drift should be systematically dealt with ahead of

  19. Nuclear ventilation installations. Method of control of the scrubbing coefficient of iodine trap

    International Nuclear Information System (INIS)

    1982-12-01

    The present standard aims at defining a method to control the scrubbing coefficient of radioactive iodine trapping systems, used in nuclear ventilation installations. It applies to the installations where the trapping, efficiency of radioactive iodine has to be known, tested and compared to a reference value generally included in the safety reports. It applies to the installations where the absolute pressure of the air in the ventilation systems is above 1,4. 10 5 Pa (1,4 Bar) [fr

  20. C-188 Co-60 sources installation and source rack loading optimization processes in a gamma irradiation facility

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Paulo de S.; Vasquez, Pablo A.S., E-mail: psantos@ipen.br, E-mail: pavsalva@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2017-11-01

    Since 2004, the Multipurpose Gamma Facility at the Nuclear and Energy Research Institute has been providing services on radiation processing for disinfection and sterilization of health care and disposable medical products as well to support research studies on modification of physical, chemical and biological properties of several materials. Recently, there was an increment in irradiation of the Cultural Heritages. This facility uses C-188 double-encapsulated radioactive Cobalt-60 sources known as pencils from manufactures outside of country. The activity of the cobalt sources decays into a stable nickel isotope with a half-life around 5.27 years, which means a loss of 12.3% annually. Then, additional pencils of Cobalt-60 are added periodically to the source rack to maintain the required capacity or installed activity of the facility. The manufacturer makes shipping of the radioactive sources inside a high density container type B(U) , by sea. This one involves many administrative, transport and radiation safety procedures. Once in the facility, the container is opened inside a deep pool water to remove the pencils. The required source geometry of the facility is obtained by loading these source pencils into predetermined diagram or positions in source modules and distributing these modules over the source rack of the facility. The dose variation can be reduced placing the higher activity source pencils near the periphery of the source rack. In this work are presented the procedures for perform the boiling leaching tests applied to the container, the Cobalt-60 sources installation, the loading processes and the source rack loading optimization. (author)

  1. Design, fabrication and installation of irradiation facilities -Advanced nuclear material development-

    International Nuclear Information System (INIS)

    Kim, Yong Seong; Lee, Jeong Yeong; Lee, Seong Ho; Ji, Dae Yeong; Kim, Seok Hoon; An, Seong Ho; Kim, Dong Hoon; Seok, Ho Cheon; Kim, Joon Yeon; Yang, Seong Hong

    1994-07-01

    The objective of this study is to design and construct the steady state fuel test loop and non-instrumented capsules to be installed in KMRR. The principle contents of this project are to design, fabricate the steady-state fuel test loop and non-instrumented capsule to be installed in KMRR for nuclear technology development. This project will be completed in 1996, so preparation of design criteria for fuel test loop have been performed in 1993 as the first year of the first phase in implementing this project. Also design and pressure drop test of non-instrumented capsule have been performed in 1993

  2. The suitability and installation of technological equipment when upgrading existing facilities

    Directory of Open Access Journals (Sweden)

    Ladnushkin A. A.

    2016-03-01

    Full Text Available to date, a large number of Russian companies in diverse and various industries, has old equipment and requires modernization of the technological process due to the growth of scientific and technological progress. In order to achieve goals when upgrading is considered such an important aspect as the readiness of the new equipment installation. Mounting hardware suitability describes the suitability and readiness of equipment for efficient Assembly at the user. Replacement of technological equipment requires large volumes of works on installation and dismantling, in the absence of the building has its own lifting mechanisms require large financial and labor costs. One of possible methods for replacement of process equipment is the technology of without crane installation allows us to carry out work in existing space planning. Today is the question of the necessity of development and introduction of new technological production methods and fixtures tooling in which it is possible to conduct installation and dismantling of technological equipment in the operating production process.

  3. Environmental Monitoring, Water Quality - Water Pollution Control Facilities

    Data.gov (United States)

    NSGIC Education | GIS Inventory — A Water Pollution Control Facility is a DEP primary facility type related to the Water Pollution Control Program. The sub-facility types related to Water Pollution...

  4. The Study on quality control of nuclear power installation project

    International Nuclear Information System (INIS)

    Wu Jie

    2008-01-01

    The quality planning, quality assurance and quality control are discussed by applying the quality control (QC) theory and combining the real situation of the Qinshan II project. This paper is practical and plays an active role in instruction of project quality control by applying the above QC theory and control techniques. (authors)

  5. Method for installing a control rod driving device in a reactor

    International Nuclear Information System (INIS)

    Sato, Haruo; Watanabe, Masatoshi.

    1975-01-01

    Object: To install a device using a wire rope, including individually moving up and down a control rod and a control rod driving device thereby enabling to install them within a low house and to reduce time required for installing operation. Structure: The control rod is temporarily attached to a support structure for the control rod driving device, the control rod driving device is suspended on a crane positioned upwardly of the support structure, a rope connected to the control rod driving device is connected to the control rod, a sagged portion of the rope is then wound about a rotary cylinder, the control rod is disconnected from its temporary attachment, and the wound rope is wound back while the rotary cylinder is rotated to move down the control rod. After the rope has been released from the rotary cylinder, the control rod driving device is moved down by the crane. (Kamimura, M.)

  6. Accountability control system in plutonium fuel facility

    International Nuclear Information System (INIS)

    Naruki, Kaoru; Aoki, Minoru; Mizuno, Ohichi; Mishima, Tsuyoshi

    1979-01-01

    More than 30 tons of plutonium-uranium mixed-oxide fuel have been manufactured at the Plutonium Facility in PNC for JOYO, FUGEN and DCA (Deuterium Critical Assembly) and for the purpose of irradiation tests. This report reviews the nuclear material accountability control system adopted in the Plutonium Facility. Initially, the main objective of the system was the criticality control of fissible materials at various stages of fuel manufacturing. The first part of this report describes the functions and the structure of the control system. A flow chart is provided to show the various stages of material flow and their associated computer files. The system is composed of the following three sub-systems: procedures of nuclear material transfer; PIT (Physical Inventory Taking); data retrieval, report preparation and file maintenance. OMR (Optical Mark Reader) sheets are used to record the nuclear material transfer. The MUF (Materials Unaccounted For) are evaluated by PIT every three months through computer processing based on the OMR sheets. The MUF ratio of Pu handled in the facility every year from 1966 to 1977 are presented by a curve, indicating that the MUF ratio was kept well under 0.5% for every project (JOYO, FUGEN, and DCA). As for the Pu safeguards, the MBA (Material Balance Area) and the KMP (Key Measurement Point) in the facility of PNC are illustrated. The general idea of the projected PINC (Plutonium Inventory Control) system in PNC is also shortly explained. (Aoki, K.)

  7. Installation of a flow cytometry facility and some applications in radiobiology

    International Nuclear Information System (INIS)

    Walsh, M.; Kellington, J.P.

    1988-01-01

    Flow cytometry has enormous potential in many areas of experimental pathology. Details of the installation and commissioning of a flow cytometer at the Harwell Laboratory are described. Following an explanation of the principles of flow cytometry, several applications to specific problems in radiobiology are discussed. Also included are results of some preliminary studies with the Harwell flow cytometer on samples such as blood, bone marrow, macrophages and cell cultures, and a discussion of future applications. (author)

  8. A new gas stripper system for BARC-TIFR Pelletron Accelerator facility: installation and preliminary results

    International Nuclear Information System (INIS)

    Sharma, S.C.; Ninawe, N.G.; Yadav, M.L.; Ekambaram, M.; Ramjilal; Matkar, U.V.; Ansari, Q.N.; Lokare, R.N.; Ramlal; Gupta, A.K.; Bhagwat, P.V.; Pillay, R.G.

    2009-01-01

    The gas-stripper plays a key role in stripping the heavy and molecular ion beams in a tandem accelerator. Efficiency of gas stripper depends on its supporting vacuum pumps. A new recirculating turbo molecular pump-based gas stripper has been installed in the high voltage terminal of Pelletron Accelerator. Re-circulating the stripper gas reduces the flow of gas into the accelerating tubes reducing the transmission losses. Preliminary results obtained using the new gas stripper system are discussed. (author)

  9. Testing of the West Valley Vitrification Facility transfer cart control system

    International Nuclear Information System (INIS)

    Halliwell, J.W.; Bradley, E.C.

    1995-01-01

    Oak Ridge National Laboratory (ORNL) has designed and tested the control system for the West Valley Demonstration Project Vitrification Facility transfer cart. The transfer cart will transfer canisters of vitrified high-level waste remotely within the Vitrification Facility. The control system operates the cart under battery power by wireless control. The equipment includes cart-mounted control electronics, battery charger, control pendants, engineer's console, and facility antennas. Testing was performed in several phases of development: (1) prototype equipment was built and tested during design, (2) board-level testing was then performed at ORNL during fabrication, and (3) system-level testing was then performed by ORNL at the fabrication subcontractor's facility for the completed cart system. These tests verified (1) the performance of the cart relative to design requirements and (2) operation of various built-in cart features. The final phase of testing is planned to be conducted during installation at the West Valley Vitrification Facility

  10. Installing and detaching apparatus for a control rod drive mechanism

    International Nuclear Information System (INIS)

    Akimoto, Seiichi; Watanabe, Mitsuhiro; Yoshida, Tomiharu; Sugaya, Jun-ichi; Saito, Takashi.

    1976-01-01

    Object: To facilitate maintenance and repair of a control rod drive mechanism. Structure: The apparatus comprises a means moving in a moving direction of a control rod within a reactor vessel, said moving means having a housing mounted thereon, a means mounted on the reactor vessel to release a connection between a control rod drive mechanism connected to the control rod and the control rod, and a means for mounting and removing a fixing means which connects the reactor vessel to the control rod drive means. With this arrangement, cooling water of high radioactivity level may not be leaked outside to thereby notably reduce dangerousness of exposure and materially cut time required for mounting and removing the control rod drive mechanism. (Ohara, T.)

  11. Design/installation and structural integrity assessment under the Federal Facility Agreement for Bethel Valley Low-Level Waste Collection and Transfer System upgrade for Building 2026 (High Radiation Level Analytical Laboratory) and Building 2099 (Monitoring and Control Station) at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1994-10-01

    This document presents a Design/Installation and Structural Integrity Assessment for a replacement tank system for portions of the Bethel Valley Low Level Waste (LLW) System, located at the Oak Ridge Reservation, Oak Ridge, Tennessee. This issue of the assessment covers the design aspects of the replacement tank system, and certifies that the design has sufficient structural integrity and is acceptable for the storing or treating of hazardous and/or radioactive substances. The present issue identifies specific activities that must be completed during the fabrication, installation, and testing of the replacement tank system in order to provide assurance that the final installation complies with governing requirements. Portions of the LLW system are several decades old, or older, and do not comply with current environmental protection regulations. Several subsystems of the LLW system have been designated to receive a state-of-the-art replacement and refurbishment. One such subsystem serves Building 2026, the High Radiation Level Analytical Laboratory. This assessment focuses on the scope of work for the Building 2026 replacement LLW Collection and Transfer System, including the provision of a new Monitoring and Control Station (Building 2099) to receive, store, and treat (adjust pH) low level radioactive waste

  12. Generic description of facilities at the shaft head (auxiliary entrance installations) of deep geological repositories; Generische Beschreibung von Schachtkopfanlagen (Nebenzugangsanlagen) geologischer Tiefenlager

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-10-15

    In a deep geological repository, the access structures function as the link between the surface and the installations and structures at the disposal level. In the planned implementation scenarios, at least two access structures will be in operation up to the time of closure of the repository. The radioactive waste will be transported via the main access from the surface to the disposal level during emplacement operations. For the construction and operation of a deep geological repository, additional access structures are required. These auxiliary accesses and the associated surface infrastructure (e.g. shaft head installations) form the subject of this report. To provide as broad and comprehensive a description as possible, seven types of auxiliary access facilities are defined; these are characterised in line with the current status of planning and their functions and impacts are described. During construction, operation and dismantling of auxiliary access facilities, the usual conventional safety measures (inter alia) have to be observed (e.g. groundwater protection, fire prevention, facility security, accident prevention). Regarding the 'Ordinance on Protection against Major Accidents' no large quantities of hazardous materials, i.e. above the corresponding threshold quantities, are to be expected in the auxiliary access facilities. Proper handling and compliance with applicable regulations in all phases will ensure no hazard to humans and the environment. As no handling of radioactive materials is foreseen in the auxiliary access facilities, and because exhaust air and waste water from the controlled zones of a repository will, in principle, be removed via the main access and not the auxiliary accesses, a safety-relevant emission of radioactive substances and transport of contaminated material can be ruled out for the auxiliary access facilities during both normal operation and also in the case of an accident. Based on the information presented in

  13. NEW METHODS AND FACILITIES OF MAGNETIC CONTROL OF THE MECHANICAL CHARACTERISTICS OF ARTICLES

    Directory of Open Access Journals (Sweden)

    V. F. Matjuk

    2004-01-01

    Full Text Available There are given the results of development in the State scientific university ''Institute of applied physics of the National Academy of Sciences of Belarus” of the facilities for magnetic control of the steels mechanical characteristics - coercimeter KIPF-1, impulse magnetic analyzers IMA- 4M, IMA-5B, impulse magnetic installations IMPOK-IB and facilities of their metrological support. The information about the scale of , using IS given.

  14. Feasible research on VLLW disposal in control area of nuclear installation

    International Nuclear Information System (INIS)

    Kong Jinsong; Guo Weiqun

    2013-01-01

    Based on the basic requirements on the VLLW landfill disposal specified by the national codes and standards, a on-site disposal of VLLW in the control area of nuclear installation was proposed. A detail analysis of the advantages and disadvantages about the disposal method and the problem to be solved were described. Results showed that the on-site disposal of VLLW in the control area of nuclear installation was feasible in practice. (authors)

  15. Quality assurance requirements for control of procurement items and services for nuclear fuel reprocessing facilities

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Requirements and guidelines are provided for the control of activities to be exercised during procurement of items and services which affect the quality of nuclear facilities. These requirements and guidelines apply to procurement activities for items and services such as designing, purchasing, fabricating, handling, shipping, storing, cleaning, constructing, erecting, installing, inspecting, texting, maintaining and modifying

  16. Integrated control and diagnostic system architectures for future installations

    International Nuclear Information System (INIS)

    Wood, R.; March-Leuba, J.

    2000-01-01

    Nuclear reactors of the 21st century will employ increasing levels of automation and fault tolerance to increase availability, reduce accident risk, and lower operating costs. Key developments in control algorithms, fault diagnostics, fault tolerance, and distributed communications are needed to implement the fully automated plant. It will be equally challenging to integrate developments in separate information and control fields into a cohesive system, which collectively achieves the overall goals of improved safety, reliability, maintainability, and cost-effectiveness. Under the Nuclear Energy Research Initiative (NERI), the US Department of Energy is sponsoring a project to address some of the technical issues involved in meeting the long-range goal of 21st century reactor control systems. This project involves researchers from Oak Ridge National Laboratory, the University of Tennessee, and North Carolina State University. The research tasks under this project focus on some of the first-level breakthroughs in control design, diagnostic techniques, and information system design that will provide a path to enable the design process to be automated in the future. This paper describes the conceptual development of an integrated nuclear plant control and information system architecture, which incorporates automated control system development that can be traced to a set of technical requirements. The expectation is that an integrated plant architecture with optimal control and efficient use of diagnostic information can reduce the potential for operational errors and minimize challenges to the plant safety systems

  17. Preliminary assessment report for Army Aviation Support Facility No. 3, Installation 13307, Hunter Army Airfield, Savannah, Georgia

    International Nuclear Information System (INIS)

    Kolpa, R.; Smith, K.

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Georgia Army National Guard property located on Hunter Army Airfield (HAA) near Savannah, Georgia, known as Army Aviation Support Facility (AASF) No. 3. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, types and quantities of hazardous substances utilized, the nature and amounts of wastes generated or stored at the facility, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the AASF No. 3 property, requirements of the Department of Defense Installation Restoration Program (IRP). The scope of this assessment is limited to the facilities and past activities contained within the area now occupied by AASF No. 3. However, this assessment report is intended to be read in conjunction with a previous IRP assessment of HAA completed in 1992 (USATHAMA 1992) and to provide comprehensive information on AASF No. 3 for incorporation with information contained in that previous assessment for the entirety of HAA

  18. Installation of a muon veto for low background gamma spectroscopy at the LBNL low-background facility

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, K.J., E-mail: kjthomas@lbl.gov [Department of Nuclear Engineering, University of California, Berkeley, CA 94720 (United States); Nuclear Science Division, Lawrence Berkeley Laboratory, CA 94720 (United States); Norman, E.B. [Department of Nuclear Engineering, University of California, Berkeley, CA 94720 (United States); Nuclear Science Division, Lawrence Berkeley Laboratory, CA 94720 (United States); Smith, A.R.; Chan, Y.D. [Nuclear Science Division, Lawrence Berkeley Laboratory, CA 94720 (United States)

    2013-10-01

    An active veto system consisting of plastic scintillation panels was installed outside the Pb shielding of a 115% n-type HPGe detector in an effort to reduce background continuum generated by cosmic ray muons on the surface. The Low Background Facility at the Lawrence Berkeley National Laboratory performs low level assay (generally of primordial U, Th, K) of candidate construction materials for experiments that require a high level of radiopurity. The counting is performed in two facilities: one local surface site and a remote underground site of approximately 600 m.w.e. For the recently installed veto system at the surface location, the top scintillator panel has been in use for nearly 1 year and the full 3π anticoincidence shield was commissioned into normal counting operations in January 2013. The integrated background from 20 to 3600 keV is reduced overall by a factor of 8, where most of the energy spectrum above 100 keV achieves an overall reduction that varies from 8 to 10. A dramatic improvement of peak-to-background across the entire continuum is observed, greatly enhancing low-level peaks that would otherwise be obscured.

  19. The study of the installation of spent fuel interim storage facility from safety aspect point of view

    International Nuclear Information System (INIS)

    Djunaidi, Prayogo S.

    1999-01-01

    The installation of the ISFSF of the RSG-GAS has been come a cureneed, since the RSG-GAS has been operating for more than 10 years. The spent fuel stored in the reactor storage pool in creasing from time to time and therefore a long time storage is needed until the decommissioning of the reactor. The safety aspect related to the installation of the ISFSF has been studied, but the most important aspect are prevention of criticality of the spen fuel in the storage. The radiation dose must be less than that has been recommended by ICRP and the release of the radioactive material must be avoided . In this paper one of the safety aspects i.e. the radiological aspect is described, while the other aspects are referenced to safety analysis report of the facility. From the calculation it can be seen that in accident condition the total radiation dose received by the handling operator is 1.06 mSv and 1.6 mSv resulted from Kr-85 and 1-131. This is lower than the limitation recommended by the ICRP No. 60.1990. Verification for other safety aspect of the facility in still needed

  20. The installation and performance test of the surveillance system for DUPIC facility

    International Nuclear Information System (INIS)

    Kim, Dong Young; Kim, Ho Dong; Cha, Hong Ryul

    2000-07-01

    We have developed the real time surveillance system, named by DSSS, for DUPIC test facility. The system acquires data from He-3 neutron monitors(DSNM) and CCD cameras to automatically diagnose the transportation status of nuclear material. This technical report shortly illustrates important features of hardware and software of the system

  1. The installation and performance test of the surveillance system for DUPIC facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dong Young; Kim, Ho Dong; Cha, Hong Ryul

    2000-07-01

    We have developed the real time surveillance system, named by DSSS, for DUPIC test facility. The system acquires data from He-3 neutron monitors(DSNM) and CCD cameras to automatically diagnose the transportation status of nuclear material. This technical report shortly illustrates important features of hardware and software of the system.

  2. SANS-II at SINQ: Installation of the former Risø-SANS facility

    DEFF Research Database (Denmark)

    Strunz, P.; Mortensen, K.; Janssen, S.

    2004-01-01

    SANS-II facility at SINQ (Paul Scherrer Institute)-the reinstalled former Riso small-angle neutron scattering instrument-is presented. Its operational characteristics are listed. Approaches for precise determination of wavelength, detector dead time and attenuation factors are described as well. (C...

  3. The Self-Calibration Test of flowmeter installed in STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) facility

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Minhwan; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The objective of this study is to describe the procedure of the self-calibration test for the flowmeters and to analyze the result of the test. In this work, the test procedure of the self-calibration of two flowmeters (FT-101, FT-102) installed in STELLA facility was described and the test result was analyzed. In regard to the long-term SFR development plan, a large-scale sodium thermal-hydraulic test project is being progressed by KAERI. This project is called STELLA (Sodium Integral Effect Test Loop for Safety Simulation and Assessment), and it is proceeding by adopting the QA (Quality Assurance) program. Due to the specificity of an experiment using sodium(Na) categorized as Class 3(pyrophoric material and water-prohibiting substance) by the Safety Control of Dangerous Substances Act, it is necessary to apply QA in consideration of the sodium experiment environment in certain parts. The one of them is about calibration of measuring instrument such as a flowmeter, thermocouple and pressure gauge. It is described in the QAP (Quality Assurance Procedures) of KAERI that calibration work should be conducted in accordance with self-calibration procedures in a special case where conventional calibration is not practicable. The calibration of two flowmeters (FT-101, FT-102) installed in STELLA facility is the typical example. As a result of test, it was confirmed that the flowmeters meet the pass criterion. Therefore, it was concluded that the flowmeters maintain instrument capacity a year ago.

  4. Automated entry control system for nuclear facilities

    International Nuclear Information System (INIS)

    Ream, W.K.; Espinoza, J.

    1985-01-01

    An entry control system to automatically control access to nuclear facilities is described. The design uses a centrally located console, integrated into the regular security system, to monitor the computer-controlled passage into and out of sensitive areas. Four types of entry control points are used: an unmanned enclosed portal with metal and SNM detectors for contraband detection with positive personnel identification, a bypass portal for contraband search after a contraband alarm in a regular portal also with positive personnel identification, a single door entry point with positive personnel identification, and a single door entry point with only a magnetic card-type identification. Security force action is required only as a response to an alarm. The integration of the entry control function into the security system computer is also described. The interface between the entry control system and the monitoring security personnel utilizing a color graphics display with touch screen input is emphasized. 2 refs., 7 figs

  5. Experience in ensuring authenticity of information from safeguards systems installed in facilities

    International Nuclear Information System (INIS)

    Abedin-Zadeh, R.; Thiele, R.; Wagner, W.; Whichello, J.

    1991-01-01

    The increasing sophistication of non-destructive assay instruments, containment and surveillance devices and ancillary computer facilities used for safeguards purposes has resulted in a growing requirement for means to ensure the authenticity of information and thus preserve for the IAEA its capability to draw independent conclusions. The achievements of the last few years, particularly with regard to the development of new instruments, one of a kind instrumentation, conceptually new approaches such as the use of near-real-time accounting, and joint use arrangements, are largely the result of cooperation between the IAEA, state authorities, plant operators and certain national laboratories. It is anticipated that demands for various authentication features will further expand as growth in sophistication of equipment and automation of nuclear facilities continues, and that increasing reliance on in-line, unattended use instrumentation will become in future years the approach of choice. 8 refs, 1 fig., 1 tab

  6. Decree no 2007-1557 from November 2, 2007, relative to basic nuclear facilities and to the nuclear safety control of nuclear materials transport; Decret no 2007-1557 du 2 novembre 2007 relatif aux installations nucleaires de base et au controle, en matiere de surete nucleaire, du transport de substances radioactives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-11-15

    This decree concerns the enforcement of articles 5, 17 and 36 of the law 2006-686 from June 13, 2006, relative to the transparency and safety in the nuclear domain. A consultative commission of basic nuclear facilities is established. The decree presents the general dispositions relative to basic nuclear facilities, the dispositions relative to their creation and operation, to their shutdown and dismantling. It precises the dispositions in the domain of public utility services, administrative procedures and sanctions. It stipulates also the particular dispositions relative to other facilities located in the vicinity of nuclear facilities, relative to the use of pressure systems, and relative to the transport of radioactive materials. (J.S.)

  7. Dimensional control and check of field machining parts for reactor internals installation

    International Nuclear Information System (INIS)

    Zhang Caifang

    2010-01-01

    Some key issues of dimensional control for reactor internals installation are analyzed, and important technical requirements of crucial quality control elements on the measurement, machining, and checking of reactor internals filed machining parts are discussed. Moreover, provisions on quality control and risk prevention of reactor internals filed machining parts are presented in this paper. (author)

  8. ENGINEERING AND ECONOMIC FACTORS AFFECTING THE INSTALLATION OF CONTROL TECHNOLOGIES FOR MULTIPOLLUTANT STRATEGIES

    Science.gov (United States)

    The report evaluates the engineering and economic factors associated with installing air pollution control technologies to meet the requirements of strategies to control sulfur dioxide (SO2), oxides of nitrogen (NOX), and mercury under the Clear Skies Act multipollutant control s...

  9. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-01-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. The authors emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities

  10. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-10-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. We emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities. 13 refs., 15 figs., 3 tabs

  11. Controlled Fab installation onto polymeric micelle nanoparticles for tuned bioactivity

    Science.gov (United States)

    Chen, Shaoyi; Florinas, Stelios; Teitgen, Abigail; Xu, Ze-Qi; Gao, Changshou; Wu, Herren; Kataoka, Kazunori; Cabral, Horacio; Christie, R. James

    2017-12-01

    Antibodies and antigen-binding fragments (Fabs) can be used to modify the surface of nanoparticles for enhanced target binding. In our previous work, site-specific conjugation of Fabs to polymeric micelles using conventional methods was limited to approximately 30% efficiency, possibly due to steric hindrance related to macromolecular reactants. Here, we report a new method that enables conjugation of Fabs onto a micelle surface in a controlled manner with up to quantitative conversion of nanoparticle reactive groups. Variation of (i) PEG spacer length in a heterofunctionalized cross-linker and (ii) Fab/polymer feed ratios resulted in production of nanoparticles with a range of Fab densities on the surface up to the theoretical maximum value. The biological impact of variable Fab density was evaluated in vitro with respect to cell uptake and cytotoxicity of a drug-loaded (SN38) targeted polymeric micelle bearing anti-EphA2 Fabs. Fab conjugation increased cell uptake and potency compared with non-targeted micelles, although a Fab density of 60% resulted in decreased uptake and potency of the targeted micelles. Altogether, our findings demonstrate that conjugation strategies can be optimized to allow control of Fab density on the surface of nanoparticles and also that Fab density may need to be optimized for a given cell-surface target to achieve the highest bioactivity.

  12. Preliminary assessment report for Kent National Guard Facility (Installation 53065), 24410 Military Road, Kent, Washington

    International Nuclear Information System (INIS)

    Ketels, P.; Aggarwal, P.; Rose, C.M.

    1993-08-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Washington Army National Guard property in Kent, Washington. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment

  13. Quality control of a virtual simulation installation. SFPM report nr 25, August 2009

    International Nuclear Information System (INIS)

    Foulquier, Jean-Noel; Allieres, Norbert; Batalla, Alain; Beaumont, Stephane; Di Bartolo, Cristelle; Khodri, Mustapha; Tauziede, Jean-Marc; Dedieu, Veronique; Bramoule, Celine; Caselles, Olivier; Lacaze, Brigitte; Mazurier, Jocelyne

    2009-08-01

    This report is a notably comprehensive guide for the different controls which can be performed on devices present in a Virtual Simulation installation. After a brief historical recall, the authors present the definition and organisation of a virtual simulation, the different components of a virtual simulation installation, and the different steps of virtual simulation process. Then, they address the quality control of the scanner-simulator (linearity and periodicity of controls, patient table or support, tolerance levels and periodicity of controls of this support). They address tracking systems (quality control of laser systems), the quality control of virtual simulation tools (iso-centre contouring and positioning, ballistic tools, tolerance levels, control periodicity), the quality control of data transfer or objects (elements to be analysed during an image transfer, tolerance levels and control periodicity), the imager quality control, and tests phantoms (the physical and digital phantoms)

  14. Post-Installation evaluation of the neutron radiography facility of ITU TRIGA Mark-II Reactor

    International Nuclear Information System (INIS)

    Yavuz, H.; Durmayaz, A.

    2008-01-01

    Results of the experiments for determining the characteristics of the previously described neutron radiography facility designed and built in the Istanbul Technical University are presented. The thermal and total neutron fluxes and the gamma exposure rates have been measured inside, at the exit of the neutron beam collimator, and at its surroundings. The ratio of neutron flux to gamma exposure rate at maximum power has been determined. The results have been compared to those measured in the absence of the collimator. The neutron fluxes have been determined by using the foil activation method with gold foils enclosed in cadmium capsules. The gamma exposure rates have been measured by using Li 7 F- CTLD 700 thermoluminescent dosemeters. (authors)

  15. Instrumentation report 1: specification, design, calibration, and installation of instrumentation for an experimental, high-level, nuclear waste storage facility

    International Nuclear Information System (INIS)

    Brough, W.G.; Patrick, W.C.

    1982-01-01

    The Spent Fuel Test-Climax (SFT-C) is being conducted 420 m underground at the Nevada Test Site under the auspices of the US Department of Energy. The test facility houses 11 spent fuel assemblies from an operating commercial nuclear reactor and numerous other thermal sources used to simulate the near-field effects of a large repository. We developed a large-scale instrumentation plan to ensure that a sufficient quality and quantity of data were acquired during the three- to five-year test. These data help satisfy scientific, operational, and radiation safety objectives. Over 800 data channels are being scanned to measure temperature, electrical power, radiation, air flow, dew point, stress, displacement, and equipment operation status (on/off). This document details the criteria, design, specifications, installation, calibration, and current performance of the entire instrumentation package

  16. Installation and instrumentation of a test-trench facility in the unsaturated zone at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Lewis, B.D.

    1984-01-01

    Two simulated waste trenches have been constructed just north of the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory. Sections of culvert occupy part of these trenches and are accessible through vertical caissons. These structures therefore allow personnel access for installing instrumentation, maintenance, and observation. Instrumented simulated waste containers will occupy the remainder of the trenches, in order that soil-moisture migration may be observed in relation to waste container forms. The installation will be used to determine, under actual and simulated conditions at a shallow land-burial site in an arid environment, typical soil-moisture content, unsaturated hydraulic conductivity, matric potential, soil-moisture flux, and soil-moisture velocity. The information will be collected using instrumentation located in disturbed and undisturbed soils, simulated waste containers, and the underlying basalt layer. Therefore, data collected from the facility will (a) help characterize the hydrogeologic and geochemical properties of the surficial sediments, (b) contribute to understanding the hydrogeologic phenomena associated with buried waste (including leachate formation and radionuclide migration), (c) provide information on water and solute movement at the sediment/basalt interface, and (d) be used in a radionuclide migration model

  17. Techniques for controlling air pollution from the operation of nuclear facilities. Report of a panel

    International Nuclear Information System (INIS)

    1966-01-01

    This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level.

  18. Some mathematical aspects of creation of the control system for a physical installation

    International Nuclear Information System (INIS)

    Efimov, K.M.; Efimova, T.E.; Zagurskij, A.B.

    1988-01-01

    The article presented is a result of investigations connected to the problems of the software creation for the linear accelerator automatic control system. The problems considered arise before each scientific group engaged in the development of the automatic control complex for a physical installation. The possible ways of solving such problems are discussed

  19. Competitive adsorption of heavy metals in soil underlying an infiltration facility installed in an urban area.

    Science.gov (United States)

    Hossain, M A; Furumai, H; Nakajima, F

    2009-01-01

    Accumulation of heavy metals at elevated concentration and potential of considerable amount of the accumulated heavy metals to reach the soil system was observed from earlier studies in soakaways sediments within an infiltration facility in Tokyo, Japan. In order to understand the competitive adsorption behaviour of heavy metals Zn, Ni and Cu in soil, competitive batch adsorption experiments were carried out using single metal and binary metal combinations on soil samples representative of underlying soil and surface soil at the site. Speciation analysis of the adsorbed metals was carried out through BCR sequential extraction method. Among the metals, Cu was not affected by competition while Zn and Ni were affected by competition of coexisting metals. The parameters of fitted 'Freundlich' and 'Langmuir' isotherms indicated more intense competition in underlying soil compared to surface soil for adsorption of Zn and Ni. The speciation of adsorbed metals revealed less selectivity of Zn and Ni to soil organic matter, while dominance of organic bound fraction was observed for Cu, especially in organic rich surface soil. Compared to underlying soil, the surface soil is expected to provide greater adsorption to heavy metals as well as provide greater stability to adsorbed metals, especially for Cu.

  20. Automation facilities for agricultural machinery control

    Directory of Open Access Journals (Sweden)

    A. Yu. Izmaylov

    2017-01-01

    Full Text Available The possibility of use of the automation equipment for agricultural machinery control is investigated. The authors proposed solutions on creation of the centralized unified automated information system for mobile aggregates management. In accordance with the modern requirements this system should be open, integrated into the general schema of agricultural enterprise control. Standard hardware, software and communicative features should be realized in tasks of monitoring and control. Therefore the schema should be get with use the unified modules and Russian standards. The complex multivariate unified automated control system for different objects of agricultural purpose based on block and modular creation should correspond to the following principles: high reliability, simplicity of service, low expenses in case of operation, the short payback period connected to increase in productivity, the reduced losses when harvesting, postharvest processing and storage, the improved energetic indices. Technological processes control in agricultural production is exercised generally with feedback. The example without feedback is program control by temperature in storage in case of the cooling mode. Feedback at technological processes control in agricultural production allows to optimally solve a problem of rational distribution of functions in man-distributed systems and forming the intelligent ergonomic interfaces, consistent with professional perceptions of decision-makers. The negative feedback created by the control unit allows to support automatically a quality index of technological process at the set level. The quantitative analysis of a production situation base itself upon deeply formalized basis of computer facilities that promotes making of the optimal solution. Information automated control system introduction increases labor productivity by 40 percent, reduces energetic costs by 25 percent. Improvement of quality of the executed technological

  1. Recommendations for the lighting of sporting facilities. 5. edition; Recommandations relatives a l'eclairage des installations sportives. 5. edition

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-01-01

    Natural and artificial lighting is an important factor of comfort, pleasure and safety in sporting facilities and influences the construction costs but also the frequenting of installations. The duration of use of installations and the profitability of investments are directly linked with the prolongation of visiting hours for competition, training and leisure purposes. This book presents, first, the common recommendations and principles for the lighting of sporting facilities in general. The particular recommendations relative to some specific activities are considered in a second part (golf, ski, bowls, pelota, skate-board, hippodromes etc..). (J.S.)

  2. Facilities for in-service control

    International Nuclear Information System (INIS)

    Werner, H.

    1980-01-01

    Up to now the efficiency of in-service control had been limited and dependent on special qualifications of the super-intending personnel and was thus neither exact nor transferable. In the meantime a great number of testing and measuring facilities for special application have been developed. Even novel types of testing methods do not grant absolutely precise statements. In most cases, however, there is a possibility of planning repairs by trend control and of avoiding failures of operation with aggravating consequences. Technical designers from all subject fields should be made familiar with the continually increasing spectrum of in-service inspection techniques so that a better application of modern and well-tried testing methods can be planned. Systematic in-service inspections complete the Rules of Technology which are safety-oriented with regard to the nonlinear wear between regular dates of control which has been ignored so far and its implied risks. Components which are not liable to control can be checked much better by novel type methods. (orig./RW) [de

  3. Wind power installations in Switzerland - Checklist for investors in large-scale installations; Eoliennes en Suisse. Liste de controle pour investisseurs de grandes installations

    Energy Technology Data Exchange (ETDEWEB)

    Ott, W.; Kaufmann, Y.; Steiner, P. [Econcept AG, Zuerich (Switzerland); Gilgen, K.; Sartoris, A. [IRAP-HSR, Institut fuer Raumentwicklung an der Hochschule fuer Technik Rapperswil, Rapperswil (Switzerland)

    2008-07-01

    This report published by the Swiss Federal Office of Energy (SFOE) takes a look at a checklist for investors in large-scale wind-power installations. The authors state that the same questions are often posed in the course of the planning and realisation of wind turbine installations. This document presents a checklist that will help achieve the following goals: Tackling the steps involved in the planning and implementation phases, increasing planning security, systematic implementation in order to reduce risks for investors and to shorten time-scales as well as the reduction of costs. Further, participative processes can be optimised by using comprehensively prepared information in order to reduce the risk of objections during project approval. The structure of the check-list is described and discussed.

  4. Non-radioactive disposal facility-bioremediation horizontal well installation project

    International Nuclear Information System (INIS)

    Kupar, J.; Hasek, M.

    1998-01-01

    The Sanitary Landfill Corrective Action Plan proposes a two pronged approach to remediation. The first part of the total remediation strategy is the placement of a RCRA style closure cap to provide source control of contaminants into the groundwater. The second part of the proposed remediation package is a phased approach primarily using an in situ bioremediation system for groundwater clean up of the Constituents of Concern (COCs) that exceed their proposed Alternate Concentration Limits (ACL). The phased in approach of groundwater clean up will involve operation of the in situ bioremediation system, followed by evaluation of the Phase 1 system and, if necessary, additional phased remediation strategies. This document presents pertinent information on operations, well locations, anticipated capture zones, monitoring strategies, observation wells and other information which will allow a decision on the acceptability of the remedial strategy as an interim corrective action prior to permit application approval. The proposed interim phase of the remediation program will position two horizontal bioremediation wells such that the respective zones of influence will intersect the migration path for the highest concentrations of each plume

  5. An automatic system for controlling the quality of straws installed in the ATLAS TRT detector

    CERN Document Server

    Golunov, A O; Gousakov, Yu V; Kekelidze, G D; Livinski, V V; Mouraviev, S V; Parzycki, S S; Peshekhonov, V D; Price, M J; Savenkov, A A

    2004-01-01

    This article describes an automatic system to control the quality of straws installed in the wheels of the end-cap Transition Radiation Tracker of the ATLAS experiment. The system tests both the straightness and the electrical insulation of the straws during installation. The testing time per straw is 9s; consequently it takes about 2h to measure one layer of straws. The off-line analysis takes 20s per straw. With this system defects can be immediately detected and corrected. This clearly influences the future performance of the detector.

  6. Contamination control training for biomedical facilities

    International Nuclear Information System (INIS)

    Trinoskey, P.A.

    1994-10-01

    In 1991, a contamination control course was developed for the Biology and Biotechnology Research Program (BBRP) at the Lawrence Livermore National Laboratory (LLNL). This course was based on the developer's experience in Radiation Safety at the University of Utah and University of Kansas Medical Center. This course has been well received at LLNL because it addresses issues that are important to individuals handling small quantities of radioactive materials. This group of users is often overlooked. They are typically very well educated and are expected to ''know'' what they should do. Many of these individuals are not initially comfortable working with radioactive materials. They appreciate the opportunity to be introduced to contamination control techniques and to discuss issues they may have. In addition, the authors benefit by experience that researchers bring from other facilities. The training course will address the specific radiological training requirements for chemists, biologists, and medical researchers who are using small amounts of dispersible radionuclides in tabletop experiments, and will not be exposed to other radiation sources. The training will include: the potential hazards of typical radionuclides, contamination control procedures, and guidance for developing and including site-specific information. The training course will eliminate the need for Radiological Worker II training for bio-medical researchers. The target audience for this training course is bio-medical researchers

  7. RETROFITTING CONTROL FACILITIES FOR WET-WEATHER FLOW TREATMENT

    Science.gov (United States)

    Available technologies were evaluated to demonstrate the technical feasibility and cost effectiveness of retrofitting existing facilities to handle wet-weather flow. Cost/benefit relationships were also compared to construction of new conventional control and treatment facilities...

  8. Controlling Infrastructure Costs: Right-Sizing the Mission Control Facility

    Science.gov (United States)

    Martin, Keith; Sen-Roy, Michael; Heiman, Jennifer

    2009-01-01

    Johnson Space Center's Mission Control Center is a space vehicle, space program agnostic facility. The current operational design is essentially identical to the original facility architecture that was developed and deployed in the mid-90's. In an effort to streamline the support costs of the mission critical facility, the Mission Operations Division (MOD) of Johnson Space Center (JSC) has sponsored an exploratory project to evaluate and inject current state-of-the-practice Information Technology (IT) tools, processes and technology into legacy operations. The general push in the IT industry has been trending towards a data-centric computer infrastructure for the past several years. Organizations facing challenges with facility operations costs are turning to creative solutions combining hardware consolidation, virtualization and remote access to meet and exceed performance, security, and availability requirements. The Operations Technology Facility (OTF) organization at the Johnson Space Center has been chartered to build and evaluate a parallel Mission Control infrastructure, replacing the existing, thick-client distributed computing model and network architecture with a data center model utilizing virtualization to provide the MCC Infrastructure as a Service. The OTF will design a replacement architecture for the Mission Control Facility, leveraging hardware consolidation through the use of blade servers, increasing utilization rates for compute platforms through virtualization while expanding connectivity options through the deployment of secure remote access. The architecture demonstrates the maturity of the technologies generally available in industry today and the ability to successfully abstract the tightly coupled relationship between thick-client software and legacy hardware into a hardware agnostic "Infrastructure as a Service" capability that can scale to meet future requirements of new space programs and spacecraft. This paper discusses the benefits

  9. System design and installation for RS600 programmable control system for solar heating and cooling

    Science.gov (United States)

    1978-01-01

    Procedures for installing, operating, and maintaining a programmable control system which utilizes a F8 microprocessor to perform all timing, control, and calculation functions in order to customize system performance to meet individual requirements for solar heating, combined heating and cooling, and/or hot water systems are described. The manual discusses user configuration and options, displays, theory of operation, trouble-shooting procedures, and warranty and assistance. Wiring lists, parts lists, drawings, and diagrams are included.

  10. Design/installation and structural integrity assessment under the Federal Facility Agreement for Bethel Valley low-level waste collection and transfer system upgrade for Building 2026 (High Radiation Level Analytical Laboratory) and Building 2099 (Monitoring and Control Station) at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1994-11-01

    This document presents a Design/Installation and Structural Integrity Assessment for a replacement tank system for portions of the Bethel Valley Low-Level Waste (LLW) System, located at the Oak Ridge Reservation, Oak Ridge, Tennessee. This issue of the assessment covers the design aspects of the replacement tank system, and certifies that the design has sufficient structural integrity and is acceptable for the storing or treating of hazardous and/or radioactive substances. This document will be reissued at a future date and will then include the assessment of the installation of the replacement tank system. The present issue identifies specific activities that must be completed during the fabrication, installation, and testing of the replacement tank system in order to provide assurance that the final installation complies with governing requirements

  11. Second session: operating European facilities and their programs; Session 2: Les installations Europeennes actuelles et leurs programmes

    Energy Technology Data Exchange (ETDEWEB)

    Iracane, D. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Porracchia, A.; Fougeras, P.; Morey, J.M. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d' Etudes des Reacteurs; Loubiere, S.; Durande-Ayme, P. [CEA Saclay, Nuclear Energy Div., Reactors and Nuclear Services Deptment, 91 - Gif-sur-Yvette (France); Guidez, J.; Goux, D. [CEA Valrho, Dir. de l' Energie Nucleaire, DEN, 30 - Marcoule (France); Dupraz, R.; Brand, B. [FRAMATOME, AREVA-FANP, 69 - Lyon (France); Blanc, J.Y. [CEA Saclay, 91 - Gif sur Yvette (France); Perthuis, S. de [FRAMATOME ANP, 92 - Paris-La-Defence (France); Le Rouzic, J.F. [Electricite de France (EDF), 92 - Clamart (France)

    2005-07-01

    Most European nuclear post-irradiation examination facilities are ageing and the optimization of the remaining infrastructures may lead to connect them through a network implying consistent staff competence between countries and efficient nuclear material transport means. The second article describes the 3 very-low power research reactors operating in France: Minerve, Masurca and Eole. The Osiris reactor is presented in the third article, the author focuses on the devices available in Osiris to perform irradiation in light water reactor conditions and in high temperature reactor conditions and on the associated programs. Phenix reactor located on the Marcoule site had been performing from 1974 to 1990 the necessary technological qualifications required by the fast reactor system. An important upgrading program, led from 1994 to 2003, has allowed the reactor to begin a second life. Its investigation program encompasses research work on the transmutation of actinides and fission products and on new nuclear fuels and materials required for the future fourth generation of reactors. In Europe about 20 hot laboratories offer services to perform examination and qualification required by their national civil nuclear programs. Most are state-owned and show a large range of activities: nuclear fuels, materials, reprocessing, radio-nuclides, and radio-active sources. The last article reviews the main test loops operating in France and in neighboring countries. About 30 installations are reported and classified according to their activity fields : critical heat flux, hydro-mechanics, device testing, accidental situations, helium and severe reactor accidents. (A.C.)

  12. On Orientation Control of Suspended Blade During Installation in Wind Turbines

    DEFF Research Database (Denmark)

    Schmidt, Lasse; Roemer, Daniel Beck; Pedersen, Henrik Clemmensen

    2015-01-01

    This paper discusses problems involved in the procedure for offshore installation of blades in wind turbines, due to wind loads. In general the high winds at sea provides for nearly optimal conditions for harvesting energy via wind turbines due to the often high wind speeds and low turbulence...... intensity. However, the very same features also call for great difficulties during installation of the wind turbine blades, making this process extremely difficult, expensive and time consuming. Often the blades are hoisted to the wind turbine hub via cranes and sought held in appropriate positions by so......-called taglines/wires, but still significant motion oscillations of blade root ends are experienced, even at rather low wind speeds. The paper considers the possibility to dampen the oscillating motions via control of the tagline lengths. The main control strategy considered, is the possibility to control...

  13. Status of safety at Areva group facilities. 2007 annual report; Areva, etat de surete des installations nucleaires. Rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.

  14. Controlled Archaeological Test Site (CATS) Facility

    Data.gov (United States)

    Federal Laboratory Consortium — CATS facility is at the Construction Engineering Research Laboratory (CERL), Champaign, IL. This 1-acre test site includes a variety of subsurface features carefully...

  15. 75 FR 18572 - Facility Control Numbers

    Science.gov (United States)

    2010-04-12

    ...), biodiesel production facilities (BCN), or ethanol production facilities (ECN). A taxable fuel registrant... -CB-) will be issued a BCN for each biodiesel production physical location that a registrant in good... approved terminal. Each TCN identifies a unique physical location in the bulk transport/delivery system and...

  16. A comprehensive centralized control system for radiation waste treatment facility

    International Nuclear Information System (INIS)

    Kong Jinsong

    2014-01-01

    A comprehensive centralized control system is designed for the radiation waste treatment facility that lacking of coordinated operational mechanism for the radiation waste treatment. The centralized control and alarm linkage of various systems is implemented to ensure effectively the safety of nuclear facility and materials, improve the integral control ability through advanced informatization ways. (author)

  17. A new conception for the central control facility of MEA

    International Nuclear Information System (INIS)

    Schimmel, F.

    1986-01-01

    To control the AFBU from the Central Control Facility some change will be necessary. This has led to a complete revision of the facilities of both consoles. Some proposals are made to improve the response time of the control systems. These improvements are feasible at short notice. (G.J.P.)

  18. LightLeaves: computer controlled kinetic reflection hologram installation and a brief discussion of earlier work

    International Nuclear Information System (INIS)

    Connors Chen, Betsy

    2013-01-01

    LightLeaves is an installation combining leaf shaped, white light reflection holograms of landscape images with a special kinetic lighting device that houses a lamp and moving leaf shaped masks. The masks are controlled by an Arduino microcontroller and servomotors that position the masks in front of the illumination source of the holograms. The work is the most recent in a long series of landscapes that combine multi-hologram installations with computer controlled devices that play with the motion of the holograms, the light, sound or other elements in the work. LightLeaves was first exhibited at the Peabody Essex Museum in Salem, Massachusetts in a show titled E ye Spy: Playing with Perception .

  19. LightLeaves: computer controlled kinetic reflection hologram installation and a brief discussion of earlier work

    Energy Technology Data Exchange (ETDEWEB)

    Connors Chen, Betsy, E-mail: acmeholo@gmail.com [ACME Holography, Somerville, Massachusetts USA 02144 (United States)

    2013-02-22

    LightLeaves is an installation combining leaf shaped, white light reflection holograms of landscape images with a special kinetic lighting device that houses a lamp and moving leaf shaped masks. The masks are controlled by an Arduino microcontroller and servomotors that position the masks in front of the illumination source of the holograms. The work is the most recent in a long series of landscapes that combine multi-hologram installations with computer controlled devices that play with the motion of the holograms, the light, sound or other elements in the work. LightLeaves was first exhibited at the Peabody Essex Museum in Salem, Massachusetts in a show titled {sup E}ye Spy: Playing with Perception{sup .}.

  20. The calibration procedure of the radiation monitoring system installed in radiation controlled area of KOMAC

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sung-Kyun; Min, Yi-Sub; Park, Jeong-Min; Cho, Yong-Sub [Korea Atomic Energy Research Institute, Gyeongju (Korea, Republic of)

    2016-10-15

    The spaces, where these accelerators are installed, are defined as the radiation controlled area and the levels of the radiation in this area are monitored by the radiation monitoring system (RMS) to protect radiation workers and experiment users from the hazards of the ionizing radiation and the surface and air contamination tests are carried out periodically by the radiation secure team. The most of RMS instruments are installed in the accelerator building, where the 100-MeV proton linear accelerator is installed. All detectors of RMS should be calibrated every year to prove the reliability of RMS and almost all instruments for RMS was calibrated during this summer maintenance period of KOMAC this year. Almost all RMS instruments installed in KOMAC is calibrated between 2016-07-13 and 2016-08-24. As the calibration result, if the current reading value are within the 5% of the reference dose rate value, this RMS instrument can be used one more year. Otherwise, the detector of that RMS instrument should be repaired or replaced. The self-calibration certificate for each RMS instrument will be published only for the instrument to satisfy the condition.

  1. Simulator Facility for Attitude Control and Energy Storage of Spacecraft

    National Research Council Canada - National Science Library

    Tsiotras, Panagiotis

    2002-01-01

    This report concerns a designed and built experimental facility that will allow the conduction of experiments for validating advanced attitude control algorithms for spacecraft in a weightless environment...

  2. Functioning strategy study on control systems of large physical installations used with a digital computer

    International Nuclear Information System (INIS)

    Bel'man, L.B.; Lavrikov, S.A.; Lenskij, O.D.

    1975-01-01

    A criterion to evaluate the efficiency of a control system functioning of large physical installations by means of a control computer. The criteria are the object utilization factor and computer load factor. Different strategies of control system functioning are described, and their comparative analysis is made. A choice of such important parameters as sampling time and parameter correction time is made. A single factor to evaluate the system functioning efficiency is introduced and its dependence on the sampling interval value is given. Using diagrams attached, it is easy to find the optimum value of the sampling interval and the corresponding maximum value of the single efficiency factor proposed

  3. Regionally differentiated air pollution control regulations in the installation-related emission control law of the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Buettner, T.W.

    1992-01-01

    The volume treats an issue from the boundary zone between environmental law and environmental economics, namely the regionalization of air pollution control standards in installation-related emission control law. In order to examine the question of whether this proposal, which originates in the field of environmental economics, can be adopted and is purposeful, the author initially performs a complete inventorization of applicable norms, this covering emission control law, the law of regional planning, and the provisions of international law. This status quo is then reviewed using conformity and optimization criteria developed by the political sciences. The assessment comes to the conclusion that the introduction of regionally differentiated air pollution control standards is not desirable. The author further submits proposals for the streamlining of the law of installation-related air pollution control in the Federal Republic of Germany. (orig.) [de

  4. Experience in the installation of a microprocessor system for controlling converter units of the Vyborg substation

    International Nuclear Information System (INIS)

    Gusakovskii, K. B.; Zmaznov, E. Yu.; Katantsev, S. V.; Mazurenko, A. K.; Mestergazi, V. A.; Prochan, G. G.; Funtikova, S. F.

    2006-01-01

    The experience in the installation of modern digital systems for controlling converter units at the Vyborg converter substation on the basis of advanced microprocessor devices is considered. It is shown that debugging of a control and protection system on mathematical and physical models does not guarantee optimum control of actual converter devices. Examples of advancing the control and protection system are described, the necessity for which has become obvious in tests of actual equipment. Comparison of oscillograms of processes before optimization of the control system and after its optimization and adjustment shows that the digital control system makes it possible to improve substantially the algorithms of control and protection in the short term and without changing the hardware component

  5. Physical Sciences Facility Air Emission Control Equivalency Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Brown, David M.; Belew, Shan T.

    2008-10-17

    This document presents the adequacy evaluation for the application of technology standards during design, fabrication, installation and testing of radioactive air exhaust systems at the Physical Sciences Facility (PSF), located on the Horn Rapids Triangle north of the Pacific Northwest National Laboratory (PNNL) complex. The analysis specifically covers the exhaust portion of the heating, ventilation and air conditioning (HVAC) systems associated with emission units EP-3410-01-S, EP-3420-01-S and EP 3430-01-S.

  6. Complementary safety assessment assessment of nuclear facilities - Tricastin facility - AREVA; Evaluation complementaire de la surete des installations nucleaires de base - Site du Tricastin - AREVA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This complementary safety assessment analyses the robustness of the Areva part of the Tricastin nuclear site to extreme situations such as those that led to the Fukushima accident. This study includes the following facilities: Areva NC Pierrelatte, EURODIF production, Comurhex Pierrelatte, Georges Besse II plant and Socatri. Robustness is the ability for the plant to withstand events beyond which the plant was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accidental sequence. Moreover, safety is not only a matter of design or engineered systems but also a matter of organizing: task organization (including subcontracting) as well as the setting of emergency plans or the inventory of nuclear materials are taken into consideration in this assessment. This report is divided into 10 main chapters: 1) the feedback experience of the Fukushima accident; 2) description of the site and its surroundings; 3) featuring of the site's activities and installations; 4) accidental sequences; 5) protection from earthquakes; 6) protection from floods; 7) protection from other extreme natural disasters; 8) the loss of electrical power and of the heat sink; 9) the management of severe accidents; and 10) subcontracting policy. This analysis has identified 5 main measures to be taken to limit the risks linked to natural disasters: -) continuing the program for replacing the current conversion plant and the enrichment plant; -) renewing the storage of hydrofluoric acid at the de-fluorination workshop; -) assessing the seismic behaviour of some parts of the de-fluorination workshop and of the fluorine fabrication workshop; -) improving the availability of warning and information means in case of emergency; and -) improving the means to mitigate accidental gaseous releases. (A.C.)

  7. Installing Omeka

    Directory of Open Access Journals (Sweden)

    Jonathan Reeve

    2016-07-01

    Full Text Available Omeka.net is a useful service for Omeka beginners, but there are a few reasons why you might want to install your own copy of Omeka. Reasons include: * Upgrades. By installing Omeka yourself, you can use the latest versions of Omeka as soon as they’re released, without having to wait for Omeka.net to upgrade their system. * Plugins and themes. You can install any plugin or theme you want, without being restricted to those provided by Omeka.net. * Customizations. You can buy a custom domain name, and customize your code to achieve your desired functionality. * Control. You have control over your own backups, and you can update the server yourself so that its security is always up-to-date. * Price. There are many low-cost Virtual Private Servers (VPSs now, some of which cost only $5 per month. * Storage. Many shared hosting providers now offer unlimited storage. This is useful if you have a large media library. In this tutorial, we’ll be entering a few commands on the command line. This tutorial assumes no prior knowledge of the command line, but if you want a concise primer, consult the Programming Historian introduction to BASH. There are other ways of installing Omeka, of course, some using exclusively GUI tools. Some hosting providers even offer “one-click installs” via their control panels. Many of those methods, however, will install older versions of Omeka which are then harder to upgrade and maintain. The method outlined below may not be the easiest way to install Omeka, but it will give you some good practice with using the command line, which is a skill that will be useful if you want to manually upgrade your install, or manually install other web frameworks. (For example, this installation method is very similar to WordPress’s “Five-Minute Install”. There are four steps to this process, and it should take about an hour.

  8. Data acquisition and control system in a heavy water detritiation installation

    International Nuclear Information System (INIS)

    Stefan, Iuliana; Balteanu, Ovidiu; Retevoi, Carmen; Stefan, Liviu

    2002-01-01

    The experimental installation for extracting tritium and deuterium from the tritiated heavy water used as moderator in CANDU type nuclear reactors is described. The separated tritium of high purity can be used in the fusion reactors of the future or in various laboratory researches. The fluids implied in operating this installation require special safety measures to be taken to protect both the operational personnel and the environment. Accordingly, in the technologic room no personnel is allowed and hence parameter monitoring, analyses and the testing must be done by remote control equipment. The computers for monitoring, warning and testing, as well as the sensors are housed in the data acquisition room, separated from the control room. The values generated by the process variables are converted in electrical or pneumatic signals and subsequently transmitted to the subsystems of monitoring, control and protection. Data acquisition in the control room is ensured by a computer provided with a FieldPoint interface. So, the connection between I/O modules from the data acquisition room and the computer ensures a 115.2 kb/s speed. Measured values of the parameters are recorded and displayed in the control room. Here these are compared with preset limits of the process parameters and in case of abnormal behavior, an alarm is triggered both optically and acoustically. At the same time, the program which controls the inputs and the outputs makes decisions and issues corrective or preventive commands for the technological process or installation protection, respectively. A diagram illustrating the monitoring, using a LabView platform is presented

  9. Building control for nuclear materials R and D facility

    International Nuclear Information System (INIS)

    Hart, O.

    1979-01-01

    The new plutonium research and development facility at LASL was the first facility to be completed in the United States under the new environmental requirements. To insure that these new requirements are met, a redundant computer system is used to monitor and control the building. This paper describes the supervisory control and data acquisition system that was implemented to perform that function

  10. Computer-controlled environmental test systems - Criteria for selection, installation, and maintenance.

    Science.gov (United States)

    Chapman, C. P.

    1972-01-01

    Applications for presently marketed, new computer-controlled environmental test systems are suggested. It is shown that capital costs of these systems follow an exponential cost function curve that levels out as additional applications are implemented. Some test laboratory organization changes are recommended in terms of new personnel requirements, and facility modification are considered in support of a computer-controlled test system. Software for computer-controlled test systems are discussed, and control loop speed constraints are defined for real-time control functions. Suitable input and output devices and memory storage device tradeoffs are also considered.

  11. France. The Centre de la Manche disposal facility: Entering into the institutional control period

    International Nuclear Information System (INIS)

    2001-01-01

    The Centre de la Manche disposal facility, created by decree in 1969, is the first French near-surface radioactive waste disposal facility. It lies at the northwest end of the Cotentin peninsula, next to the COGEMA-La Hague fuel reprocessing plant. The Centre de la Manche facility occupies an area of about 150,000 m 2 . Its operation was terminated in late June 1994 with about 500,000 m 3 of packages disposed of. Operating feedback from the Centre de la Manche was used to design the second French disposal facility, located in the Aube, which has been receiving LILW since 1992. Since the end of the operating period, ANDRA has been preparing the statutory files to prepare the Centre de la Manche for its entry into the institutional control period. A new government decree will set the framework in which the Centre will evolve in this period. The regulatory process includes the filing of an application with the ministries concerned, containing a file with the requisite statutory documents, including an impact study of the facility on its environment as well as a hazard study. The file will then be submitted to a public inquiry, an essential informative period of the project designed to make a compilation of criticisms and suggestions from the public. In support of the application, a safety report has been sent to the Nuclear Installation Safety Directorate (DSIN) for a decision on the admissibility of the application. Recently, the Group of experts appointed by the DSIN which examined it has come out in favor of the creation of a new basic nuclear installation (i.e., a new government agency) for the institutional control period. A draft decree will then be submitted to the approval of the Interministerial Commission for Basic Nuclear Installations. This process, initiated in 1994, is nearing completion

  12. Emergency facility control device for nuclear reactor

    International Nuclear Information System (INIS)

    Ikehara, Morihiko.

    1981-01-01

    Purpose: To increase the reliability of a nuclear reactor by allowing an emergency facility to be manually started and stopped to make its operation more convenient and eliminate the possibility of erroneous operation in an emergency. Constitution: There are provided a first water level detector for detecting a level lower than the first low water level in a reactor container and a second water level detector for detecting a level lower than the second low water level lower than the first low water level, and an emergency facility can be started and stopped manually only when the level is higher than the second low water level, but the facility will be started regardless of the state of the manual operation when the level is lower than the second low water level. Thus, the emergency facility can be started by manual operation, but will be automatically started so as to secure the necessary minimum operation if the level becomes lower than the second low water level and the stopping operation thereafter is forgotten. (Kamimura, M.)

  13. Design, manufacture and installation of measuring and control equipments for the advanced thermal prototype reactor 'Fugen'

    International Nuclear Information System (INIS)

    Hirota, Shigeo; Kawabata, Yoshinori

    1979-01-01

    The advanced thermal prototype reactor ''Fugen'' attained the criticality on March 20, 1978, and 100% output operation on November 13, 1978. On March 20, 1979, it passed the final inspection, and since then, it has continued the smooth operation up to now. The measuring and control equipments are provided for grasping the operational conditions of the plant and operating it safely and efficiently. At the time of designing, manufacturing and installing the measuring and control equipments for Fugen, it was required to clarify the requirements of the plant design, to secure the sufficient functions, and to improve the operational process, maintainability and the reliability and accuracy of the equipments. Many design guidelines and criteria were decided in order to coordinate the conditions among five manufacturers and give the unified state as one plant. The outline of the instrumentations for neutrons, radiation monitoring and process data, the control systems for reactivity, reactor output, pressure and water supply, the safety protection system, and the process computer are described. Finally, the installations and tests of the measuring and control equipments are explained. The aseismatic capability of the equipments was confirmed. (Kako, I.)

  14. Installation of PMV Operation Program in DDC Controller and Air Conditioning Control Using PMV Directly as Set Point

    Science.gov (United States)

    Haramoto, Ken-Ichi

    In general, air conditioning control in a building is operated mainly by indoor air temperature control. Although the operators of the machine in the building accepted a claim for indoor air temperature presented by the building inhabitants, the indoor conditions have been often too cool or warm. Therefore, in an attempt to create better thermal environments, the author paid attention to the PMV that is a thermal comfort index. And then, the possibility of air conditioning control using the PMV directly as the set point was verified by employing actual equipment in an air conditioning testing room and an office building. Prior to the execution of this control, the operation program of the PMV was installed in a DDC controller for the air conditioning control. And information from indoor sensors and so on was inputted to the controller, and the computed PMV was used as the feedback variable.

  15. Techniques for controlling air pollution from the operation of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    1966-03-01

    This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level. Refs, 24 figs, 5 tabs.

  16. Change in plan for installation of nuclear reactor in Genkai Nuclear Power Plant of Kyushu Electric Power Co., Inc. (change in plan for No.3 and No.4 nuclear reactor facilities) (report)

    International Nuclear Information System (INIS)

    1987-01-01

    This report, compiled by the Nuclear Safety Commission to be submitted to the Minister of International Trade and Industry, deals with studies on a proposed change in the plan for the installation of nuclear reactors in the Genkai Nuclear Power Plant of Kyushu Electric Power Co., Inc. (change in the plan for the No.3 and No.4 nuclear reactor facilities). The conclusions of and principles for the examination and evaluation are described first. The studies carried out are focused on the safety of the facilities, and it is concluded that part of the proposed change is appropriate with respect to the required technical capability and that part of the change will not have adverse effects on the safety design of the facilities. The examination of the safety design of the reactor facilities cover the reactivity control, new material for the steam generator, design of chemical and volume control systems, design of liquid waste treatment facilities, integration of all confinement vessel spray rings, and design of the diesel power generator. It is confirmed that all of them can meet the safety requirements. Studies and analyses are also made of the emission of radiations to the surrounding environment, abnormal transient changes during operations, and possible accidents. (Nogami, K.)

  17. Environmental Control Plan for the Industrial Hygiene Field Services Facility

    International Nuclear Information System (INIS)

    Donnelly, J.W.

    2000-01-01

    This environmental control plan is for the Hanford Site's Industrial Hygiene Field Services Facility, located in the 100-N Area. This facility is used for the maintenance and storage of respirators, respiratory equipment and testing, calibration and testing of industrial hygiene equipment, and asbestos fiber counting

  18. Risk Control of Offshore Installations. A Framework for the Establishment of Risk Indicators

    Energy Technology Data Exchange (ETDEWEB)

    Oeien, Knut

    2001-07-01

    Currently quantitative risk assessments are carried out to analyze the risk level of offshore installations and to evaluate whether or not the risk level is acceptable. By way of the quantitative risk analysis the risk status of a given installation is obtained. However, the risk status is obtained so infrequently that it is inadequate for risk control. It can be compared to economic control having the economic status presented about each fifth year, which is obviously inadequate. It is important to know the risk status because this may provide an early warning about the need for remedial actions. Without frequent information about the risk status, control of risk cannot be claimed. The main objective of this thesis has been the development of a framework for the establishment of risk indicators. These risk indicators provide a status of the risk level through measuring of changes in technical, operational and organizational factors important to risk, and is thus a means to control risk during operation of offshore petroleum installations. The framework consists of a technical methodology using the quantitative risk assessment as a basis, an organizational model, and an organizational quantification methodology. Technical risk indicators are established from the technical methodology covering the risk factors explicitly included in the quantitative risk assessment. Organizational risk indicators measure changes in the organizational risk factors included in the organizational model, but not included in the quantitative risk assessment. The organizational model is an extension to the risk model in the quantitative risk assessment. The organizational quantification methodology calculates the effect of the changes measured by the organizational risk indicators. The organizational model may also be applied as a qualitative tool for root cause analysis of incidents (process leaks). Other results are an intermediate-level expert judgment procedure applicable for

  19. Control of radiation in animal facilities

    International Nuclear Information System (INIS)

    Hightower, D.; Hood, D.M.; Neff, R.D.

    1977-01-01

    Use of radioactive materials in animals for research and clinical studies is on the increase. These studies may be undertaken with little or no disruption of normal facility operations if a few facts are considered. The primary factor of consideration is the radiopharmaceutical - its pharmacologic behavior and physical characteristics. The preferred radionuclide is one with the shortest half-life compatible with the variables to be measured. The fact that an animal is a source of radiation as well as a potential source of contamination must be kept in mind. Improper use of radiopharmaceuticals is inexcusable

  20. CSNI collective statement on support facilities for existing and advanced reactors. The function of OECD/Nea joint projects Nea committee on the safety of nuclear installations (CSNI)

    International Nuclear Information System (INIS)

    2008-01-01

    The NEA Committee on the Safety of Nuclear Installations (CSNI) has recently completed a study on the availability and utilisation of facilities supporting safety studies for current and advanced nuclear power reactors. The study showed that significant steps had been undertaken in the past several years in support of safety test facilities, mainly by conducting multinational joint projects centered on the capability of unique test facilities worldwide. Given the positive experience of the safety research projects, it has been recommended that efforts be made to prioritize technical issues associated with advanced (Generation IV) reactor designs and to develop options on how to efficiently obtain the necessary data through internationally co-ordinated research, preparing a gradual extension of safety research beyond the needs set by currently operating reactors. This statement constitutes a reference for future CSNI activities and for safety authorities, R and D centres and industry for internationally co-ordinated research initiatives in the nuclear safety research area. (author)

  1. Regulatory control and challenges in Medical facilities using ionising radiation sources

    International Nuclear Information System (INIS)

    Agarwal, S.P.

    2008-01-01

    Medical facilities utilising ionising radiation sources for diagnostic and treatment of cancer are regulated under the provisions of Atomic Energy (Radiation Protection) Rules, 2004 promulgated under the Atomic Energy Act 1962. The Competent Authority for the enforcement of the rules is Chairman, Atomic Energy Regulatory Board (AERB). Practice specific codes are issued by AERB for medical facilities such as Radiotherapy, Nuclear Medicine and Radiology. Regulatory process for control of medical facilities covers the entire life cycle of the radiation sources in three stages viz pre-Iicensing, during useful life and decommissioning and disposal. Pre-Iicensing requirements include use of type approved sources and equipment, approval of design layout of the facility and installation, exclusive (safe and secure) source storage facility when the equipment is not in use, radiation (area/individual) monitoring devices, qualified, trained and certified manpower, emergency response plans and commitment from the licensee for the safe disposal of disused/decayed sources. Compliance to these requirements makes the applicant eligible to obtain license from AERB for the operation of the medical facility. During the use of radiation sources, specific prior approval of the Competent Authority is required in respect of every source replacement, sale, transfer, transport, import and export. Further, all licensees are required to send the periodic safety Status reports to AERB as well as reporting of any off normal events. AERB conducts inspection of the facilities to ensure compliance with the safety requirements during operation of the facility. Violation of safety norms by licensee attracts enforcement action which includes suspension, modification or withdrawal of licensee for operation of the facility. Upon completion of the useful life of the source, the licensee decommissions the facility and returns the source to the original supplier. For returning the source, prior

  2. Material accountancy and control practice at a research reactor facility

    International Nuclear Information System (INIS)

    Bouchard, J.; Maurel, J.J.; Tromeur, Y.

    1982-01-01

    This session surveys the regulations, organization, and accountancy practice that compose the French State System of Accountancy and Control. Practical examples are discussed showing how inventories are verified at a critical assembly facility and at a materials testing reactor

  3. Computerized system controls Canadian training facility

    International Nuclear Information System (INIS)

    Dingwall, K.

    1996-01-01

    The Petroleum Industry Training Service (PITS), a non-profit organization headquartered in Calgary, Alberta, Canada, has earned a reputation as the most sophisticated training organization of its kind. Backed by such resources as the $25-million Nisku Training Center, located on a 38-acre site near Edmonton, PITS provides present and future petroleum engineers/operators/administrators with on-the-job experience in every facet of oil/gas processing. Nearly 3,000 students attend the Nisku training facility each year. Courses range in length from one day to six months, on topics as diverse as petroleum engineering, field production, drilling and well service, safety, environmental impact and management. Designed to teach skills needed at all levels, the courses fulfill an important educational need for firms with both new hires and seasoned personnel. PITS certificates are well-recognized by industry and government agencies

  4. 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

  5. Protection against falldown from roofs during installation of photovoltaic facilities; Schutz gegen Absturz von Daechern bei der Montage von Photovoltaikanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Lux, Reinhard [Berufsgenossenschaft Energie Textil Elektro Medienerzeugnisse (BGETEM), Koeln (Germany). Fachbereich Maschinen und Anlagen

    2010-07-15

    The increasing number of photovoltaic systems that are installed and must be maintained has brought about a higher number of accidents. In particular, accidents involving falls from roofs are very serious and often fatal. The contribution outlines the pertinent legal regulations and technical rules, prevents a systematik risk classification, and lists established and effective protection measures. (orig.)

  6. Installation and management of the SPS and LEP control system computers

    International Nuclear Information System (INIS)

    Bland, Alastair

    1994-01-01

    Control of the CERN SPS and LEP accelerators and service equipment on the two CERN main sites is performed via workstations, file servers, Process Control Assemblies (PCAs) and Device Stub Controllers (DSCs). This paper describes the methods and tools that have been developed to manage the file servers, PCAs and DSCs since the LEP startup in 1989. There are five operational DECstation 5000s used as file servers and boot servers for the PCAs and DSCs. The PCAs consist of 90 SCO Xenix 386 PCs, 40 LynxOS 486 PCs and more than 40 older NORD 100s. The DSCs consist of 90 OS-968030 VME crates and 10 LynxOS 68030 VME crates. In addition there are over 100 development systems. The controls group is responsible for installing the computers, starting all the user processes and ensuring that the computers and the processes run correctly. The operators in the SPS/LEP control room and the Services control room have a Motif-based X window program which gives them, in real time, the state of all the computers and allows them to solve problems or reboot them. ((orig.))

  7. Upgrade of the Los Alamos Plutonium Facility control system

    International Nuclear Information System (INIS)

    Pope, N.G.; Turner, W.J.; Brown, R.E.; Bibeau, R.A.; Davis, R.R.; Hogan, K.

    1996-01-01

    After 20 yrs service, the Los Alamos Plutonium Facility is undergoing an upgrade to its aging Facility Control System. The new system design includes a network of redundantly-paired programmable logic controllers that will interface with about 2200 field data points. The data communications network that has been designed includes a redundant, self-healing fiber optic data highway as well as a fiber optic ethernet. Commercially available human-machine interface software running on a UNIX-based system displays facility subsystem status operator X-terminals. Project design features, methods, costs, and schedule are discussed

  8. Apparatus for installing and removing a control rod drive in a nuclear reactor

    International Nuclear Information System (INIS)

    Turner, A.P.L.; Ward, R.

    1989-01-01

    This patent describes an apparatus for installing and removing a control rod drive from beneath the pressure vessel of a nuclear reactor. It consists of elevator carriage for carrying the control rod drive into and out of the region beneath the pressure vessel in a generally horizontal position, an elevator cradle mounted on the carriage for pivotal movement about an axis between horizontal and vertical positions and for vertical movement, when in the vertical position, means for securing the control rod drive to the elevator cradle, and a winch cart movable horizontally between a first position spaced from the pivot axis and a second position near the pivot axis. The cart has a winch cable supporting the lower end of the elevator carriage for moving the elevator carriage and the control rod drive between horizontal and vertical positions on the elevator carriage when the cart is spaced from the pivot axis and for raising and lowering the elevator cradle and the control rod drive when the cart is positioned near the pivot axis. The control rod drive is mounted on the elevator cradle by a bearing permitting rotational and horizontal movement of the control rod drive when the drive is in a vertical position, a swing arm, a pneumatically actuated cylinder in axial alignment with the control rod drive for raising and lowering the control rod drive, and means pivotally mounting the cylinder on the swing arm for movement about an axis spaced from and generally parallel to the vertically extending axis so that the position of the cylinder and the control rod drive can be shifted horizontally about the vertically extending axes

  9. The ATF [Advanced Toroidal Facility] Status and Control System

    International Nuclear Information System (INIS)

    Baylor, L.R.; Devan, W.R.; Sumner, J.N.; Alban, A.M.

    1987-01-01

    The Advanced Toroidal Facility (ATF) Status and Control System (SCS) is a programmable controller-based state monitoring and supervisory control system. This paper describes the SCS implementation and its use of a host computer to run a commercially available software package that provides color graphic interactive displays, alarm logging, and archiving of state data

  10. Measurement control program at model facility

    International Nuclear Information System (INIS)

    Schneider, R.A.

    1984-01-01

    A measurement control program for the model plant is described. The discussion includes the technical basis for such a program, the application of measurement control principles to each measurement, and the use of special experiments to estimate measurement error parameters for difficult-to-measure materials. The discussion also describes the statistical aspects of the program, and the documentation procedures used to record, maintain, and process the basic data

  11. National Ignition Facility integrated computer control system

    International Nuclear Information System (INIS)

    Van Arsdall, P.J. LLNL

    1998-01-01

    The NIF design team is developing the Integrated Computer Control System (ICCS), which is based on an object-oriented software framework applicable to event-driven control systems. The framework provides an open, extensible architecture that is sufficiently abstract to construct future mission-critical control systems. The ICCS will become operational when the first 8 out of 192 beams are activated in mid 2000. The ICCS consists of 300 front-end processors attached to 60,000 control points coordinated by a supervisory system. Computers running either Solaris or VxWorks are networked over a hybrid configuration of switched fast Ethernet and asynchronous transfer mode (ATM). ATM carries digital motion video from sensors to operator consoles. Supervisory software is constructed by extending the reusable framework components for each specific application. The framework incorporates services for database persistence, system configuration, graphical user interface, status monitoring, event logging, scripting language, alert management, and access control. More than twenty collaborating software applications are derived from the common framework. The framework is interoperable among different kinds of computers and functions as a plug-in software bus by leveraging a common object request brokering architecture (CORBA). CORBA transparently distributes the software objects across the network. Because of the pivotal role played, CORBA was tested to ensure adequate performance

  12. Fermilab accelerator control system: Analog monitoring facilities

    International Nuclear Information System (INIS)

    Seino, K.; Anderson, L.; Smedinghoff, J.

    1987-10-01

    Thousands of analog signals are monitored in different areas of the Fermilab accelerator complex. For general purposes, analog signals are sent over coaxial or twinaxial cables with varying lengths, collected at fan-in boxes and digitized with 12 bit multiplexed ADCs. For higher resolution requirements, analog signals are digitized at sources and are serially sent to the control system. This paper surveys ADC subsystems that are used with the accelerator control systems and discusses practical problems and solutions, and it describes how analog data are presented on the console system

  13. Can administrative referenda be an instrument of control over large-scale technical installations?

    International Nuclear Information System (INIS)

    Rossnagel, A.

    1986-01-01

    An administrative referendum offers the possibility of direct participation of the citizens in decisions concerning large-scale technical installations. The article investigates the legal status of such a referendum on the basis of constitutional and democratic principles. The conclusion drawn is that any attempt to realize more direct democracy in a concrete field of jurisdiction of the state will meet with very large difficulties. On the other hand, the author clearly states more direct democracy for control over the establishment of large-scale technology to be sensible in terms of politics and principles of democracy, and possible within the constitutional system. Developments towards more direct democracy would mean an enhancement of representative democracy and would be adequate vis a vis the problems posed by large-scale technology. (HSCH) [de

  14. Regulations concerning licensing of nuclear reactor facilities and other nuclear installations, Decree No 7/9141, 6 January 1975

    International Nuclear Information System (INIS)

    1975-01-01

    This Decree lays down the licensing system for nuclear installations in Turkey and also sets up a Nuclear Safety Committee whose duty is to ensure that the requirements of this Decree are met. The Committee is made up of members of the Atomic Energy Commission specialized in reactors, nuclear safety, health physics, reactor physics as well as two experts respectively appointed by the Ministry of Health and Social Welfare and the Ministry of Energy and National Resources. (NEA) [fr

  15. Changes in radiological protection and quality control in Spanish dental installations: 1996-2003.

    Science.gov (United States)

    Alcaraz-Baños, Miguel; Parra-Pérez, María del Carmen; Armero-Barranco, David; Velasco-Hidalgo, Francisco; Velasco-Hidalgo, Esteban

    2009-10-01

    The European Union has established specific directives concerning radiological protection which are obligatory for member States. In addition, all Spanish dental clinics with radiological equipment are required to have an annual quality control check. To analyze the effect of new European legislation on dental radiological practice in Spain and to determine whether it has resulted in lower doses being administered to patients. A total of 10,171 official radiological quality control reports on Spanish dental clinics, covering 16 autonomous regions, were studied following the passing of Royal Decree 2071/1995 on quality criteria in radiodiagnostic installations. The reports, compiled by U.T.P.R Asigma S.A., a company authorised by the Nuclear Safety Council, cover the years 1996 to 2003, which has enabled us to monitor the evolution of radiological procedures in dental clinics over a seven year period. According to the reports for 2003, 77.3 % of clinics complied with EU requirements, using equipment of 70 kVp, 8 mA, 1.5 mm Al filters, with a collimator length of 20 cm. However, non-compliance was detected in approximately a third (30.8%) of the equipment inspected: alterations in the kilovoltage used, exposure time, performance of the tubing, dosage, linearity/intensity of current and acoustic-luminous signal 6.86%. The mean skin dose reached 3.11 mGy for patients who received an x-ray of an upper molar, representing a decrease of 18% over the seven years studied. there has obviously been a general improvement in the parameters studied, but only 77.3% of the installations complied fully with official EU regulations concerning dental radiological protection.

  16. 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)

  17. Optimal control of hydroelectric facility incorporating pump storage

    International Nuclear Information System (INIS)

    Zhao, Guangzhi; Davison, Matt

    2009-01-01

    We consider a simple model of a pump-assisted hydroelectric facility operating in a market with time-varying but deterministic power prices and constant water inflows. The engineering details of the facility are described by a model containing several parameters. We present an algorithm for optimizing first the energy and then the profit produced by these plants. This algorithm allows us to describe the relationships between control trajectory and time, and between inflow and price. Remarkably, we see that under some reasonable choices of facility parameters and for power prices that are not extremely variable, the optimal profit operation of these facilities is not too different from their optimal energy operation, and the control is less affected by the price as the inflow rate increases. (author)

  18. Control of DWPF [Defense Waste Processing Facility] melter feed composition

    International Nuclear Information System (INIS)

    Edwards, R.E. Jr.; Brown, K.G.; Postles, R.L.

    1990-01-01

    The Defense Waste Processing Facility will be used to immobilize Savannah River Site high-level waste into a stable borosilicate glass for disposal in a geologic repository. Proper control of the melter feed composition in this facility is essential to the production of glass which meets product durability constraints dictated by repository regulations and facility processing constraints dictated by melter design. A technique has been developed which utilizes glass property models to determine acceptable processing regions based on the multiple constraints imposed on the glass product and to display these regions graphically. This system along with the batch simulation of the process is being used to form the basis for the statistical process control system for the facility. 13 refs., 3 figs., 1 tab

  19. Recent trends of plutonium facilities and their control

    Energy Technology Data Exchange (ETDEWEB)

    Muto, T [Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works

    1974-02-01

    Much interest has been focussed on Pu recycle since the oil crisis because of an expected shortage of enriched uranium. Plutonium handling techniques and plutonium fuel fabricating facilities should be developed to meet the future demand of plutonium, but the radioactive property of plutonium to be reprocessed from spent fuel and recycled plutonium is remarkably different, and it has to be handled safely. Technical criteria for plutonium facilities are specified in the USAEC regulatory guides and other rules. Some of these criteria are location condition, quality of confinement, protection against accidents and so on. The control conditions for plutonium facilities are exposure control, criticality control, measurement control and new system of safeguard. These problems are under development to meet the future requirement for the safe handling of Pu material.

  20. Preliminary assessment report for Virginia Army National Guard Army Aviation Support Facility, Richmond International Airport, Installation 51230, Sandston, Virginia

    International Nuclear Information System (INIS)

    Dennis, C.B.

    1993-09-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Virginia Army National Guard (VaARNG) property in Sandston, Virginia. The Army Aviation Support Facility (AASF) is contiguous with the Richmond International Airport. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The PA is designed to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. The AASF, originally constructed as an active Air Force interceptor base, provides maintenance support for VaARNG aircraft. Hazardous materials used and stored at the facility include JP-4 jet fuel, diesel fuel, gasoline, liquid propane gas, heating oil, and motor oil

  1. Remote control of a fusion facility

    Energy Technology Data Exchange (ETDEWEB)

    Schissel, D.P. [General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States)], E-mail: schissel@fusion.gat.com; Abla, G.; Humphreys, D.A.; Penaflor, B.G.; Sammuli, B.S.; Walker, M.L. [General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States)

    2009-06-15

    Magnetic fusion experiments keep growing in size and complexity resulting in a concurrent growth in collaboration between experimental sites and laboratories worldwide. This scientific collaboration activity is strong at existing experimental sites, is a major element of machines just coming on line, and is also a thrust of experiments that will come on line in the next decade. Computer science research into enhancing the ability to scientifically participate in a fusion experiment remotely has been growing in size in an attempt to better address the needs of fusion scientists worldwide. The natural progression of this research is to examine how to move from remote scientific participation to remote hardware control. This paper examines the challenges associated with remote experimental device control and proposes a solution based on a semantic approach that defines a Gatekeeper software system that will be the only channel of interaction for incoming requests to the experimental site. The role of the Gatekeeper is to validate the identification and access privilege of the requestor and to ensure the validity of the proposed request. The Gatekeeper will be a modular system, transparent to end-users, and allow a high volume of activity.

  2. Remote control of a fusion facility

    International Nuclear Information System (INIS)

    Schissel, D.P.; Abla, G.; Humphreys, D.A.; Penaflor, B.G.; Sammuli, B.S.; Walker, M.L.

    2009-01-01

    Magnetic fusion experiments keep growing in size and complexity resulting in a concurrent growth in collaboration between experimental sites and laboratories worldwide. This scientific collaboration activity is strong at existing experimental sites, is a major element of machines just coming on line, and is also a thrust of experiments that will come on line in the next decade. Computer science research into enhancing the ability to scientifically participate in a fusion experiment remotely has been growing in size in an attempt to better address the needs of fusion scientists worldwide. The natural progression of this research is to examine how to move from remote scientific participation to remote hardware control. This paper examines the challenges associated with remote experimental device control and proposes a solution based on a semantic approach that defines a Gatekeeper software system that will be the only channel of interaction for incoming requests to the experimental site. The role of the Gatekeeper is to validate the identification and access privilege of the requestor and to ensure the validity of the proposed request. The Gatekeeper will be a modular system, transparent to end-users, and allow a high volume of activity.

  3. Qt based control system software for Low Energy Accelerator Facility

    International Nuclear Information System (INIS)

    Basu, A.; Singh, S.; Nagraju, S.B.V.; Gupta, S.; Singh, P.

    2012-01-01

    Qt based control system software for Low Energy Accelerating Facility (LEAF) is operational at Bhabha Atomic Research Centre (BARC), Trombay, Mumbai. LEAF is a 50 keV negative ion electrostatic accelerator based on SNICS ion source. Control system uses Nokia Trolltech's QT 4.x API for control system software. Ni 6008 USB based multifunction cards has been used for control and read back field equipments such as power supplies, pumps, valves etc. Control system architecture is designed to be client server. Qt is chosen for its excellent GUI capability and platform independent nature. Control system follows client server architecture. The paper will describe the control system. (author)

  4. Radioactive material inventory control at a waste characterization facility

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  5. Design, Fabrication, Installation and Commissioning of the Helium Refrigeration system Supporting Superconducting Radio Frequency Testing at Facility for Rare Isotope Beams at Michigan State University

    Science.gov (United States)

    Casagrande, F.; Fila, A.; Nguyen, C.; Tatsumoto, H.

    2017-12-01

    The Facility for Rare Isotope Beams (FRIB) will be a scientific user facility for the Office of Nuclear Physics in the U.S. Department of Energy Office of Science (DOE-SC). The FRIB linear accelerator (LINAC) will be comprised of cryomodules each with multiple Superconducting Radio Frequency (SRF) cavities operating at 2 K. A helium refrigeration system was designed, fabricated, installed and commissioned in the SRF high bay building to test and certify these cavities and cryomodules before installation in the FRIB LINAC tunnel. The helium refrigeration system includes a helium refrigerator which has nominal capacity of 900 W at 4 K, 5000 L liquid helium storage Dewar, helium gas storage, two room temperature vacuum pumps capable of 2.5 g/s each for 2 K testing, purifier, purifier recovery compressor, and the distribution system for liquid nitrogen and helium. The helium refrigeration system is now operational supporting three below grade cavity testing Dewars and one cryomodule testing bunker meeting the required throughput of 1 cavity per day.

  6. Control Rod Drive Mechanism Installed in the Internal of Reactor Pressure Vessel

    Energy Technology Data Exchange (ETDEWEB)

    Choi, M. H.; Choi, S.; Park, J. S.; Lee, J. S.; Kim, D. O.; Hur, N. S.; Hur, H.; Yu, J. Y

    2008-09-15

    This report describes the review results and important technologies related to the in-vessel type control rod drive mechanism. Generally, most of the CRDMs used in the PWR are attached outside of the reactor pressure vessel, and the pernetration of the vessel head can not avoid. However, in-vessel type CRDMs, which are installed inside the reactor vessel, can eliminate the possibility of rod ejection accidents and the penetration of the vessel head, and provide a compact design of the reactor vessel and containment. There are two kinds of in-vessel type CRDM concerning the driving force-driven by a driving motor and by a hydraulic force. Motor driven CRDMs have been mainly investigated in Japan(MRX, IMR, DRX, next generation BWR etc.), and developed the key components such as a canned motor, an integrated rod position indicator, a separating ball-nut and a ball bearing that can operate under the water conditions of a high temperature and pressure. The concept of hydraulically driven CRDMs have been first reported by KWU and Siemens for KWU 200 reactor, and Argentina(CAREM) and China(NHR-5, NHR-200) have been developed the internal CRDM with the piston and cylinder of slightly different geometries. These systems are driven by the hydraulic force which is produced by pumps outside of the reactor vessel and transmitted through a pipe penetrating the reactor vessel, and needs complicated control and piping systems including pumps, valves and pipes etc.. IRIS has been recently decided the internal CRDMs as the reference design, and an analytical and experimental investigations of the hydraulic drive concept are performed by POLIMI in Italy. Also, a small French company, MP98 has been developed a new type of control rods, called 'liquid control rods', where reactivity is controlled by the movement of a liquid absorber in a manometer type device.

  7. Study on the state-of-the-arts technologies and policy trends for the decommissioning of nuclear installations and facilities

    International Nuclear Information System (INIS)

    Jeong, G. J.; Park, J. H.; Jeong, U. S. and others

    2005-12-01

    D and D project of the nuclear facilities is now the one of the biggest projects among the nuclear ones in the world. The nuclear facilities have their unique characteristics so making preparations about technical research in advance is very important in economic side and worker's protection side. Especially, because workers have a high possibility to contact radioactive material directly, an automation technology and shielding technology for worker's protection as well as a system development which can perform D and D work efficiently are necessary for D and D project. The waste reduction technology development, D and D equipment development, container development, and the study related the establishment of the level of the release regulation for radioactive waste are also important. The purpose of this research is to grasp of the national and internal D and D status for the nuclear facilities and to estimate them so we expect to prevent the possibility of a tremendous economical loss as the initiative of the nuclear D and D market is lost due to not understand the situation about the status of the related technologies. And we also expect to practical use the accumulated experience to decommissioning facilities in North

  8. Closed-circuit television and remote crane control for vitrification facilities

    International Nuclear Information System (INIS)

    Bennett, P.R.; Morrison, J.E.

    1986-01-01

    The Defense Waste Processing Facility is currently under construction at the Savannah River Plant. Within the main process cell (MPC), a 117-ton capacity bridge crane is to be installed to facilitate remote handling and processing operations. E. I. du Pont de Nemours and Company defined and PRC designed and built an operational prototype closed-circuit television (CCTV) and remote control system. Phase I of the program developed the CCTV system to prove the feasibility of a remote viewing system. The phase II program added full crane functional remote control and installed it on an existing hot canyon crane. This prototype system established the criteria for the development of the MPC crane and future crane systems. Parameters were: (a) failsafe assurance, (b) high liability, (c) ease of maintenance for dressed-out personnel, (d) rapid malfunction diagnosis, (e) ergonomics, (f) known picture orientation, and (g) audio system to monitor operational sounds. The complete system has undergone a total demonstration of its operational capabilities using simulator circuits for crane functions and is now being integrated with the crane for a full operational demonstration. The system will then be mothballed pending installation by construction personnel ready for cold startup of the plant in 1988

  9. A database system for the control of radioactive effluents generated by the IPEN-CNEN/SP installations

    International Nuclear Information System (INIS)

    Maduar, M.F.

    1992-01-01

    A PC-compatible database system has been developed in order to optimize the control of liquid and gaseous effluents generated by the installations of IPEN-CNEN/SP. The system implements source-term generation, optimizes the discharge control of the effluents and allows several ways for the retrieval of data concerning to the effluents. (author)

  10. National Ignition Facility TestController for automated and manual testing

    Energy Technology Data Exchange (ETDEWEB)

    Zielinski, Jason, E-mail: fishler2@llnl.gov [Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States)

    2012-12-15

    The Controls and Information Systems (CIS) organization for the National Ignition Facility (NIF) has developed controls, configuration and analysis software applications that combine for several million lines of code. The team delivers updates throughout the year, from major releases containing hundreds of changes to patch releases containing a small number of focused updates. To ensure the quality of each delivery, manual and automated tests are performed using the NIF TestController test infrastructure. The TestController system provides test inventory management, test planning, automated and manual test execution, release testing summaries and results search, all through a web browser interface. As part of the three-stage software testing strategy, the NIF TestController system helps plan, evaluate and track the readiness of each release to the NIF production environment. After several years of use in testing NIF software applications, the TestController's manual testing features have been leveraged for verifying the installation and operation of NIF Target Diagnostic hardware. The TestController recorded its first test results in 2004. Today, the system has recorded the execution of more than 160,000 tests and continues to play a central role in ensuring that NIF hardware and software meet the requirements of a high reliability facility. This paper describes the TestController system and discusses its use in assuring the quality of software delivered to the NIF.

  11. National Ignition Facility TestController for automated and manual testing

    International Nuclear Information System (INIS)

    Zielinski, Jason

    2012-01-01

    The Controls and Information Systems (CIS) organization for the National Ignition Facility (NIF) has developed controls, configuration and analysis software applications that combine for several million lines of code. The team delivers updates throughout the year, from major releases containing hundreds of changes to patch releases containing a small number of focused updates. To ensure the quality of each delivery, manual and automated tests are performed using the NIF TestController test infrastructure. The TestController system provides test inventory management, test planning, automated and manual test execution, release testing summaries and results search, all through a web browser interface. As part of the three-stage software testing strategy, the NIF TestController system helps plan, evaluate and track the readiness of each release to the NIF production environment. After several years of use in testing NIF software applications, the TestController's manual testing features have been leveraged for verifying the installation and operation of NIF Target Diagnostic hardware. The TestController recorded its first test results in 2004. Today, the system has recorded the execution of more than 160,000 tests and continues to play a central role in ensuring that NIF hardware and software meet the requirements of a high reliability facility. This paper describes the TestController system and discusses its use in assuring the quality of software delivered to the NIF.

  12. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

  13. The inner-city Skater Facility - playground or control mechanism?

    DEFF Research Database (Denmark)

    Gravesen, David Thore

    2016-01-01

    special Social services, School and Police unit), that observe, mingle and socialize at the facility. The social workers affiliated with the SSP understand and define their role in contradiction to the official agenda. The social workers seek to pull the young people off the street and get them to enroll......The inner-city Skater Facility - playground or control mechanism? In 2013, the municipality in Horsens, a medium-sized provincial town in Denmark, bestowed the city's children and young people a skater facility at the city's central squares. Officially, the municipality donated the facility to give...... local children and young people an opportunity to use their leisure time stimulating their bodies, having a great time with friends and other urban dwellers. The gift is accompanied by a number of (more or less camouflaged) crime prevention- and social education agendas, carried out by the SSP (a...

  14. The installations maintenance control using SAP R/3; O controle de manutencao de instalacoes utilizando o SAP R/3

    Energy Technology Data Exchange (ETDEWEB)

    Ribeiro, Robison Tirre; Pereira, Paulo Manoel Borges; Jorge, Kemal Vieira [Transportadora Brasileira Gasoduto Bolivia Brasil S.A., Rio de Janeiro, RJ (Brazil)

    2004-07-01

    TBG (Transportadora Brasileira Gasoduto Bolivia Brasil S.A.) began their operations in 1999 and since the beginning the SAP R/3 PM module (Plant Maintenance) is used for the control of the maintenance activities and to manager the Master Maintenance and Inspection Plans. On these five years, a series of reports and SAP functionalities were developed or configured to adapt the system R/3 to the needs of TBG maintenance. Now, the whole management and control of the surface facilities maintenance (compression station, city gate, measurement station, etc) is accomplished by SAP R/3 system. (author)

  15. A web-based three-tier control and monitoring application for integrated facility management of photovoltaic systems

    Directory of Open Access Journals (Sweden)

    Apostolos Meliones

    2014-01-01

    Full Text Available The architecture of a control system can be designed vertically with the distinction between functional levels. We adopt this layered approach for the design and implementation of a network-based control and monitoring application. In this paper we present the design and implementation of a network-based management application for controlling and monitoring the input and output data of remote equipment aiming at performance macro-observation, alarm detection, handling operation failures, installation security, access control, collection and recording of statistical data and provisioning of reports. The main services provided to the user and operating over the public internet and/or mobile network include control, monitoring, notification, reporting and data export. Our proposed system consists of a front-end for field (site-level control and monitoring as well as a service back-end which undertakes to collect, store and manage data from all remote installations. Hierarchical data acquisition methodology and performance macro-observation are according to the IEC 61724 standard. We have successfully used our control and monitoring application for integrated facility management of photovoltaic plant installations; nevertheless it can be easily migrated to other renewable energy generation installations and remote automation applications in general.

  16. An evaluation on the scenarios of work trajectory during installation of dismantling equipment for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, KwanSeong; Choi, ByungSeon; Moon, JeiKwon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Kang, ShinYoung; Choi, JongWon; Jeong, SeongYoung; Ahn, SangMyeon; Lee, JungJun

    2016-01-01

    Highlights: • An evaluation on the scenarios of work trajectory. • An evaluation using the virtual decommissioning environments. • An evaluation on work movement under radiation environments. - Abstract: This study is intended to suggest an ergonomic evaluation on the working postural comfort. This study issued for the first time a methodology in view of combination between visual field and comfort. Especially, the ergonomic evaluation using the virtual decommissioning environments is user-friendly because setup of physical mock-up environments is difficult. This study verified the front and standing postures are best working postures during movement under radiation environments of nuclear facilities. It is expected that this methodology will make it possible to establish the ergonomic plan for decommissioning of nuclear facilities and safety of decommissioning will be improved and also decommissioning costs also can be reduced.

  17. The Design Fabrication Installation & Evaluation of the Balance Probe Monitor for Large Centrifuges at a National Laboratory Facility.

    Energy Technology Data Exchange (ETDEWEB)

    Gallegos, Jonathan Michael [Univ. of Texas, Austin, TX (United States)

    2016-11-01

    Balance Probe Monitors were designed, fabricated, installed, and evaluated at Sandia National Laboratories (SNL) for the 22,600 g kg (50,000 g lb) direct drive electromotor driven large centrifuges. These centrifuges provide a high onset/decay rate g environment. The Balance Probe Monitor is physically located near a centrifuge’s Capacitance Probe, a crucial sensor for the centrifuge’s sustainability. The Balance Probe Monitor will validate operability of the centrifuge. Most importantly, it is used for triggering a kill switch under the condition that the centrifuge displacement value exceeds allowed tolerances. During operational conditions, the Capacitance Probe continuously detects the structural displacement of the centrifuge and an adjoining AccuMeasure 9000 translates this displacement into an output voltage.

  18. Control and Data Acquisition System of the ATLAS Facility

    International Nuclear Information System (INIS)

    Choi, Ki-Yong; Kwon, Tae-Soon; Cho, Seok; Park, Hyun-Sik; Baek, Won-Pil; Kim, Jung-Taek

    2007-02-01

    This report describes the control and data acquisition system of an integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) facility, which recently has been constructed at KAERI (Korea Atomic Energy Research Institute). The control and data acquisition system of the ATLAS is established with the hybrid distributed control system (DCS) by RTP corp. The ARIDES system on a LINUX platform which is provided by BNF Technology Inc. is used for a control software. The IO signals consists of 1995 channels and they are processed at 10Hz. The Human-Machine-Interface (HMI) consists of 43 processing windows and they are classified according to fluid system. All control devices can be controlled by manual, auto, sequence, group, and table control methods. The monitoring system can display the real time trend or historical data of the selected IO signals on LCD monitors in a graphical form. The data logging system can be started or stopped by operator and the logging frequency can be selected among 0.5, 1, 2, 10Hz. The fluid system of the ATLAS facility consists of several systems including a primary system to auxiliary system. Each fluid system has a control similarity to the prototype plant, APR1400/OPR1000

  19. First 10 kg of naked germanium detectors installed in liquid nitrogen in GENIUS Test-Facility in GRAN-SASSO

    Energy Technology Data Exchange (ETDEWEB)

    Klapdor-Kleingrothaus, H.V. [Max-Planck-Institut fuer Kernphysik, Heidelberg (Germany)

    2004-07-01

    The GENIUS Test Facility has come into operation in Gran Sasso on May 5, 2003 with its first ten kg of naked Ge detectors in liquid nitrogen. This is the first time that this novel technique for extreme background reduction in search for rare decays is applied under the background conditions of an underground laboratory. GENIUS-TF has the potential to check the DAMA evidence for cold dark matter by modulation, and possibly, to improve the accuracy of the recently observed first signal for neutrinoless double beta decay. (orig.)

  20. First 10 kg of naked germanium detectors installed in liquid nitrogen in GENIUS Test-Facility in GRAN-SASSO

    International Nuclear Information System (INIS)

    Klapdor-Kleingrothaus, H.V.

    2004-01-01

    The GENIUS Test Facility has come into operation in Gran Sasso on May 5, 2003 with its first ten kg of naked Ge detectors in liquid nitrogen. This is the first time that this novel technique for extreme background reduction in search for rare decays is applied under the background conditions of an underground laboratory. GENIUS-TF has the potential to check the DAMA evidence for cold dark matter by modulation, and possibly, to improve the accuracy of the recently observed first signal for neutrinoless double beta decay. (orig.)

  1. Centralized computer-based controls of the Nova Laser Facility

    International Nuclear Information System (INIS)

    Krammen, J.

    1985-01-01

    This article introduces the overall architecture of the computer-based Nova Laser Control System and describes its basic components. Use of standard hardware and software components ensures that the system, while specialized and distributed throughout the facility, is adaptable. 9 references, 6 figures

  2. 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.)

  3. Program for upgrading nuclear materials protection, control, and accounting at all facilities within the All-Russian Institute of Experimental Physics (VNIIEF)

    International Nuclear Information System (INIS)

    Yuferev, V.; Zhikharev, S.; Yakimov, Y.

    1998-01-01

    As part of the Department of Energy-Russian program for strengthening nuclear material protection, control, and accounting (MPC and A), plans have now been formulated to install an integrated MPC and A system at all facilities containing large quantities of weapons-usable nuclear material within the All-Russian Institute of Experimental Physics (VNIIEF, Arzamas-16) complex. In addition to storage facilities, the complex houses a number of critical facilities used to conduct nuclear physics research and facilities for developing procedures for disassembly of nuclear weapons

  4. Invasive Species Guidebook for Department of Defense Installations in the Chesapeake Bay Watershed: Identification, Control, and Restoration

    Science.gov (United States)

    2007-11-01

    Crown vetch Coronilla varia MD, VA 14 Leafy spurge Euphorbia esula VA 15 Ground ivy Glechoma hederacea DC, MD, PA, VA, WV 17 Cogongrass Imperata ...INSTALLATIONS IN THE CHESAPEAKE BAY WATERSHED IDENTIFICATION AND CONTROL METHODS Cogongrass ( Imperata cylindrica) Description & Biology – A large

  5. Regulatory control of nuclear facility valves and their actuators

    International Nuclear Information System (INIS)

    1993-01-01

    The methods and procedures by which the Finnish Centre for Radiation and Nuclear Safety (STUK) regulates valves and their actuators in nuclear power plants and in other nuclear facilities are specified in the guide. The scope of regulation depends on the Safety Class of the valve and the actuator in question. The Safety Classification principles for the systems, structures and components of the nuclear power plants are described in the guide YVL 2.1 and the regulatory control of the nuclear facility safety valves is described in the guide YVL 5.4

  6. The inspection of (collective) tapwater installations in 2009. Progress report; De controle van collectieve leidingwaterinstallaties in 2009. Voortgang controletaak

    Energy Technology Data Exchange (ETDEWEB)

    Dik, H.H.J.

    2011-02-15

    For the first time since 2004, less newly build collective tap water installations show shortcomings. This is true for both the first inspection and the follow-up inspections preformed by the water companies. This seems to indicate a break in the trend of previous years where less newly build installations pass inspection without shortcomings. Still, one-third of the inspected installations do not comply with legionella regulations when first inspected. These non-compliances can be the cause of high to very high risk of contamination of the installation or the public mains system. These conclusions are drawn from the inspections preformed in 2009 by the drinking water companies in newly build and existing installations. By order of the Dutch Ministry of Infrastructure and the Environment and the VROM Inspectorate, the Institute for Public Health and the Environment of the Netherlands (RIVM) compile a yearly report since 2004 on the inspection of tap water installations. In 2009 more than 47.000 newly build and existing installations were inspected. The inspections have found and resolved more than 8000 situations of high to very high risk for public health. In existing installations, the number of non-compliance found at first inspections has decreased over the years. At the second inspection of installations that do not comply, the number of non-complying installations increases. The cause of this trend is unknown, and should be investigated. Only a quarter of the installations that must comply with special regulations for the prevention of Legionella (high-priority installations like hospitals, swimming pools, etc.) comply at first inspection. Starting from 2009, these installations are inspected according to a special intervention strategy. It is still too early to see results from this strategy. [Dutch] Voor het eerst sinds 2004 vertonen minder collectieve leidingwaterinstallaties in nieuwbouw gebreken. Dit geldt voor zowel de eerste (basis)controle als de

  7. Safety assessment and quality control of medical x-ray facilities in some hospitals in Ghana

    International Nuclear Information System (INIS)

    Darko, E.O.; Charles, D.F.

    1998-01-01

    Safety assessment and quality control measurements of diagnostic x-ray installations were carried out in five hospitals in Ghana. The study was focused on the siting, design and construction of the buildings housing the x-ray units, assessment of safety systems and devices and measurements of the technical performance, and film processing conditions. The location, inadequacies in the design/construction, unavailability of relevant safety systems and devices, violation of basic safety principles and poor performance of some of the x-ray facilities indicate the need to improve quality control programmes, safety culture and enforcement of regulatory standards in diagnostic x-ray examinations in Ghana. (author). 8 refs., 11 tabs., 8 figs

  8. Applicability of the Critical pathway analysis usually used for nuclear installations, to the control marine environment pollution by heavy metals

    International Nuclear Information System (INIS)

    Franca, E.P.; Pfeiffer, W.C.; Fiszman, M.; Lacerda, L.D. de

    1984-01-01

    The methodology of the controlling radionuclide releases from nuclear facilities by the critical pathway criteria, is given. The use of this methodology for the environmental impact studies for an industry that causes pollution is discussed. (M.A.) [pt

  9. Manual on quality assurance for installation and commissioning of instrumentation, control and electrical equipment in nuclear power plants

    International Nuclear Information System (INIS)

    1989-01-01

    The present Manual on Quality Assurance (QA) for Installation and Commissioning of Instrumentation, Control and Electrical (ICE) Equipment of Nuclear Power Plants contains supporting material and illustrative examples for implementing basic requirements of the quality assurance programme in procurement, receiving, installation and commissioning of this equipment. The Manual on Quality Assurance for Installation and Commissioning of ICE Equipment is designed to supplement and be consistent with the Guidebook as well as with the IAEA Code and Safety Guides on Quality Assurance. It is intended for the use of managerial staff and QA personnel of nuclear power plant owners or the organizations respectively responsible for the legal, technical, administrative and financial aspects of a nuclear power plant. The information provided in the Manual will also be useful to the inspection staff of the regulatory organization in the planning and performance of regulatory inspections at nuclear power plants

  10. Durable Residual Wall Lining (DL) Installation Concepts and Acceptability as an IRS Replacement Tool for Malaria Vector Control

    DEFF Research Database (Denmark)

    Larsen, Marie Louise; Lenau, Torben Anker

    that will eliminate the need for repeated spraying of walls over a period of 3-4 years after installation. The objective of this project was to evaluate a variety of methods for attaching DL to various wall surfaces found in traditional, rural African housing. Assessments were made as to strength of attachment under...... various stresses and appearance after installation. The experiments took place in Anwona village near Obuasi, Ghana with the support and cooperation of AngloGold Ashanti’s Malaria Control Center. 55 mechanical and adhesive products were tested for their ability to hold a static load (simulating long...... observations were included in the DL Installation Manual, the final delivery of this project....

  11. Authorization procedure for the construction and operation of nuclear installations within the EC Member States, including supervision and control

    International Nuclear Information System (INIS)

    Amaducci, Sandro; Didier, J.M.

    1978-01-01

    This report is an updating of the report EUR 5284, Authorization procedure for the construction and operation of nuclear installations within the EEC Member States, prepared in 1974 by J.M. Didier and Associates. Recent developments regarding the authorization procedure for the construction and operation of nuclear installations have taken place in Italy (introduction of a site approval procedure) and in Denmark (adoption of an overall legislation on the subject, however not yet in force). With respect to supervision and control of nuclear installations during construction and operation, competences of, as well as their exercise by, supervisory authorities in all EC Member States, with the exception of Ireland, are also analysed in the current study

  12. Evaluation of the Nuclear Medicine facilities in Minas Gerais state: quality control program of equipment

    International Nuclear Information System (INIS)

    Kubo, Tadeu Takao Almodovar; Biancardi, Rodrigo; Rocha, Adriana Marcia Guimaraes; Ferreira, Denia Romao; Silva, Franciele Aquiles Anjos; Assuncao, Jonathan Buenos Aires; Alves, Ederson Henrique; Almeida, Ana Flavia Batista; Alves, Nathalia Fernandes; Xavier, Faber Henrique Zacarias; Gontijo, Rodrigo Modesto Gadelha; Mamede, Marcelo; Universidade Federal de Minas Gerais

    2017-01-01

    With the reformulation of the CNEN-NN-3.05 standard in December 2013, Brazil's Nuclear Medicine (NMS) services have to perform a greater number of quality controls for SPECT and PET equipment. However, little is known about the reality of the quality control programs of these services regarding the application of the new standard. Thus, in this context, the objective of the present study was to evaluate the quality control program of MNSs in the state of Minas Gerais. All NMSs in the state of Minas Gerais were invited to participate in the project. Of these, 34.48% (20 facilities) agreed to participate in the project, 50.00% (29 facilities) did not respond to the invitation and 15.52%(9 facilities) declined their participation. Thus, as of November 2015, 20 SPECT and 2 PET/CT equipment were evaluated for the performance of the quality control tests recommended by the new CNEN standard. The phantoms required for the evaluation came from the Laboratory of Dosimetry and Quality Control of UFMG. Even with the deadlines set by CNEN for the implementation of the quality control program in the NMSs, more than 50% of the evaluated services did not implement the quality controls, and the absence of specific phantoms is the main reason for the failure. Among the problems found in the installations, the most critical were: collimators with no conditions of use in the clinical routine, linearity problems of the evaluated image and values of image uniformity superior to the limits of acceptance. Problems in the uniformity and linearity of the image found directly impacted the performance of other tests, such as spatial resolution, SPECT performance, among others. In a general way, the NMSs in the state of Minas Gerais evaluated with the present study are in clinical feasible conditions. (author)

  13. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states; Rapport sur le controle de la surete et de la securite des installations nucleaires. Deuxieme partie: la reconversion des stocks de plutonium militaire. L'utilisation des aides accordees aux pays d'Europe centrale et orientale et aux nouveaux etats independants

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2002-07-01

    This report deals with two different aspects of the safety and security of nuclear facilities. The first aspect concerns the reconversion of weapon grade plutonium stocks: the plutonium in excess, plutonium hazards and nuclear fuel potentialities, the US program, the Russian program, the actions of European countries (France, Germany), the intervention of other countries, the unanswered questions (political aspects, uncertainties), the solutions of the future (improvement of reactors, the helium-cooled high temperature reactor technology (gas-turbine modular helium reactor: GT-MHR), the Carlo Rubbia's project). The second aspect concerns the actions carried out by the European Union in favor of the civil nuclear facilities of central and eastern Europe: the European Union competencies through the Euratom treaty, the conclusions of the European audit office about the PHARE and TACIS nuclear programs, the status of committed actions, the coming planned actions, and the critical analysis of the policy adopted so far. (J.S.)

  14. Report on the control of the safety and security of nuclear facilities. Part 2: the reconversion of military plutonium stocks. The use of the helps given to central and eastern Europe countries and to the new independent states; Rapport sur le controle de la surete et de la securite des installations nucleaires. Deuxieme partie: la reconversion des stocks de plutonium militaire. L'utilisation des aides accordees aux pays d'Europe centrale et orientale et aux nouveaux etats independants

    Energy Technology Data Exchange (ETDEWEB)

    Birraux, C

    2002-07-01

    This report deals with two different aspects of the safety and security of nuclear facilities. The first aspect concerns the reconversion of weapon grade plutonium stocks: the plutonium in excess, plutonium hazards and nuclear fuel potentialities, the US program, the Russian program, the actions of European countries (France, Germany), the intervention of other countries, the unanswered questions (political aspects, uncertainties), the solutions of the future (improvement of reactors, the helium-cooled high temperature reactor technology (gas-turbine modular helium reactor: GT-MHR), the Carlo Rubbia's project). The second aspect concerns the actions carried out by the European Union in favor of the civil nuclear facilities of central and eastern Europe: the European Union competencies through the Euratom treaty, the conclusions of the European audit office about the PHARE and TACIS nuclear programs, the status of committed actions, the coming planned actions, and the critical analysis of the policy adopted so far. (J.S.)

  15. Concerning modification of installation plan for reactor (modification of No.3 and No.4 reactor facilities) at Genkai nuclear power plant of Kyushu Electric Power Co., Ltd. (reply to inquiry)

    International Nuclear Information System (INIS)

    1988-01-01

    In response to an inquiry on the title issue, the Nuclear Safety Commission made an examination and submitted the findings to the Minister of International Trade and Industry. The modifications include the construction of combustion facilities for volume reduction of miscellaneous solid wastes. In the facilities, miscellaneous solid wastes will be combusted for volume reduction, and the combustion residue will be cooled with water and processed into glass-like granules, which will be stored in drums in the solid waste storage facilities. It is confirmed that the release of radioactive substances into the environment will be negligible, that the facilities have been designed to the Class B anti-earthquake standards, and that radiation monitors will be installed. The modifications also include the installation of an improved cement solidification system to replace a conventional-type system and a change in the capacity of the solid waste storage facilities. It is concluded that all proposed modifications should be approved. (Nogami, K.)

  16. Dismantling of nuclear facilities: the industrial know-how; Demantelement des installations nucleaires: les voies de la maitrise industrielle

    Energy Technology Data Exchange (ETDEWEB)

    Lellament, R. [Societe Francaise d' Energie Nucleaire (SFEN), Groupe de Reflexion Energie/Environnement, 75 - Paris (France)

    2004-11-01

    Numerous nuclear facilities in laboratories or research reactors have been decommissioned and dismantled over the 2 last decades throughout the world. The valuable feedback experience has allowed nuclear industry to design, upgrade and test specific techniques for dismantling. These techniques are efficient although they have been validated on a reduced number of nuclear power plants. In France only 3 power units have been dismantled: Chinon A1, A2 and Brennilis (EL4) and they are not representative of the real park of EDF'reactors. 6 PWR-type reactors have already been dismantled in the Usa. The results of a survey concerning 26 countries shows that the dismantling cost is around 320 dollars/kWe, it represents 15% of the construction cost which is far from being excessive as it is often read in the media. The dismantling costs can be broken into: - de-construction (25-55%), - wastes from dismantling (17-43%), - security and monitoring (8-13%), - site reclamation (5-13%), and - engineering and project management (5-24%). (A.C.)

  17. Control of occupational exposure in nuclear facilities for terrestrial support to marine vessels; Controle de exposição dos indivíduos em instalações nucleares de apoio terrestre a embarcações marítimas

    Energy Technology Data Exchange (ETDEWEB)

    Lara, E.G., E-mail: evelise.lara@gmail.com [Universidade Federal de Minas Gerais - UFMG, Belo Horizonte-MG (Brazil); Pinheiro, A.R.M.; Borsoi, S.S.; Silva, T.P., E-mail: andrericardopinheiro@gmail.com, E-mail: sadborsoi@usp.br, E-mail: thiago_padilhasilva@poli.ufrj.br [Escola Politécnica, Universidade de São Paulo - POLI-USP, São Paulo-SP (Brazil); Baroni, D.B.; Santos, F.C., E-mail: dbbaroni@gmail.com, E-mail: felipecruz.santos1@gmail.com [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo-SP (Brazil)

    2017-07-01

    This study addresses some basic requirements for exposure control of occupational exposure during the design phase of ground-based nuclear facilities for marine vessels. US regulatory guidelines, CNEN standards and experiences acquired in conventional nuclear installations were used. The installation design should consider the provision of mobile devices for monitoring and decontamination. Finally, it is observed that the establishment of additional exposure control criteria can directly impact the civil, architectural and electromechanical projects of the facility, from the conceptual phase.

  18. The Overview of the National Ignition Facility Distributed Computer Control System

    International Nuclear Information System (INIS)

    Lagin, L.J.; Bettenhausen, R.C.; Carey, R.A.; Estes, C.M.; Fisher, J.M.; Krammen, J.E.; Reed, R.K.; VanArsdall, P.J.; Woodruff, J.P.

    2001-01-01

    The Integrated Computer Control System (ICCS) for the National Ignition Facility (NIF) is a layered architecture of 300 front-end processors (FEP) coordinated by supervisor subsystems including automatic beam alignment and wavefront control, laser and target diagnostics, pulse power, and shot control timed to 30 ps. FEP computers incorporate either VxWorks on PowerPC or Solaris on UltraSPARC processors that interface to over 45,000 control points attached to VME-bus or PCI-bus crates respectively. Typical devices are stepping motors, transient digitizers, calorimeters, and photodiodes. The front-end layer is divided into another segment comprised of an additional 14,000 control points for industrial controls including vacuum, argon, synthetic air, and safety interlocks implemented with Allen-Bradley programmable logic controllers (PLCs). The computer network is augmented asynchronous transfer mode (ATM) that delivers video streams from 500 sensor cameras monitoring the 192 laser beams to operator workstations. Software is based on an object-oriented framework using CORBA distribution that incorporates services for archiving, machine configuration, graphical user interface, monitoring, event logging, scripting, alert management, and access control. Software coding using a mixed language environment of Ada95 and Java is one-third complete at over 300 thousand source lines. Control system installation is currently under way for the first 8 beams, with project completion scheduled for 2008

  19. National Ignition Facility Control and Information System Operational Tools

    International Nuclear Information System (INIS)

    Marshall, C.D.; Beeler, R.G.; Bowers, G.A.; Carey, R.W.; Fisher, J.M.; Foxworthy, C.B.; Frazier, T.M.; Mathisen, D.G.; Lagin, L.J.; Rhodes, J.J.; Shaw, M.J.

    2009-01-01

    The National Ignition Facility (NIF) in Livermore, California, is the world's highest-energy laser fusion system and one of the premier large scale scientific projects in the United States. The system is designed to setup and fire a laser shot to a fusion ignition or high energy density target at rates up to a shot every 4 hours. NIF has 192 laser beams delivering up to 1.8 MJ of energy to a ∼2 mm target that is planned to produce >100 billion atm of pressure and temperatures of >100 million degrees centigrade. NIF is housed in a ten-story building footprint the size of three football fields as shown in Fig. 1. Commissioning was recently completed and NIF will be formally dedicated at Lawrence Livermore National Laboratory on May 29, 2009. The control system has 60,000 hardware controls points and employs 2 million lines of control system code. The control room has highly automated equipment setup prior to firing laser system shots. This automation has a data driven implementation that is conducive to dynamic modification and optimization depending on the shot goals defined by the end user experimenters. NIF has extensive facility machine history and infrastructure maintenance workflow tools both under development and deployed. An extensive operational tools suite has been developed to support facility operations including experimental shot setup, machine readiness, machine health and safety, and machine history. The following paragraphs discuss the current state and future upgrades to these four categories of operational tools.

  20. An automated entry control system for nuclear facilities

    International Nuclear Information System (INIS)

    Ream, W.K.; Espinoza, J.

    1985-01-01

    An entry control system to automatically control access to nuclear facilities is described. The design uses a centrally located console, integrated into the regular security system, to monitor the computer-controlled passage into and out of sensitive areas. Four types of entry control points are used: an unmanned enclosed portal with metal and SNM detectors for contraband detection with positive personnel identification, a bypass portal for contraband search after a contraband alarm in a regular portal also with positive personnel identification, a single door entry point with positive personnel identification, and a single door entry point with only a magnetic card-type identification. Security force action is required only as a response to an alarm. The integration of the entry control function into the security system computer is also described. The interface between the entry control system and the monitoring security personnel utilizing a color graphics display with touch screen input is emphasized

  1. Design of Data Acquisition and Control System for Indian Test Facility of Diagnostics Neutral Beam

    International Nuclear Information System (INIS)

    Soni, Jignesh; Tyagi, Himanshu; Yadav, Ratnakar; Rotti, Chandramouli; Bandyopadhyay, Mainak; Bansal, Gourab; Gahluat, Agrajit; Sudhir, Dass; Joshi, Jaydeep; Prasad, Rambilas; Pandya, Kaushal; Shah, Sejal; Parmar, Deepak; Chakraborty, Arun

    2015-01-01

    Highlights: • More than 900 channels Data Acquisition and Control System. • INTF DACS has been designed based on ITER-PCDH guidelines. • Separate Interlock and Safety system designed based on IEC 61508 standard. • Hardware selected from ITER slow controller and fast controller catalog. • Software framework based on ITER CODAC Core System and LabVIEW software. - Abstract: The Indian Test Facility (INTF) – a negative hydrogen ion based 100 kV, 60 A, 5 Hz modulated NBI system having 3 s ON/20 s OFF duty cycle. Prime objective of the facility is to install a full-scale test bed for the qualification of all Diagnostic Neutral Beam (DNB) parameters, prior to installation in ITER. The automated and safe operation of the INTF will require a reliable and rugged instrumentation and control system which provide control, data acquisition (DAQ), interlock and safety functions, referred as INTF-DACS. The INTF-DACS has been decided to be design based on the ITER CODAC architecture and ITER-PCDH guidelines since the technical understanding of CODAC technology gained from this will later be helpful in development of plant system I&C for DNB. For complete operation of the INTF, approximately 900 numbers of signals are required to be superintending by the DACS. In INTF conventional control loop time required is within the range of 5–100 ms and for DAQ except high-end diagnostics, required sampling rates in range of 5 sample per second (Sps) to 10 kSps; to fulfill these requirements hardware components have been selected from the ITER slow and fast controller catalogs. For high-end diagnostics required sampling rates up to 100 MSps normally in case of certain events, therefore event and burst based DAQ hardware has been finalized. Combined use of CODAC core software (CCS) and NI-LabVIEW has been finalized due to the fact that full required DAQ support is not available in present version of CCS. Interlock system for investment protection of facility and Safety system for

  2. Design of Data Acquisition and Control System for Indian Test Facility of Diagnostics Neutral Beam

    Energy Technology Data Exchange (ETDEWEB)

    Soni, Jignesh, E-mail: jsoni@ipr.res.in [Institute for Plasma Research, Bhat, Gandhinagar 382 428, Gujarat (India); Tyagi, Himanshu; Yadav, Ratnakar; Rotti, Chandramouli; Bandyopadhyay, Mainak [ITER-India, Institute for Plasma Research, Gandhinagar 380 025, Gujarat (India); Bansal, Gourab; Gahluat, Agrajit [Institute for Plasma Research, Bhat, Gandhinagar 382 428, Gujarat (India); Sudhir, Dass; Joshi, Jaydeep; Prasad, Rambilas [ITER-India, Institute for Plasma Research, Gandhinagar 380 025, Gujarat (India); Pandya, Kaushal [Institute for Plasma Research, Bhat, Gandhinagar 382 428, Gujarat (India); Shah, Sejal; Parmar, Deepak [ITER-India, Institute for Plasma Research, Gandhinagar 380 025, Gujarat (India); Chakraborty, Arun [Institute for Plasma Research, Bhat, Gandhinagar 382 428, Gujarat (India)

    2015-10-15

    Highlights: • More than 900 channels Data Acquisition and Control System. • INTF DACS has been designed based on ITER-PCDH guidelines. • Separate Interlock and Safety system designed based on IEC 61508 standard. • Hardware selected from ITER slow controller and fast controller catalog. • Software framework based on ITER CODAC Core System and LabVIEW software. - Abstract: The Indian Test Facility (INTF) – a negative hydrogen ion based 100 kV, 60 A, 5 Hz modulated NBI system having 3 s ON/20 s OFF duty cycle. Prime objective of the facility is to install a full-scale test bed for the qualification of all Diagnostic Neutral Beam (DNB) parameters, prior to installation in ITER. The automated and safe operation of the INTF will require a reliable and rugged instrumentation and control system which provide control, data acquisition (DAQ), interlock and safety functions, referred as INTF-DACS. The INTF-DACS has been decided to be design based on the ITER CODAC architecture and ITER-PCDH guidelines since the technical understanding of CODAC technology gained from this will later be helpful in development of plant system I&C for DNB. For complete operation of the INTF, approximately 900 numbers of signals are required to be superintending by the DACS. In INTF conventional control loop time required is within the range of 5–100 ms and for DAQ except high-end diagnostics, required sampling rates in range of 5 sample per second (Sps) to 10 kSps; to fulfill these requirements hardware components have been selected from the ITER slow and fast controller catalogs. For high-end diagnostics required sampling rates up to 100 MSps normally in case of certain events, therefore event and burst based DAQ hardware has been finalized. Combined use of CODAC core software (CCS) and NI-LabVIEW has been finalized due to the fact that full required DAQ support is not available in present version of CCS. Interlock system for investment protection of facility and Safety system for

  3. Identifying the best locations to install flow control devices in sewer networks to enable in-sewer storage

    Science.gov (United States)

    Leitão, J. P.; Carbajal, J. P.; Rieckermann, J.; Simões, N. E.; Sá Marques, A.; de Sousa, L. M.

    2018-01-01

    The activation of available in-sewer storage volume has been suggested as a low-cost flood and combined sewer overflow mitigation measure. However, it is currently unknown what the attributes for suitable objective functions to identify the best location for flow control devices are and the impact of those attributes on the results. In this study, we present a novel location model and efficient algorithm to identify the best location(s) to install flow limiters. The model is a screening tool that does not require hydraulic simulations but rather considers steady state instead of simplistic static flow conditions. It also maximises in-sewer storage according to different reward functions that also considers the potential impact of flow control device failure. We demonstrate its usefulness on two real sewer networks, for which an in-sewer storage potential of approximately 2,000 m3 and 500 m3 was estimated with five flow control devices installed.

  4. Infection control challenges in deployed US military treatment facilities.

    Science.gov (United States)

    Hospenthal, Duane R; Crouch, Helen K

    2009-04-01

    Personnel sustaining combat-related injuries in current overseas conflicts continue to have their care complicated by infections caused by multidrug-resistant organisms, including Acinetobacter, Klebsiella, and Pseudomonas. Although presumed to be due to multiple factors both within and outside of the combat theater, concern has been raised about the difficulties in establishing and maintaining standard infection control (IC) practices in deployed medical treatment facilities and in the evacuation of the injured back to the United States. Level III facilities (hospitals capable of holding patients >72 hours) in Iraq and Afghanistan and the evacuation system from Iraq to the continental US were reviewed by an expert IC-infectious disease team. All reviewed facilities had established IC programs, but these were staffed by personnel with limited IC experience, often without perceived adequate time dedicated to perform their duties, and without uniform levels of command emphasis or support. Proper hand hygiene between patients was not always ideal. Isolation and cohorting of patients to decrease multidrug-resistant organism colonization and infection varied among facilities. Review of standard operating procedures found variability among institutions and in quality of these documents. Application of US national and theater-specific guidelines and of antimicrobial control measures also varied among facilities. Effective IC practices are often difficult to maintain in modern US hospitals. In the deployed setting, with ever-changing personnel in a less than optimal practice environment, IC is even more challenging. Standardization of practice with emphasis on the basics of IC practice (e.g., hand hygiene and isolation procedures) needs to be emplaced and maintained in the deployed setting.

  5. Facility-wide synchronization of standard FAIR equipment controllers

    International Nuclear Information System (INIS)

    Rauch, S.; Terpstra, W.; Panschow, W.; Thieme, M.; Prados, C.; Zweig, M.; Kreider, M.; Beck, D.; Bär, R.

    2012-01-01

    The standard equipment controller under development for the new FAIR accelerator facility is the Scalable Control Unit (SCU). It is designed to synchronize and control the actions of up to 12 purpose-built slave cards, connected in a proprietary crate by a parallel backplane. Inter-crate coordination and facility-wide synchronization are a core FAIR requirement and thus precise timing of SCU slave actions is of vital importance. The SCU consists primarily of two components, an x86 COM Express daughter board and a carrier board with an Altera Arria II GX FPGA, interconnected by PCI Express. The x86 receives configuration and set values with which it programs the real-time event-condition-action (ECA) unit in the FPGA. The ECA unit receives event messages via the timing network, which also synchronizes the clocks of all SCUs in the facility using White Rabbit. Matching events trigger actions on the SCU slave cards such as: ramping magnets, triggering kickers, etc. Timing requirements differ depending on the action taken. For softer real-time actions, an interrupt can be generated for complex processing on the x86. Alternatively, the FPGA can directly fire a pulse out a LEMO output or an immediate SCU bus operation. The delay and synchronization achievable in each case differs and this paper examines the timing performance of each to determine which approach is appropriate for the required actions. (author)

  6. Keeping the Edge. Air Force Materiel Command Cold War Context (1945-1991). Volume 2: Installations and Facilities

    Science.gov (United States)

    2003-08-01

    Acronyms Azon B BART BDR BEEF BEET BEMI-AA BGM BLC BMEWS BMW Bomarc BRAC BRL BUIC BW C C-4 C4I CA CAA CANEL CAT CBS CDS CEBMCO...adaptation of the Naval Hospital in Corona , California. The board’s decision implied that General Armstrong still leaned toward the Naval research hospital...parallel to ones found at the Army’s Fort Detrick in Maryland and at the Center for Disease Control in Atlanta. The segregated area contained a virus and

  7. An Integration Testing Facility for the CERN Accelerator Controls System

    CERN Document Server

    Stapley, N; Bau, J C; Deghaye, S; Dehavay, C; Sliwinski, W; Sobczak, M

    2009-01-01

    A major effort has been invested in the design, development, and deployment of the LHC Control System. This large control system is made up of a set of core components and dependencies, which although tested individually, are often not able to be tested together on a system capable of representing the complete control system environment, including hardware. Furthermore this control system is being adapted and applied to CERN's whole accelerator complex, and in particular for the forthcoming renovation of the PS accelerators. To ensure quality is maintained as the system evolves, and toimprove defect prevention, the Controls Group launched a project to provide a dedicated facility for continuous, automated, integration testing of its core components to incorporate into its production process. We describe the project, initial lessons from its application, status, and future directions.

  8. Global Horizontal Control Network of Shanghai Synchrotron Radiation Facility

    International Nuclear Information System (INIS)

    Yu Chenghao; Ke Ming; Du Hanwen; Yin Lixin; Zhao Zhentang; Dong Lan; Huang Kaixi

    2009-01-01

    As a national big scientific engineering, Shanghai Synchrotron Radiation Facility (SSRF) has rigid requirement to the components with sub-millimeter accuracy. In the process of survey and positioning global control network is a connecting link, which determines the position relationship between building and accelerator devices, and provides high accuracy datum to local control network. Within the designing process, building and devices are very restrict. While among observation, it's hard to be observed and abound with disadvantages. With continuous optimization and careful operation, super-high accuracy of 0.3 mm within 400 m circumference was achieved and slab's periodic movement could be seen through 3 times measurement. (authors)

  9. External radiation exposure control system in accelerator facilities

    International Nuclear Information System (INIS)

    Ogawa, Tatsuhiko; Iimoto, Takeshi; Kosako, Toshiso

    2011-01-01

    The external exposure control systems in KEK and CERN are discussed to find out good practices and unreasonableness of radiation control in accelerator facilities, which plays an important role in optimizing national and/or site specific radiological regulations, referring to relevant ICRP publications. Personal dose limits and radiation area classifications were analyzed and their reasonableness were explored. Good example of supervised areas, area classification based on realistic assumptions on working time etc are found. On the other hand, unreasonable systems, that are often attributed to the national regulation or ideas presented in the old publications are also found. (author)

  10. Installation design of pump motor control systems for supplied of the RSG-GAS secondary raw water cooling system

    International Nuclear Information System (INIS)

    Kiswanto; Teguh Sulistyo; M-Taufik

    2013-01-01

    It has designed already of an installation of the pump motor control system for supplied of raw water to fulfil the RSG-GAS secondary cooling system. The installation design of this plant is used to supply electrical energy from PLN and 3 phase generator to operate the pump motor embedded multilevel type, capacity, Q = 30 m 3 /h; electric power, PN = 4 kW; voltage, 380V/3-/50Hz, and Y connections that can be operated manually or automatically by using the automatic transfer switch. The results obtained recapitulation total load of 4 kW, the magnitude of the nominal current of 9.5 A; kind of safety and capacity are used NFB 16 A, use of this type of cable to the control panel is PLN NYY 6 mm 2 diameter maximum current capacity of 25 A cable and use the control panel to the pump motor cable type NYY 4 mm 2 diameter maximum current capacity of 20 A. The design of the pump motor control system installation is ready to be implemented. (author)

  11. Dose control programme of Hot Cell facility at Isotope Wing

    International Nuclear Information System (INIS)

    Sapkal, Jyotsna A.; Suresh, Manju; Shreenivas, V.; Amruta, C.T.; Yadav, R.K.B.; Gopalkrishanan, R.K.; Patil, B.N.; Sastry, K.V.S.

    2015-01-01

    Hot Cell Facility of Board of Radiation Isotope Technology (BRIT) at Radiological Laboratories (RLG) is involved in fabrication of sealed radioisotopes like Cobalt-60, Cesium-137 and Iridium-192 radioisotopes which are widely used for various medical and industrial applications. In the field of Medicine, above radioactive sources are used for treatment procedures such as Teletherapy and Brachytherapy. 192 Ir radioisotope is widely used for industrial radiography particularly for non-destructive testing of welds in steel in the oil and gas industries. In spite of the increased production of these radioisotopes to meet the requirements from medical and industrial sector, the annual Collective Dose for BRIT facility, during 2011-2013 has shown a downward trend. This paper describes in brief the measures adopted by the facility based on the radiological safety inputs provided by Radiation Hazards Control (RHC) Unit of Isotope Wing, RLG for reducing the collective dose during year 2012 and 2013 by nearly 40% of collective dose consumed for year-2011. Strict implementation of the radiological safety measures during handling of radioactive sources, administrative controls and engineered safety measures resulted in lowering of collective dose during year 2011-2013. (author)

  12. DoD Needs to Improve Screening and Access Controls for General Public Tenants Leasing Housing on Military Installations (REDACTED)

    Science.gov (United States)

    2016-04-01

    helps enhance service members’ quality of life by improving the condition of military-owned housing faster and more economically than traditional...DEPARTMENT OF THE ARMY SUBJECT: DoD Needs to Improve Screening and Access Controls for General Public Tenants Leasing Housing on Military...public tenants who leased DoD privatized housing before granting those tenants unescorted access to military installations. In addition, DoD officials

  13. Smart Microgrid Energy Management Controls for Improved Energy Efficiency and Renewables Integration at DoD Installations

    Science.gov (United States)

    2013-05-01

    reduced greenhouse gas (GHG) emissions; 2. Increased energy efficiency; and 3. Increased energy surety. This demonstration will also directly impact ...megawatt (MW), as well as a gas-fired cogeneration plant in excess of 7 MW. In the future, additional solar PV, fuel cells and advanced energy storage... Energy Management Controls for Improved Energy Efficiency and Renewables Integration at DoD Installations May 2013 Report Documentation Page Form

  14. Installation of a permeable reactive barrier at the mining complex facility in Los Gigantes - Cordoba : Monitoring plan of surface and underground water

    International Nuclear Information System (INIS)

    Grande Cobian, Juan D.; Sanchez Proano, Paula; Cicerone, Daniel S.

    2009-01-01

    The Argentine National Atomic Energy Commission declares under its Environmental policy the commitment to restore those sites where activities concerning Uranium mining were developed. It makes it beyond the scope of the Project of Environmental Restitution of the Uranium Mining (PRAMU from its Spanish abbreviation). The Chemistry of Water and Soil Division at the Environmental Chemistry and Energy Generation Department belonging to the Chemistry Management Office assist the PRAMU on the installation of an hydroxyapatite permeable reactive barrier (PRB) inside the Mining Complex facility placed at Los Gigantes in the Argentine province of Cordoba (in advance named the site). Among the preliminary assessment activities that are being carried out before the installation of the PRB, it has been prepared a monitoring program of surface water and groundwater useful to develop an environmental baseline suitable for the efficiency assessment of the corrective action to be applied. An exploratory campaign was conducted in the site with the aim of establishing a monitoring net of meteorological and hydrological, as well as physical, chemical and biological parameters in matrixes of sediments, water and suspended particulate matter collected on a regular time basis from its surface water and groundwater bodies. The processed results turn into useful environmental information to: a) determine the status of the environmental baseline of the site, b) establish a water quality index (WQI) to manage the natural resource quality according to a rational basis, c) plan experiments related to the design process of a biogenic hydroxyapatite PRB and d) apply chemometric and mechanistic models to forecast the contaminants mobilization through different scenarios and improve the engineering design of the PRB. Once achieved the hydrogeological characterisation of the site and taking into account the originality of the system the following results have been reached: 1) The boundaries of

  15. Software of microcomputer ELEKTRONIKA-60 installed in the control system of the measuring projector PUOS-4

    International Nuclear Information System (INIS)

    Dikij, V.M.; Nekipelova, G.D.; Shakhbazyan, V.V.; Yurpalov, V.D.

    1990-01-01

    The tasks, structure and aspects of realization of servodrivers of the PUOS-4 measuring projector (measuring carriage, tape transport) on the installed ELEKTRONIKA-60 microcomputer operating in the multi-machine system of film information preprocessing, are considered. Realizability of drivers is estimated under rigid operation conditions using the RTM60 real time monitor. The problem of the projector testing is also considered. 11 refs.; 5 figs.; 1 tab

  16. Correlation plot facility in the SLC control system

    International Nuclear Information System (INIS)

    Hendrickson, L.; Phinney, N.; Sanchez-Chopitea, L.

    1991-05-01

    The Correlation Plot facility is a powerful interactive tool for data acquisition and analysis throughout the SLC. A generalized interface allows the user to perform a wide variety of machine physics experiments without the need for specialized software. It has been used extensively during SLC commissioning and operation. The user may step one or two independent parameters such as magnet or feedback setpoints while measuring or calculating up to 160 others. Measured variables include all analog signals available to the control system as well as a variety of derived parameters such as beam size or emittance. Various fitting algorithms and display options are provided for data analysis. A software-callable interface is also provided. Applications based on this facility are used to phase klystrons, measure emittance and dispersion, minimize beam size at the interaction point and maintain beam collisions. 4 refs., 3 figs

  17. Phytochrome-mediated responses: Implications for controlled environment research facilities

    Science.gov (United States)

    Smith, Harry

    1994-01-01

    Light is undoubtedly the most important environmental variable for plant growth and development; plants not only use radiant energy in photosynthesis, they also respond to the quantity, quality, direction and timing of incident radiation through photomorphogenic response that can have huge effects on the rate of growth and the pattern of development. It is surprising, therefore, that the manufacturers and suppliers of controlled environment facilities have been singularly uninventive in the design of the lighting assemblies they provide. The consumer has one choice only - a lighting assembly that provides irradiance levels usually only a fraction of sunlight, and a control system that is limited to regulating the timing of the on-off switch. The reasons for these limitations are partly technological, but in the main they result from ignorance on the part of both the consumer and the manufacturer. A specific and powerful example of this ignorance relates to the importance of the so-called far-red wavelengths (FR = 700-800 nm). Because the human eye can hardly detect wavelengths above 700 nm, and photosynthesis also cuts off at about 700 nm, the majority of plant and crop physiologists are still almost completely unaware that FR radiation can have massive effects on growth rate and development. In consequence, most growth cabinets have light sources based on fluorescent tubes, and provide very little FR apart from that emitted by a token number of small incandescent bulbs. Larger growth facilities often use broader spectrum light sources, but growth facilities that provide the capability to vary the FR incident upon the plants are about as abundant as seals in the Sahara. This article sets the background of the significance of FR radiation in the natural environment and its importance for plant growth and development in the hope that it might inform intelligently those concerned with improving the design of plant growth facilities.

  18. Phytochrome-mediated responses implications for controlled environment research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Smith, H. [Univ. of Leicester (United Kingdom)

    1994-12-31

    Light is undoubtedly the most important environmental variable for plant growth and development; plants not only use radiant energy in photosynthesis, they also respond to the quantity, quality, direction and timing of incident radiation through photomorphogenic responses that can have huge effects on the rate of growth and the pattern of development. It is surprising, therefore, that the manufacturers and suppliers of controlled environment facilities have been singularly uninventive in the design of the lighting assemblies they provide. The consumer has one choice only - a lighting assembly that provides irradiance levels usually only a fraction of sunlight, and a control system that is limited to regulating the timing of the on-off switch. The reasons for these limitations are partly technological, but in the main they result from ignorance on the part of both the consumer and the manufacturer. A specific and powerful example of this ignorance relates to the importance of the so-called far-red wavelengths (FR = 700-800 nm). Because the human eye can hardly detect wavelengths above 700 nm, and photosynthesis also cuts off at ca. 700 mn, the majority of plant and crop physiologists are still almost completely unaware that FR radiation can have massive effects on growth rate and development. In consequence, most growth cabinets have light sources based on fluorescent tubes, and provide very little FR apart from that emitted by a token number of small incandescent bulbs. Larger growth facilities often use broader spectrum light sources, but growth facilities that provide the capability to vary the FR incident upon the plants are about as abundant as seals in the Sahara. This article sets the background of the significance of FR radiation in the natural environment and its importance for plant growth and development in the hope that it might inform intelligently those concerned with improving the design of plant growth facilities.

  19. National Ignition Facility (NIF) Control Network Design and Analysis

    International Nuclear Information System (INIS)

    Bryant, R M; Carey, R W; Claybourn, R V; Pavel, G; Schaefer, W J

    2001-01-01

    The control network for the National Ignition Facility (NIF) is designed to meet the needs for common object request broker architecture (CORBA) inter-process communication, multicast video transport, device triggering, and general TCP/IP communication within the NIF facility. The network will interconnect approximately 650 systems, including the embedded controllers, front-end processors (FEPs), supervisory systems, and centralized servers involved in operation of the NIF. All systems are networked with Ethernet to serve the majority of communication needs, and asynchronous transfer mode (ATM) is used to transport multicast video and synchronization triggers. CORBA software infra-structure provides location-independent communication services over TCP/IP between the application processes in the 15 supervisory and 300 FEP systems. Video images sampled from 500 video cameras at a 10-Hz frame rate will be multicast using direct ATM Application Programming Interface (API) communication from video FEPs to any selected operator console. The Ethernet and ATM control networks are used to broadcast two types of device triggers for last-second functions in a large number of FEPs, thus eliminating the need for a separate infrastructure for these functions. Analysis, design, modeling, and testing of the NIF network has been performed to provide confidence that the network design will meet NIF control requirements

  20. Development of a unified sizing method for gas radiation heating facilities used in large-volume buildings; Developpement d'une methode de dimensionnement unifiee d'installations de chauffage radiant gaz pour les batiments de grand volume

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, M.; Bego, L.; Douls, Y.; Le Dean, P.; Paradowski, V. [Gaz de France, GDF, Dir. de la Recherche, 75 - Paris (France)

    2000-07-01

    Builders now have perfect command of the natural gas heating technique used for large-volume buildings. However, the sizing of heating facilities still leaves grounds for discussion, whatever the energies actually used. Accordingly, between 1997 and 1999, the ATG (technical association of the Gas industry in France), seven French manufacturers of 'large volume' heating equipment, the Chaleur Et Rayonnement (CER) association and Gaz de France decided to collaborate and develop a 'unified sizing method' for heating facilities using radiating emitters. During the first year of the study, the above partners worked on the said method (theoretical thermal study of the radiative phenomena, and then adaptation to the methods currently used by the various manufacturers). In 1998, with the support of the ADEME (the French environment and energy control agency), the partners tested the method on five industrial buildings (studying the thermal behavior and making air renewal measurements with search gases). This work made it possible to either confirm or adapt the theoretical evaluations which had been made originally. In 1999, a software program was produced to make the developed method more user friendly. The program can be used to determine the power to be installed, but also to assess the quality of the chosen configuration of the emitters (unit power, inclination, orientation) for optimum customer comfort. (authors)

  1. Analysis of Operational and Management Cybersecurity Controls for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Jin Seok; Ryou, Jae Cheol [Chungnam National University, Dajeon (Korea, Republic of)

    2014-08-15

    U.S. NRC developed this RG 5.71 by tailoring the baseline security controls described in NIST Special Publication 800-53 'Recommended Security Controls for Federal Information Systems and Organizations' to provide an acceptable method to comply with the 10 CFR 73.54. The purpose of this publication is to provide guidelines for selecting and specifying security controls for information systems. In this paper, we are going to analyze and compare the NRC RG 5.71 and the NIST SP800-53, in particular, for operational security controls and management security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to consider some security controls to strengthen cybersecurity of nuclear facilities.

  2. Analysis of Operational and Management Cybersecurity Controls for Nuclear Facilities

    International Nuclear Information System (INIS)

    Oh, Jin Seok; Ryou, Jae Cheol

    2014-01-01

    U.S. NRC developed this RG 5.71 by tailoring the baseline security controls described in NIST Special Publication 800-53 'Recommended Security Controls for Federal Information Systems and Organizations' to provide an acceptable method to comply with the 10 CFR 73.54. The purpose of this publication is to provide guidelines for selecting and specifying security controls for information systems. In this paper, we are going to analyze and compare the NRC RG 5.71 and the NIST SP800-53, in particular, for operational security controls and management security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to consider some security controls to strengthen cybersecurity of nuclear facilities

  3. Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Chooz - 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  4. Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Flamanville - 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  5. Controlling changes - lessons learned from waste management facilities

    International Nuclear Information System (INIS)

    Johnson, B.M.; Koplow, A.S.; Stoll, F.E.; Waetje, W.D.

    1995-01-01

    This paper discusses lessons learned about change control at the Waste Reduction Operations Complex (WROC) and Waste Experimental Reduction Facility (WERF) of the Idaho National Engineering Laboratory (INEL). WROC and WERF have developed and implemented change control and an as-built drawing process and have identified structures, systems, and components (SSCS) for configuration management. The operations have also formed an Independent Review Committee to minimize costs and resources associated with changing documents. WROC and WERF perform waste management activities at the INEL. WROC activities include storage, treatment, and disposal of hazardous and mixed waste. WERF provides volume reduction of solid low-level waste through compaction, incineration, and sizing operations. WROC and WERF's efforts aim to improve change control processes that have worked inefficiently in the past

  6. Documents pertaining to safety control of nuclear facilities

    International Nuclear Information System (INIS)

    1998-01-01

    The Finnish Radiation and Nuclear Safety Authority (STUK) controls the safety of nuclear facilities in Finland. This control encompasses on one hand the evaluation of plant safety on the basis of plans and analyses pertaining to the plant and on the other hand the inspection of plant structures, systems and components as well as of operational activity. STUK also monitors plants operational experience feedback and technical developments in the field, as well as the development of safety research and takes the necessary measures on their basis. Guide YVL 1.1 describes how STUK controls the design, construction and operation of nuclear power plants. The documents to be submitted to STUK are described in the nuclear energy legislation and YVL guides. This guide presents the mode of delivery, quality, contents and number of documents to be submitted to STUK

  7. Infection prevention and control in deployed military medical treatment facilities.

    Science.gov (United States)

    Hospenthal, Duane R; Green, Andrew D; Crouch, Helen K; English, Judith F; Pool, Jane; Yun, Heather C; Murray, Clinton K

    2011-08-01

    Infections have complicated the care of combat casualties throughout history and were at one time considered part of the natural history of combat trauma. Personnel who survived to reach medical care were expected to develop and possibly succumb to infections during their care in military hospitals. Initial care of war wounds continues to focus on rapid surgical care with debridement and irrigation, aimed at preventing local infection and sepsis with bacteria from the environment (e.g., clostridial gangrene) or the casualty's own flora. Over the past 150 years, with the revelation that pathogens can be spread from patient to patient and from healthcare providers to patients (including via unwashed hands of healthcare workers, the hospital environment and fomites), a focus on infection prevention and control aimed at decreasing transmission of pathogens and prevention of these infections has developed. Infections associated with combat-related injuries in the recent operations in Iraq and Afghanistan have predominantly been secondary to multidrug-resistant pathogens, likely acquired within the military healthcare system. These healthcare-associated infections seem to originate throughout the system, from deployed medical treatment facilities through the chain of care outside of the combat zone. Emphasis on infection prevention and control, including hand hygiene, isolation, cohorting, and antibiotic control measures, in deployed medical treatment facilities is essential to reducing these healthcare-associated infections. This review was produced to support the Guidelines for the Prevention of Infections Associated With Combat-Related Injuries: 2011 Update contained in this supplement of Journal of Trauma.

  8. Alteration of installation of reactors (alteration of No.1 and No.2 reactor facilities) in Oi Power Station, Kansai Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1984-01-01

    The Nuclear Safety Commission reported to the Minister of International Trade and Industry on October 27, 1983, that the technical capability was recognized to be adequate, and the safety after the alteration of the installation of reactors was judged to be ensured. At the time of deliberation, the guidelines for examining the safety design and safety evaluation of LWR facilities for power generation were used. Regarding the change of the degree of enrichment of replacement fuel from 3.2 to 3.4 wt.%, the limiting conditions are satisfied in the replacement core, and the nuclear design is appropriate. Eight test fuel assemblies using UO 2 pellets containing gadolinia are charged in the core of No.2 reactor, and the irradiation of two cycles is carried out. As the result of the safety examination regarding this test, the propriety of the nuclear design and mechanical design of the test fuel assemblies was confirmed. This alteration does not exert influence on the result of safety analysis made so far. This report was decided by the Committee on Examination of Reactor Safety based on the conclusion of No.26 subcommittee. (Kako, I.)

  9. Alteration of installation of nuclear reactors (alteration of No. 1 and No. 2 reactor facilities) in Shimane Nuclear Power Station, Chugoku Electric Power Co. , Inc. (report)

    Energy Technology Data Exchange (ETDEWEB)

    1987-07-01

    The Nuclear Safety Commission reported to the Minister of International Trade and Industry after prudent deliberation on this alteration problem which had been inquired on August 28, 1986. It was recognized that the technical capability of the applicant is appropriate, as the result of deliberation. It was judged that the safety after this alteration of the installation of the reactor facilities can be ensured. As the result of examining new type 8 x 8 zirconium liner fuel, there was no problem in its mechanical design, the analysis of dynamical characteristics, and the analysis of abnormal transient change and accident in operation. As to the change of the average degree of enrichment of replacement fuel, the thermonuclear design of the reactor core was adequate. In the incineration of spent resin and filter sludge, the effect of radioactive substances to the environment was negligible. The safety after abolishing the auxiliary protection function against exhaust radioactivity is ensured with a rare gas holdup equipment. The soundness of fuel and the soundness of reactor coolant pressure boundary are maintained in abnormal transient change and accident. (Kako, I.).

  10. Alteration of installation of nuclear reactors (alteration of No.1 and No.2 reactor facilities) in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    1987-01-01

    The Nuclear Safety Commission reported to the Minister of International Trade and Industry after prudent deliberation on this alteration problem which had been inquired on August 28, 1986. It was recognized that the technical capability of the applicant is appropriate, as the result of deliberation. It was judged that the safety after this alteration of the installation of the reactor facilities can be ensured. As the result of examining new type 8 x 8 zirconium liner fuel, there was no problem in its mechanical design, the analysis of dynamical characteristics, and the analysis of abnormal transient change and accident in operation. As to the change of the average degree of enrichment of replacement fuel, the thermonuclear design of the reactor core was adequate. In the incineration of spent resin and filter sludge, the effect of radioactive substances to the environment was negligible. The safety after abolishing the auxiliary protection function against exhaust radioactivity is ensured with a rare gas holdup equipment. The soundness of fuel and the soundness of reactor coolant pressure boundary are maintained in abnormal transient change and accident. (Kako, I.)

  11. Canadian Food Irradiation Facilities; Installations Canadiennes d'Irradiation des Aliments; Kanadskie ustanovki dlya oblucheniya pishchevykh produktov; Instalaciones de Irradiacion de Alimentos en el Canada

    Energy Technology Data Exchange (ETDEWEB)

    Warland, H. M.F.; MacQueen, K. F. [Atomic Energy of Canada Ltd., Commercial Products, Ottawa (Canada)

    1966-11-15

    Atomic Energy of Canada Limited (AECL) began work on the irradiation of potatoes in 1956, using spent fuel rods as the radiation source. In 1958 the first Gammacell 220, a self-contained irradiator, was designed and manufactured by AECL, and cobalt-60 was then used exclusively in the food irradiation programme. In 1960 the first food and drug clearance was obtained for potatoes. The next stage was to demonstrate to the potato industry that cobalt-60 was a safe, simple and reliable tool, and that irradiation would inhibit sprouting under field conditions. A mobile irradiator was designed and produced by AECL in 1961 to carry out this pilot-plant programme. The irradiator was mounted on a fully-equipped road trailer and spent the 1961/1962 season irradiating one million pounds of potatoes at various points in Eastern Canada. In 1965 the first commercial food irradiator was designed and built by AECL for Newfield Products, Ltd. Whilst the potato programme was under way, AECL initiated co-operative programmes with Canadian food research laboratories, using additional Gammacells. In 1960, AECL constructed an irradiation facility in a shielded room at its own plant in Ottawa for the irradiation of larger objects, such as sides of pork and stems of bananas. During 1963 the mobile irradiator, already a most useful tool, was made more versatile when its source strength was increased and it was equipped with a product cooling system and van air conditioning. Following these modifications, the unit was employed in California for the irradiation of a wide spectrum of fruits at the United States Department of Agriculture Station in Fresno. The Gammacell, mobile irradiator, shielded-room facility, the commercial food irradiator and some of the main food programmes are described in detail. There is an increasing amount of interest in irradiation by the food industry, and prospects are encouraging for future installations. (author) [French] L'Atomic Energy of Canada Limited

  12. Design, construction and installation of the electromechanical components of the current control of filament of the Pelletron Electron Accelerator

    International Nuclear Information System (INIS)

    Aguilar J, R.A.; Valdovinos A, M.; Lopez V, H.

    1985-01-01

    For the operation of the Pelletron electron accelerator is required to have control of the filament current. For it was designed, built and installed an electromechanical system located in the Acceleration Unit inside the Accelerator tank and operated from the Control console. All the components located inside the tank operated under the following conditions: Pressure: until 7.03 Kg/cm 2 ; High voltage: 10 6 V (only the insulating arrow); Atmosphere: mixture of N 2 and CO 2 or SF 6 . (Author)

  13. Optimizing operation costs of the heating system of a household using model predictive control considering a local PV installation

    DEFF Research Database (Denmark)

    Koch-Ciobotaru, Cosmin; Isleifsson, Fridrik Rafn; Gehrke, Oliver

    2012-01-01

    This paper presents a model predictive controller developed in order to minimize the cost of grid energy consumption and maximize the amount of energy consumed from a local photovoltaic (PV) installation. The usage of as much locally produced renewable energy sources (RES) as possible, diminishes...... the effects of their large penetration in the distribution grid and reduces overloading the grid capacity, which is an increasing problem for the power system. The controller uses 24 hour prediction data for the ambient temperature, the solar irradiance, and for the PV output power. Simulation results...

  14. Design, fabrication, installation and shielding integrity testing of source storage container for automatic source movement system used in TLD calibration facility

    International Nuclear Information System (INIS)

    Subramanian, V.; Baskar, S.; Annalakshmi, O.; Jose, M.T.; Jayshree, C.P.; Choudry, Shreelatha

    2012-01-01

    A state-of-art TLD laboratory has been commissioned in January 2000 at Radiological Safety Division of Indira Gandhi Centre for Atomic Research (IGCAR). The laboratory provides personnel monitoring service to 2000 occupational workers from Indira Gandhi Centre for Atomic Research and Bhabha Atomic Research Centre facilities. The laboratory has been accredited by the Radiation Safety Systems Division (RSSD), Bhabha Atomic Research Centre (BARC) since year 2002. The laboratory has exclusive facility for the calibration of the TLD cards. As apart of accreditation procedure and taking into account of geometry effect, the dose rate at the card position is determined by the accreditation authorities by using graphite chamber (secondary or national standard instrument) and often re estimated by a condenser R meter (M/s Victoreen, Germany) by our laboratory. As per the regulatory requirement, the exposure protocols should be automated. Towards this an automatic source movement system has been augmented in the calibration facility. By using the system, the source will be brought to the irradiation position by pneumatically and exposures will be terminated by counter, timer and triggering system. To accomplish this task a lead container has been designed, fabricated and mounted at the beneath of the calibration table for the storage of source. As per the automation process, a lead container for the source storage has been designed and installed beneath to the Calibration Table. The container was designed to hold a 3Ci 137 Cs source, but present activity of the source is 1.2Ci. Hence, the shielding integrity was tested with higher active source (1.7Ci 60 Co). The dose rate measured outside on the circumference of the container at the middle of the source is found to be the same as calculated using QAD CGGP calculations. The top plug is so designed to avoid inadvertent upward movement of the source. Though, the shielding was not adequate on top of the top plug, however it does

  15. An acoustically controlled tetherless underwater vehicle for installation and maintenance of neutrino detectors in the deep ocean

    International Nuclear Information System (INIS)

    Ballou, Philip J.

    1997-01-01

    The task of installing and servicing high energy neutrino detectors in the deep ocean from a surface support vessel is problematic using conventional tethered systems. An array of multiple detector strings rising 500 m from the ocean floor, and forming a grid with 50 m spacing between the strings, presents a substantial entanglement hazard for equipment cables deployed from the surface. Such tasks may be accomplished with fewer risks using a tetherless underwater remotely operated vehicle that has a local acoustic telemetry link to send control commands and sensor data between the vehicle and a stationary hydrophone suspended above or just outside the perimeter of the work site. The Phase I effort involves the development of an underwater acoustic telemetry link for vehicle control and sensor feedback, the evaluation of video compression methods for real-time acoustic transmission of video through the water, and the defining of local control routines on board the vehicle to allow it to perform certain basic maneuvering tasks autonomously, or to initiate a self-rescue if the acoustic control link should be lost. In Phase II, a prototype tetherless vehicle system will be designed and constructed to demonstrate the ability to install cable interconnections within a detector array at 4 km depth. The same control technology could be used with a larger more powerful vehicle to maneuver the detector strings into desired positions as they are being lowered to the ocean floor

  16. Requirements for Vertically Installed Runoff Control Boards for the “Paddy Field Dam” and Appropriate Orifice Shapes

    Science.gov (United States)

    Natsuki, Yoshikawa; Hideyuki, Koide; Shin-Ichi, Misawa

    While the “Paddy Field Dam” project has been recognized as an effective flood control measure, there are some cases in which the runoff control boards are vertically installed on the opening of the drainage boxes without careful consideration of the orifice shape and size. The important criteria for the runoff control boards to be satisfied are: 1. to maintain a sufficient peak runoff control function, 2. to avoid excessive ponding causing overflow, 3. to minimize the influence to the ordinary water management, and 4. to reserve sufficient orifice area to avoid blockage of the orifice with floating litters. The purpose of this study is to examine proper shapes and sizes of the orifice to satisfy the criteria for the vertically installed runoff control boards through experiments and simulations. Given the condition that the orifice has sufficient area to avoid overflow with 10 and 20 year return period rainfall event (criteria 2), the simulation results show that the orifice with horizontally wider shapes has advantages over the square or circular shapes in terms of the criteria 1 and 3. The disadvantage of the horizontally wider shapes is the blockage of the orifice with floating litters (criteria 4). In conclusion, we proposed to secure sufficient vertical distance to avoid this problem by setting a lower limit on the vertical distance and then determine the widest horizontal distance to optimize all the criteria. In addition, we have constructed the “Orifice Design Assist Tool” on the basis of the examinations in this study.

  17. Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

    Directory of Open Access Journals (Sweden)

    Nick R. Soelberg

    2013-01-01

    Full Text Available The removal of volatile radionuclides generated during used nuclear fuel reprocessing in the US is almost certain to be necessary for the licensing of a reprocessing facility in the US. Various control technologies have been developed, tested, or used over the past 50 years for control of volatile radionuclide emissions from used fuel reprocessing plants. The US DOE has sponsored, since 2009, an Off-gas Sigma Team to perform research and development focused on the most pressing volatile radionuclide control and immobilization problems. In this paper, we focus on the control requirements and methodologies for 85Kr and 129I. Numerous candidate technologies have been studied and developed at laboratory and pilot-plant scales in an effort to meet the need for high iodine control efficiency and to advance alternatives to cryogenic separations for krypton control. Several of these show promising results. Iodine decontamination factors as high as 105, iodine loading capacities, and other adsorption parameters including adsorption rates have been demonstrated under some conditions for both silver zeolite (AgZ and Ag-functionalized aerogel. Sorbents, including an engineered form of AgZ and selected metal organic framework materials (MOFs, have been successfully demonstrated to capture Kr and Xe without the need for separations at cryogenic temperatures.

  18. Mine subsidence control projects associated with solid waste disposal facilities

    International Nuclear Information System (INIS)

    Wood, R.M.

    1994-01-01

    Pennsylvania environmental regulations require applicant's for solid waste disposal permits to provide information regarding the extent of deep mining under the proposed site, evaluations of the maximum subsidence potential, and designs of measures to mitigate potential subsidence impact on the facility. This paper presents three case histories of deep mine subsidence control projects at solid waste disposal facilities. Each case history presents site specific mine grouting project data summaries which include evaluations of the subsurface conditions from drilling, mine void volume calculations, grout mix designs, grouting procedures and techniques, as well as grout coverage and extent of mine void filling evaluations. The case studies described utilized basic gravity grouting techniques to fill the mine voids and fractured strata over the collapsed portions of the deep mines. Grout mixtures were designed to achieve compressive strengths suitable for preventing future mine subsidence while maintaining high flow characteristics to penetrate fractured strata. Verification drilling and coring was performed in the grouted areas to determine the extent of grout coverage and obtain samples of the in-place grout for compression testing. The case histories presented in this report demonstrate an efficient and cost effective technique for mine subsidence control projects

  19. Control system specification for a cyclotron and neutron therapy facility

    International Nuclear Information System (INIS)

    Jacky, J.; Risler, R.; Kalet, I.; Wootton, P.; Barke, A.; Brossard, S.; Jackson, R.

    1991-01-01

    It is usually considered an essential element of good practice in engineering to produce a specification for a system before building it. However, it has been found to be quite difficult to produce useful specifications of large software systems. The authors have nearly completed a comprehensive specification for the computer control system of a cyclotron and treatment facility that provides particle beams for cancer treatments with fast neutrons, production of medical isotopes, and physics experiments. They describe the control system as thoroughly as is practical using standard technical English, supplemented by tables, diagrams, and some algebraic equations. This specification comprises over 300 single-spaced pages. A more precise and compact specification might be achieved by making greater use of formal mathematical notations instead of English. They have begun work on a formal specification of the system, using the Z and Petri net notations

  20. Study: control of atomic energy power plant; Etude de la regulation d'une installation atomique productrice d'energie

    Energy Technology Data Exchange (ETDEWEB)

    Dautray, R; Leny, J C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    We are studying the control of a very flexible atomic power plant, able to supply an independent network. Two systems have been examined: in the first the moderator pre-heats the light water, in the second, this preheating is dispensed with, subsequent to a study of the dynamics of the plant. Very complete linear approximation study is being effected on the model of the second system, all effects being taken into account. The reactor is stable at all power levels, though slight reactivity or load variations cause undamped power oscillations around the equilibrium level. (author)Fren. [French] Nous etudions la regulation d'une installation atomique d'une grande souplesse, pouvant eventuellement fournir de l'energie a un reseau isole. Deux versions de l'installation sont etudiees: dans la premiere le moderateur sert a rechauffer l'eau industrielle, mais l'etude dynamique conduit a supprimer ce rechauffage, ce qui donne la deuxieme version. On effectue sur celle-ci une etude en approximation lineaire tres complete ou l'on tient compte de differents effets. L'installation se montre stable a tous les niveaux de puissance. Toutefois, de petites perturbations de reactivite ou de charge entrainent des oscillations de puissance mal amorties autour de la position d'equilibre. (auteur)

  1. IE Information Notice No. 85-75: Improperly installed instrumentation, inadequate quality control and inadequate postmodification testing

    International Nuclear Information System (INIS)

    Jordan, E.L.

    1992-01-01

    On June 10, 1985, the licensee informed the NRC Resident Inspector that for approximately 5 days LaSalle Unit 2 had been without the capability of automatic actuation of emergency core cooling (ECCS) and that for approximately 3 days during this period the plant had been without secondary containment integrity. The major cause of this condition was improper installation (the variable and reference legs were reversed) of the two reactor vessel level actuation switches which control Division 1 automatic depressurization system (ADS), low pressure core spray (LPCS), and reactor core isolation cooling (RCIC). On July 20, 1985, the Trojan Nuclear Power Plant tripped from 100% power because of a turbine trip that was caused by the loss of the unit auxiliary transformer. All systems functioned normally except that low suction pressure caused one auxiliary feedwater pump to trip and then the other auxiliary feedwater pump to trip after restart of the first auxiliary feedwater pump. The cause of the trips of the auxiliary feedwater pumps can be traced back to improper postmodification adjustment and inadequate postmodification testing following retrofit of environmentally qualified controllers for the auxiliary feedwater system. The auxiliary feedwater pump trips on low suction pressure were caused by excessive combined flow from the two auxiliary feedwater pumps that draw from a single header from the condensate storage tank. The flow control valves were open farther than required after new environmentally qualified controllers had been installed during a recent refueling outage

  2. Analog Fixed Maximum Power Point Control for a PWM Step-downConverter for Water Pumping Installations

    DEFF Research Database (Denmark)

    Beltran, H.; Perez, E.; Chen, Zhe

    2009-01-01

    This paper describes a Fixed Maximum Power Point analog control used in a step-down Pulse Width Modulated power converter. The DC/DC converter drives a DC motor used in small water pumping installations, without any electric storage device. The power supply is provided by PV panels working around....... The proposed Optimal Power Point fix voltage control system is analyzed in comparison to other complex controls....... their maximum power point, with a fixed operating voltage value. The control circuit implementation is not only simple and cheap, but also robust and reliable. System protections and adjustments are also proposed. Simulations and hardware are reported in the paper for a 150W water pumping application system...

  3. HELOKA facility: thermo-hydrodynamic model and control

    International Nuclear Information System (INIS)

    Ghidersa, B.E.; Ihli, T.; Marchese, V.; Ionescu-Bujor, M.

    2007-01-01

    This paper presents the thermo-hydrodynamic model used to simulate the behaviour of the HELOKA (Helium Loop Karlsruhe) facility and describes the mechanism used to control various loop parameters. This test facility, which is under construction at the Forschungszentrum Karlsruhe (FZK), is designed for testing of various components for nuclear fusion such as the Helium-Cooled Pebble Bed blanket (HCPB) and the heliumcooled- divertor for the DEMO power reactor. Besides the individual testing of the blanket and divertor modules, the understanding of the behaviour of their cooling systems in conditions relevant for ITER operation is mandatory. An important aspect in the operation of these cooling loops is the accurate control, via feedback, of the flow parameters at the inlet of the test module. Understanding heat transfer and fluid flow phenomena during normal and transient operation of HELOKA is essential to ensure the adequacy of safety features. Systems analysis codes, such as RELAP5-3D, are suited to this task. However, the application of these models to HELOKA design must be later validated by experimental measurements, while the basic physical models have been proven for light water reactors. The control of the test section inlet parameters is one of the most important issues. In particular, the start-up phase, when the test section temperature is increased from ambient temperature up to 300 C, requires special attention. As a first step, the HELOKA open loop thermal transient was computed using the RELAP model. The data obtained have been used for the identification of the power-temperature transfer function needed to compute the parameters of the feedback controller (PID) using MATLAB and SIMULINK. An accurate control of the temperature during the start-up and flat top phases is achieved solely by controlling the heater power. The adopted solution reduces the harmonic distortions when operating at reduced power while keeping the investment cost low. This

  4. SNRIU nuclear installation modifications

    International Nuclear Information System (INIS)

    Goroshanskyi, Andrii

    2013-01-01

    Design stages of Nuclear Instalations (NI): NI design is performed in three stages: • Feasibility study: - Feasibility study is developed on the basis of the customer task for production facilities and linear facilities engineering and transport infrastructure that require detailed study of relevant decisions and identify options for and feasibility of construction. • Design: - The design is developed on the basis of design task, initial data and approved the previous stage under three-stage design. • Detailed documentation

  5. Wireless Occupancy Sensors for Lighting Controls: An Applications Guide for Federal Facility Managers

    Energy Technology Data Exchange (ETDEWEB)

    None

    2016-03-15

    This guide provides federal facility managers with an overview of the energy savings potential of wireless lighting occupancy sensors for various room types, cost considerations, key steps to successful installation of wireless sensors, pros and cons of various technology options, light source considerations, and codes and standards.

  6. Quality control through dosimetry at a contract radiation processing facility

    International Nuclear Information System (INIS)

    Du Plessis, T.A.; Roediger, A.H.A.

    1985-01-01

    Reliable dosimetry procedures constitute a very important part of process control and quality assurance at a contract gamma radiation processing facility that caters for a large variety of different radiation applications. The choice, calibration and routine intercalibration of the dosimetry systems employed form the basis of a sound dosimetry policy in radiation processing. With the dosimetric procedures established, detailed dosimetric mapping of the irradiator upon commissioning (and whenever source modifications take place) is carried out to determine the radiation processing characteristics and peformance of the plant. Having established the irradiator parameters, routine dosimetry procedures, being part of the overall quality control measures, are employed. In addition to routine dosimetry, independent monitoring of routine dosimetry is performed on a bi-monthly basis and the results indicate a variation of better than 3%. On an annaul basis the dosimetry systems are intercalibrated through at least one primary standard dosimetry laboratory and to date a variation of better than 5% has been experienced. The company also participates in the Pilot Dose Assurance Service of the International Atomic Energy Agency, using the alanine/ESR dosimetry system. Routine calibration of the instrumentation employed is carried out on a regular basis. Detailed permanent records are compiled on all dosimetric and instrumentation calibrations, and the routine dosimetry employed at the plant. Certificates indicating the measured absorbed radiation doses are issued on request and in many cases are used for the dosimetric release of sterilized medical and pharmaceutical products. These procedures, used by Iso-Ster at its industrial gamma radiation facility, as well as the experience built up over a number of years using radiation dosimetry for process control and quality assurance are discussed. (author)

  7. Control of radioactivity at the Luxembourg steel-making facilities

    International Nuclear Information System (INIS)

    Werner, C.

    1999-01-01

    The Luxembourg steel industry has a yearly capacity of close to 3 million tonnes of raw steel produced from scrap at three electric arc furnace steel-making plants. It has introduced in 1994 a comprehensive system of measuring devices to prevent radioactive material from being introduced into its meltshops. Detection equipment has been installed at the road and railroad accesses to the three plants. Further to the controls of incoming scrap, radioactivity is monitored on both the steel and the slag samples of each heat produced at the plants. This measure is taken in order to detect any incident involving the melting of a radioactive source that might have escaped the controls of incoming material as soon as possible. The triple purpose of these controls is: (i) to protect the personnel of the steel making plants from radiation hazards; (ii) to maintain the integrity of the equipment; and (iii) to assure integrity of the products. The presentation describes the possible origins of radioactive contamination in steel scrap as well as the behaviour in the steel making process of the different radionuclides that can be expected to be introduced into the steel making vessels through steel scrap. Together with the government agency for radiation protection, procedures have been developed for the management of any event of detection of radioactivity in the plants and to assure optimum availability of the measuring equipment. These procedures are described and commented in the presentation. The presentation includes also a report on the experience from 4 years of monitoring, during which more than 10 million tonnes of scrap have passed the gates of the steel-making plants of ProfilARBED and ARES. (author)

  8. Installations for radiation therapy with remote controlled afterloading technique. Ferngesteuerte Applikationsanlagen zur Therapie mit umschlossenen radioaktiven Stoffen

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    Installations for radiation therapy with remote controlled afterloading technique; radiation protection rules for fabrication and construction; amendment 1 to draft standard (DIN) 6853. Compared to the draft standard of Semptember 1980, the following modifications are planned as amendment 1: a. Paragraph no. 1: In the title, the word ''scope'' is changed into ''field of application''. The words ''by moving the radiation source electromecanically'' are deleted. b. Paragraph no. 2'' Standards also applicable'' and the list of ''Additional standards'' are summarized under the heading ''Standards and supporting documents'' (without any paragraph number). c. Paragraph no. 3 ''Terms'' is completed by additional terms and their definitions.

  9. Control of semivolatile radionuclides in gaseous effluents at nuclear facilities

    International Nuclear Information System (INIS)

    1982-01-01

    An up-to-date review is presented of the subject, combining the results of laboratory studies on control of the most important semivolatile radionuclides in gaseous effluents at nuclear facilities and the results of operating experience in that area. Ruthenium is the most significant semivolatile contaminant in gaseous effluents at nuclear facilities. Volatilization of ruthenium can be reduced by various means, in particular by adding reductants. Volatilized ruthenium can be retained by adsorbents such as silica gel and ferric-oxide-based materials. Decontamination factors in the order of 10 3 have been obtained with these adsorbents under optimum conditions. Volatilized ruthenium can also be removed by other equipment such as condensers and scrubbers. Experience with high-level liquid waste solidification plants has shown that, in general, ruthenium volatilization is in the order of 10% or more unless special treatment is undertaken. There is little experience with ruthenium adsorbers in plants. Silica gel seems to have performed best, with ruthenium decontamination factors of about 10 2 to 10 3 . However, feed-to-stack ruthenium decontamination factors of 10 9 or more have been obtained even without ruthenium adsorbers. Other semivolatiles are relatively insignificant under normal conditions because of a low level of volatilization potential or mass or activity in the inventory. Moreover, owing to particulate formation, they can be easily removed without specific equipment

  10. Process control and dosimetry in a multipurpose irradiation facility

    International Nuclear Information System (INIS)

    Cabalfin, E.G.; Lanuza, L.G.; Solomon, H.M.

    1998-01-01

    Complete text of publication follows. To introduce and demonstrate radiation processing to the local industries, the Philippine Nuclear Research Institute (PNRI) with the technical assistance of the International Atomic Energy Agency (IAEA) has set up a pilot scale multipurpose gamma irradiation facility. Though on a limited scale, this has led to the commercial radiation sterilization and decontamination of various products, such as empty aluminum tubes, empty gelatin capsules, spices and fresh onions. Process control in this facility involves dose measurement to ensure that the products receive the required dose to get the desired beneficial effect. Prior to routine processing, dose distribution studies to determine the locations of minimum and maximum absorbed dose are undertaken for each product and product-source geometry. The product loading pattern, which meets the required dose uniformity ratio and which gives the optimum amount of product per loading is then chosen. During routine irradiation, dosimeters are placed at the minimum and maximum absorbed dose positions of a process load. If locations of minimum or maximum dose are not readily accessible, dosimeters are placed at reference positions. The relationship of the absorbed dose at these reference positions with the absorbed dose at the minimum or maximum position is established beforehand. Fricke and ethanol chlorobenzene (ECB) dosimeters are used to measure absorbed dose. PNRI participates in the International Dose Assurance Service (IDAS) of IAEA. Results show that absorbed dose as measured by alanine agreed with ECB within 5%, while that from Fricke agreed to within 2%

  11. Process control and dosimetry in a multipurpose irradiation facility

    Energy Technology Data Exchange (ETDEWEB)

    Cabalfin, E G; Lanuza, L G; Solomon, H M [Philippine Nuclear Research Institute, Diliman, Quezon City (Philippines)

    1999-12-31

    Complete text of publication follows. To introduce and demonstrate radiation processing to the local industries, the Philippine Nuclear Research Institute (PNRI) with the technical assistance of the International Atomic Energy Agency (IAEA) has set up a pilot scale multipurpose gamma irradiation facility. Though on a limited scale, this has led to the commercial radiation sterilization and decontamination of various products, such as empty aluminum tubes, empty gelatin capsules, spices and fresh onions. Process control in this facility involves dose measurement to ensure that the products receive the required dose to get the desired beneficial effect. Prior to routine processing, dose distribution studies to determine the locations of minimum and maximum absorbed dose are undertaken for each product and product-source geometry. The product loading pattern, which meets the required dose uniformity ratio and which gives the optimum amount of product per loading is then chosen. During routine irradiation, dosimeters are placed at the minimum and maximum absorbed dose positions of a process load. If locations of minimum or maximum dose are not readily accessible, dosimeters are placed at reference positions. The relationship of the absorbed dose at these reference positions with the absorbed dose at the minimum or maximum position is established beforehand. Fricke and ethanol chlorobenzene (ECB) dosimeters are used to measure absorbed dose. PNRI participates in the International Dose Assurance Service (IDAS) of IAEA. Results show that absorbed dose as measured by alanine agreed with ECB within 5%, while that from Fricke agreed to within 2%.

  12. Overview of the West Valley Vitrification Facility transfer cart control system

    International Nuclear Information System (INIS)

    Bradley, E.C.; Rupple, F.R.

    1993-01-01

    Oak Ridge National Laboratory (ORNL) has designed the control system for the West Valley Demonstration Project Vitrification Facility transfer cart. The transfer cart will transfer canisters of vitrified high-level waste remotely within the Vitrification Facility. The control system will operate the cart under battery power by wireless control. The equipment includes cart mounted control electronics, battery charger, control pendants, engineer's console, and facility antennas

  13. Radioactive waste control at the reprocessing facility in fiscal 1980

    International Nuclear Information System (INIS)

    1982-01-01

    At the fuel reprocessing facility of the Power Reactor and Nuclear Fuel Development Corporation (PNC), the release of radioactive gaseous and liquid wastes are controlled so as not to exceed the specific levels. Concentrated low and high level liquid wastes, sludge, etc. are contained in storage tanks. Low and high level solid wastes are stored in appropriate containers. In fiscal 1980 (April to March), the release of gaseous and liquid wastes was below the specific levels (as in the previous years). Based on the report made by PNC in accordance with the law concerning the regulation of reactors, etc., the following data are presented in tables: the released quantity of radioactive gaseous and liquid wastes in fiscal 1980, the cumulative stored quantity of radioactive liquid wastes up to fiscal 1980; the cumulative stored quantity of radioactive solid wastes up to fiscal 1980 and the quantity of the same stored in fiscal 1980. (J.P.N.)

  14. Correlation Plot facility in the SLC control system

    International Nuclear Information System (INIS)

    Hendrickson, L.; Phinney, N.; Sanchez-Chopitea, L.; Clark, S.

    1991-11-01

    The Correlation Plot facility is a powerful interactive tool for data acquisition and analysis throughout the SLC. This generalized interface allows the user to perform a range of operations or machine physics experiments without the need for any specialized analysis software. The user may step one or more independent parameters, such as magnet or feedback setpoints, while measuring or calculating up to 160 other parameters. Measured variables include all analog signals available to the control system, as well as calculated parameters such as beam size, luminosity, or emittance. Various fitting algorithms and display options are provided. A software-callable interface has been provided so that a host of applications can call this package for analysis and display. Such applications regularly phase klystrons, measure emittance and dispersion, minimize beam size, and maintain beam collisions at the interaction point. 4 refs., 5 figs

  15. Correlation Plot facility in the SLC control system

    International Nuclear Information System (INIS)

    Hendrickson, L.; Phinney, N.; Sachez-Chopitea, L.; Clark, S.

    1992-01-01

    The Correlation Plot facility is a powerful interactive tool for data acquisition and analysis throughout the SLC. This generalized interface allows the user to perform a range of operations or machine physics experiments without the need for any specialized analysis software. The user may step one or more independent parameters, such as magnet or feedback set points, while measuring or calculating up to 160 other parameters. Measured variables include all analog signals available to the control system, as well as calculated parameters such as beam size, luminosity, or emittance. Various fitting algorithms and display options are provided. A software-callable interface has been provided so that a host of applications can call this package for analysis and display. Such applications regularly phase klystrons, measure emittance and dispersion, minimize beam size, and maintain beam collisions at the interaction point. (author)

  16. Radiological Control Technician: Phase 4, Facility practical training attachment

    International Nuclear Information System (INIS)

    1992-10-01

    At DOE sites with more than one facility, and where RCT tasks at each facility may differ, site and facility tasks should be separated. The tasks that are common to all the facilities on the site should be included in Phase II training with the core tasks. Tasks unique to a facility should be added to the training program qualification standard, as an attachment, as Phase IV training. Not all the DOE sites will include Phase IV training in their programs. Phase IV training allows each site to qualify technicians to a select facility. Since the core training for the technicians is standardized, the transfer of technicians between facilities requires that only facility tasks be taught, provided the core qualification is current

  17. Database design for Physical Access Control System for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sathishkumar, T., E-mail: satishkumart@igcar.gov.in; Rao, G. Prabhakara, E-mail: prg@igcar.gov.in; Arumugam, P., E-mail: aarmu@igcar.gov.in

    2016-08-15

    Highlights: • Database design needs to be optimized and highly efficient for real time operation. • It requires a many-to-many mapping between Employee table and Doors table. • This mapping typically contain thousands of records and redundant data. • Proposed novel database design reduces the redundancy and provides abstraction. • This design is incorporated with the access control system developed in-house. - Abstract: A (Radio Frequency IDentification) RFID cum Biometric based two level Access Control System (ACS) was designed and developed for providing access to vital areas of nuclear facilities. The system has got both hardware [Access controller] and software components [server application, the database and the web client software]. The database design proposed, enables grouping of the employees based on the hierarchy of the organization and the grouping of the doors based on Access Zones (AZ). This design also illustrates the mapping between the Employee Groups (EG) and AZ. By following this approach in database design, a higher level view can be presented to the system administrator abstracting the inner details of the individual entities and doors. This paper describes the novel approach carried out in designing the database of the ACS.

  18. Combustible gas concentration control facility and operation method therefor

    International Nuclear Information System (INIS)

    Yoshikawa, Kazuhiro; Ando, Koji; Kinoshita, Shoichiro; Yamanari, Shozo; Moriya, Kimiaki; Karasawa, Hidetoshi

    1998-01-01

    The present invention provides a hydrogen gas-control facility by using a fuel battery-type combustible gas concentration reducing device as a countermeasure for controlling a hydrogen gas in a reactor container. Namely, a hydrogen electrode adsorb hydrogen by using an ion exchange membrane comprising hydrogen ions as a charge carrier. An air electrode adsorb oxygen in the air. A fuel battery converts recombining energy of hydrogen and oxygen to electric energy. Hydrogen in this case is supplied from an atmosphere in the container. Oxygen in this case is supplied from the air outside of the container. If hydrogen gas should be generated in the reactor, power generation of is performed by the fuel battery by using hydrogen gas, as a fuel, on the side of the hydrogen electrode of the fuel battery and using oxygen, as a fuel, in the air outside of the container on the side of the air electrode. Then, the hydrogen gas is consumed thereby controlling the hydrogen gas concentration in the container. Electric current generated in the fuel battery is used as an emergency power source for the countermeasure for a severe accident. (I.S.)

  19. Material control and accounting requirements for uranium enrichment facilities

    International Nuclear Information System (INIS)

    Ting, P.

    1991-01-01

    This paper reports that the U.S. Nuclear Regulatory Commission has defined material control and accounting (MC and A) requirement for low-enriched uranium enrichment plants licensed under 10 CFR parts 40 and 70. Following detailed assessment of potential safeguards issues relevant to these facilities, a new MC and A rule was developed. The primary safeguards considerations are detection of the loss of special nuclear material, detection of clandestine production of special nuclear material of low strategic significance for unauthorized use or distribution, and detection of unauthorized production of uranium enriched to ≥10 wt % U-235. The primary safeguards concerns identified were the large absolute limit of error associated with the material balance closing, the inability to shutdown some uranium enrichment technologies to perform a cleanout inventory of the process system, and the flexibility of some of these technologies to produce higher enrichments. Unauthorized production scenarios were identified for some technologies that could circumvent the detection of the production and removal of 5 kilograms of U-235 as high-enriched uranium through conventional material control and accounting programs. Safeguards techniques, including the use of production and process control information, measurements, and technical surveillance, were identified to compensate for these concerns

  20. Database design for Physical Access Control System for nuclear facilities

    International Nuclear Information System (INIS)

    Sathishkumar, T.; Rao, G. Prabhakara; Arumugam, P.

    2016-01-01

    Highlights: • Database design needs to be optimized and highly efficient for real time operation. • It requires a many-to-many mapping between Employee table and Doors table. • This mapping typically contain thousands of records and redundant data. • Proposed novel database design reduces the redundancy and provides abstraction. • This design is incorporated with the access control system developed in-house. - Abstract: A (Radio Frequency IDentification) RFID cum Biometric based two level Access Control System (ACS) was designed and developed for providing access to vital areas of nuclear facilities. The system has got both hardware [Access controller] and software components [server application, the database and the web client software]. The database design proposed, enables grouping of the employees based on the hierarchy of the organization and the grouping of the doors based on Access Zones (AZ). This design also illustrates the mapping between the Employee Groups (EG) and AZ. By following this approach in database design, a higher level view can be presented to the system administrator abstracting the inner details of the individual entities and doors. This paper describes the novel approach carried out in designing the database of the ACS.

  1. Combustible gas concentration control facility and operation method therefor

    Energy Technology Data Exchange (ETDEWEB)

    Yoshikawa, Kazuhiro; Ando, Koji; Kinoshita, Shoichiro; Yamanari, Shozo; Moriya, Kimiaki; Karasawa, Hidetoshi

    1998-09-25

    The present invention provides a hydrogen gas-control facility by using a fuel battery-type combustible gas concentration reducing device as a countermeasure for controlling a hydrogen gas in a reactor container. Namely, a hydrogen electrode adsorb hydrogen by using an ion exchange membrane comprising hydrogen ions as a charge carrier. An air electrode adsorb oxygen in the air. A fuel battery converts recombining energy of hydrogen and oxygen to electric energy. Hydrogen in this case is supplied from an atmosphere in the container. Oxygen in this case is supplied from the air outside of the container. If hydrogen gas should be generated in the reactor, power generation of is performed by the fuel battery by using hydrogen gas, as a fuel, on the side of the hydrogen electrode of the fuel battery and using oxygen, as a fuel, in the air outside of the container on the side of the air electrode. Then, the hydrogen gas is consumed thereby controlling the hydrogen gas concentration in the container. Electric current generated in the fuel battery is used as an emergency power source for the countermeasure for a severe accident. (I.S.)

  2. Fuel conditioning facility zone-to-zone transfer administrative controls

    International Nuclear Information System (INIS)

    Pope, C. L.

    2000-01-01

    The administrative controls associated with transferring containers from one criticality hazard control zone to another in the Argonne National Laboratory (ANL) Fuel Conditioning Facility (FCF) are described. FCF, located at the ANL-West site near Idaho Falls, Idaho, is used to remotely process spent sodium bonded metallic fuel for disposition. The process involves nearly forty widely varying material forms and types, over fifty specific use container types, and over thirty distinct zones where work activities occur. During 1999, over five thousand transfers from one zone to another were conducted. Limits are placed on mass, material form and type, and container types for each zone. Ml material and containers are tracked using the Mass Tracking System (MTG). The MTG uses an Oracle database and numerous applications to manage the database. The database stores information specific to the process, including material composition and mass, container identification number and mass, transfer history, and the operators involved in each transfer. The process is controlled using written procedures which specify the zone, containers, and material involved in a task. Transferring a container from one zone to another is called a zone-to-zone transfer (ZZT). ZZTs consist of four distinct phases, select, request, identify, and completion

  3. NRC Information Notice No. 92-01: Cable damage caused by inadequate cable installation procedures and controls

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1993-01-01

    In June 1989, the Tennessee Valley Authority (TVA) removed the cables from a conduit in the reactor protection system of the Watts Bar Nuclear Plant, Unit 2, to inspect for damage. TVA selected this conduit in response to an employee's concern that a welding arc that struck the conduit in response to an employee's concern that a welding arc that struck the conduit during construction may have damaged cables in the conduit. When the cables were removed, TVA found significant damage in the insulation of some cables. This damage was not attributed to heat generated by the alleged welding arc. The damage was principally attributed to the pulling stresses exerted during the initial installation of the cables. Some of the cables had insulation removed down to the conductors. To assess the extent of cable damage and determine the scope of its investigation, TVA removed more cables from conduits that constituted the most difficult pulls (worst case) and found varying degrees of damage that it attributed to pulling stresses. To fill a conduit at Watts Bar, personnel used pull cords to pull more cables through the conduits over the top of existing cables. This practice is called ''pull-by.'' This practice can cause damage to the existing cables from the sawing action of the pull cords and the friction of cables as they are pulled over existing cables. TVA instituted programs to assess the adequacy of cable installation at all its nuclear facilities and take appropriate corrective actions. At Watts Bar, TVA replaced cables in conduits which exceeded a calculated threshold value of side wall bearing pressure (SWBP) and performed a high-potential (hi-pot) tests on a number of other cables in conduits with SWBP below the calculated threshold value

  4. On-off controller for installation to test the pressurized water reactor material

    International Nuclear Information System (INIS)

    Zauq, M.H.

    1982-05-01

    This report describes the design of an ON-OFF controller based on the 6800 microprocessor in its assembly language and its interfacing with its environment (sensors, periphery, etc). The controller is meant to control the temperature and the pressure inside an experimental chamber in which the material under test is placed. The ''Design basis accident'' conditions (e.g., LOCA) for a pressurized water reactor are simulated in the experimental chamber [fr

  5. Local control station for development, testing and maintenance of mirror fusion facility subsystem controls

    International Nuclear Information System (INIS)

    Ables, E.; Kelly, M.F.

    1985-01-01

    A Local Control Station (LCS) was designed and built to provide a simplified ad easily configurable means of controlling any Mirror Fusion Test Facility (MFTF-B) subsystem for the purpose of development, testing and maintenance of the subsystem. All MFTF-B Subsystems incorporate at least one Local Control Computer (LCC) that is connected to and accepts high level commands from one of the Supervisory Control and Diagnostic System (SCDS) computers. The LCS connects directly to the LCC in place of SCDS. The LCS communicates with the subsystem hardware using the same SCDS commands that the local control computer recognizes and as such requires no special configuration of the LCC

  6. Control and protection system for an electron injector installed in a high-voltage terminal

    International Nuclear Information System (INIS)

    Martin, D.; Radu, A.; Baciu, G.; Grigore, D.

    1979-01-01

    The basic principles of operation of the control and protection system for an electron accelerator gun are described. The electron gun parameters are independently controlled by using four special secondary windings of the high-voltage transformer providing the accelerating voltage. Four groups of thyristor ac regulators employing phase control are connected so as to provide independent adjustment of each parameter of the gun. The power controller of modular construction has a single-phase supply from the 50 Hz 220 V mains. (orig.)

  7. BATING A REFERENCE INSTALLATION BASED ON CONTROLLED-POTENTIAL COULOMETRY METOD IN THE FRAME OF IMPROVING THE STATE PRIMARY STANDARD GET 176 AND ITS MEASUREMENT CAPABILITIES

    Directory of Open Access Journals (Sweden)

    V. M. Zyskin

    2016-01-01

    Full Text Available The results of developing of reference installation, based on a controlled-potential coulometry, in the frame of improving the State primary standard of the units of mass (molar fraction and mass (molar concentration of a component in the liquid and solid substances and materials GET 176 are presented. The physical principles of controlled-potential coulometry, content and metrological characteristics of the developed installation are considered. Measurement results of copper, iron and lead contents in the certified reference materials of metals' solutions and CRM of brass produced by BAM, Germany, obtained using reference installation are given.

  8. Proposal for the award of a blanket contract for the supply, installation and maintenance of the LHC access control system

    CERN Document Server

    2004-01-01

    This document concerns the award of a blanket contract for the supply, installation and maintenance of the LHC access control system. Following a market survey carried out among 134 firms in fifteen Member States, a call for tenders (IT-3026/TS/LHC) was sent on 22 January 2004 to eight firms and eight consortia in six Member States. By the closing date, CERN had received nine tenders from two firms and seven consortia in five Member States. The Finance Committee is invited to agree to the negotiation of a blanket contract with the consortium CEGELEC CENTRE EST (FR) - CEGELEC (NL), the lowest technically compliant bidder, for the supply, installation and maintenance of the LHC access control system for a total amount not exceeding 4 600 000 euros (7 141 000 Swiss francs), subject to revision for inflation from 1 January 2007. The rate of exchange used is that stipulated in the tender. The firm has indicated the following distribution by country of the contract value covered by this adjudication proposal: FR - ...

  9. NRC Information No. 87-56: Improper hydraulic control unit installation at BWR plants

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    This information notice is being provided to alert addressees to a potential problem that could affect the ability of the hydraulic control units (HCUs) to control the positioning of the control rods in the event of an earthquake. In addition, the potential for damage to the control rod drive (CRD) system withdraw lines that exists under certain conditions could result in a small-break loss-of-coolant accident in the HCU area. The CRD system controls the position of the control rods within the reactor core either to change reactor core power or to rapidly shut down the reactor (scram). The HCU is a major component of the CRD system that incorporates all the hydraulic, electrical, and pneumatic equipment necessary to move one CRD mechanism during normal or scram operations. This equipment, which includes the accumulators, CRD insert lines, CRD withdraw lines, and scram valves, is supported by the HCU frames. If a sufficiently large number of HCU frame bolts are missing or loose, a Safe Shutdown Earthquake (SSE) could result in damage affecting the ability of the CRD system to control the positioning of the control rods. In addition, damage to a CRD withdraw line could result in a small-break loss-of-coolant accident in the area of the HCUs

  10. Some technical aspects of the nuclear material accounting and control at nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Miller, O.A.; Babaev, N.S.; Gryazev, V.M.; Gadzhiev, G.I.; Gabeskiriya, V.Ya.

    1977-01-01

    The possibilities of nuclear material accounting and control are discussed at nuclear facilities of fuel cycle (WWER-type reactor, fuel fabrication plant, reprocessing plant and uranium enrichment facility) and zero energy fast reactor facility. It is shown that for nuclear material control the main method is the accounting with the application isotopic correlations at the reprocessing plant and enrichment facility. Possibilities and limitations of the application of destructive and non-destructive methods are discussed for nuclear material determinations at fuel facilities and their role in the accounting and safeguards systems as well as possibilities of the application of neutron method at a zero energy fast reactor facility [ru

  11. Tuberculosis Infection Control in Health-Care Facilities: Environmental Control and Personal Protection.

    Science.gov (United States)

    Lee, Ji Yeon

    2016-10-01

    Transmission of tuberculosis (TB) is a recognized risk to patients and healthcare workers in healthcare settings. The literature review suggests that implementation of combination control measures reduces the risk of TB transmission. Guidelines suggest a three-level hierarchy of controls including administrative, environmental, and respiratory protection. Among environmental controls, installation of ventilation systems is a priority because ventilation reduces the number of infectious particles in the air. Natural ventilation is cost-effective but depends on climatic conditions. Supplemented intervention such as air-cleaning methods including high efficiency particulate air filtration and ultraviolet germicidal irradiation should be considered in areas where adequate ventilation is difficult to achieve. Personal protective equipment including particulate respirators provides additional benefit when administrative and environmental controls cannot assure protection.

  12. Development of control technology for HTTR hydrogen production system with mock-up test facility

    International Nuclear Information System (INIS)

    Ohashi, Hirofumi; Inaba, Yoshitomo; Nishihara, Tetsuo; Takeda, Tetsuaki; Hayashi, Koji; Takada, Shoji; Inagaki, Yoshiyuki

    2006-01-01

    The Japan Atomic Energy Agency has been planning the demonstration test of hydrogen production with the High Temperature Engineering Test Reactor (HTTR). In a HTTR hydrogen production system (HTTR-H2), it is required to control a primary helium temperature within an allowable value at a reactor inlet to prevent a reactor scram. A cooling system for a secondary helium with a steam generator (SG) and a radiator is installed at the downstream of a chemical rector in a secondary helium loop in order to mitigate the thermal disturbance caused by the hydrogen production system. Prior to HTTR-H2, the simulation test with a mock-up test facility has been carried out to establish the controllability on the helium temperature using the cooling system against the loss of chemical reaction. It was confirmed that the fluctuations of the helium temperature at chemical reactor outlet, more than 200 K, at the loss of chemical reaction could be successfully mitigated within the target of ±10 K at SG outlet. A dynamic simulation code of the cooling system for HTTR-H2 was verified with the obtained test data

  13. Micooprecessor controlled facility for I.N.A.A. using short half life nuclides

    International Nuclear Information System (INIS)

    Bode, P.; Korthoven, P.J.M.; Bruin, M. de

    1986-01-01

    At IRI a new, fully atomated facility for short half life INAA is being developed and installed at the Institute 2 MW reactor. The fast rabbit transfer system is constructed only of plastic and carbonfiber parts, so that rabbit contamination is minimized. This system is automated in such a way that it can operate safely without direct supervision; the sequence of irradiations and measurements is optimized by a computer-program for a given set of samples and analysis procedures. The rabbit system is controlled by an Apple IIe-computer connected to the central PDP 11/44 system of the Radiochemistry department. For a given set of samples and required analysis procedures (irradiation-,decay-, and measurement times) the central computer calculates an optimal sequence of individual actions (transfer from and to the reactor, sample storage of detector) to be carried out by the system. This sequence is loaded into the Apple-computer as a series of commands together with timing information. Actual control of the procedure occurs through the peripheral computer, which makes the system independent of delays or break-downs of the central multi-user computer system. Hardware, software and operating characteristics of the fast rabbit system will be discussed. (author)

  14. Installation of the product transport system and control system for the Co-60 irradiator at the Institute of Investigations of the Alimentary Industry (IIIA), La Havana, Cuba

    International Nuclear Information System (INIS)

    Tran Khac An; Le Minh Tuan; Pham Thi Thu Hong; Nguyen Thanh Cuong; Huynh Dong Phuong; Ha Thanh Viet; Truong Vu Thanh Nhan

    2016-01-01

    Under the protocol of international cooperation in science and technology between Vietnam and Cuba - “Installation of the product transport system and control system for the Cobalt-60 irradiator at the Institute of Investigations of the Alimentary Industry (IIIA)”, the renovation of the irradiator has been started since 2012 and carried out by Research and Development Center for Radiation Technology (VINAGAMMA). The renovation work comprises the installation of the tote box transport system that was designed and constructed by Isotope Institute Budapest, Hungary, the installation of the PLC based control system which were designed and constructed by VINAGAMMA, installations of technological systems and training Cuban irradiator operators. The project has been successfully implemented and the industrial Co-60 irradiator with new control system has been put into operation. (author)

  15. Control strategies used in the control software for the Heavy Ion Research Facility in Lanzhou

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, Wen-Xiong [College of Power Engineering, Chongqing University, Chongqing 400044 (China); Postdoctoral Station, Chongqing University, Chongqing 400044 (China); Wang, Yan-Yu [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Pan, Liang-Ming [College of Power Engineering, Chongqing University, Chongqing 400044 (China); Tu, Sheng-Pan [State Grid Chongqing Maintenance Company, Chongqing 400044 (China)

    2016-07-01

    Automation control systems are important for the operation of an accelerator. To ensure the reliable, stable and flexible operation of the Heavy Ion Research Facility in Lanzhou (HIRFL), several control systems are developed. The developed control systems are the SECRAL control system, the LECR3 control system, the LAPECR1 control system and the Electro-Static septum control system. The corresponding control software systems are developed using Visual C++. To ensure the accuracy, stability and flexibility of the control systems, some special control strategies are developed in the control software systems. This paper provides a detailed description of the main control strategies used in the control software systems. The main control strategies are composed of a reliable communication mechanism, a correct data/command transmission mechanism, an efficient data storage mechanism and an interlock protection mechanism. To guarantee a reliable communication between the devices for the commercially purchased devices and the built in-house ones, a modified heartbeat method is developed. To provide flexible reconstitution function for the control systems, the command queue and the state machine are combined. The message mechanism and the multiple windows mechanism are also used for the module mechanism. The relevant control systems are introduced as examples of these control strategies. These systems have been running stably for several years.

  16. Control strategies used in the control software for the Heavy Ion Research Facility in Lanzhou

    International Nuclear Information System (INIS)

    Zhou, Wen-Xiong; Wang, Yan-Yu; Pan, Liang-Ming; Tu, Sheng-Pan

    2016-01-01

    Automation control systems are important for the operation of an accelerator. To ensure the reliable, stable and flexible operation of the Heavy Ion Research Facility in Lanzhou (HIRFL), several control systems are developed. The developed control systems are the SECRAL control system, the LECR3 control system, the LAPECR1 control system and the Electro-Static septum control system. The corresponding control software systems are developed using Visual C++. To ensure the accuracy, stability and flexibility of the control systems, some special control strategies are developed in the control software systems. This paper provides a detailed description of the main control strategies used in the control software systems. The main control strategies are composed of a reliable communication mechanism, a correct data/command transmission mechanism, an efficient data storage mechanism and an interlock protection mechanism. To guarantee a reliable communication between the devices for the commercially purchased devices and the built in-house ones, a modified heartbeat method is developed. To provide flexible reconstitution function for the control systems, the command queue and the state machine are combined. The message mechanism and the multiple windows mechanism are also used for the module mechanism. The relevant control systems are introduced as examples of these control strategies. These systems have been running stably for several years.

  17. 14 CFR 171.159 - Installation requirements.

    Science.gov (United States)

    2010-01-01

    ... Installation requirements. (a) The facility must be installed according to accepted good engineering practices... must have a reliable source of suitable primary power, either from a power distribution system or...

  18. 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

  19. Solar heating and cooling system installed at RKL Controls Company, Lumberton, New Jersey. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-03-01

    Solar heating and cooling of a 40,000 square foot manufacturing building, sales offices and the solar computer control center/display room are described. Information on system description, test data, major problems and resolutions, performance, operation and maintenance manual, manufacturer's literature and as-built drawings are provided also. The solar system is composed of 6000 square feet of Sunworks double glazed flat plate collectors, external above ground storage subsystem, controls, ARKLA absorption chiller, heat recovery and a cooling tower.

  20. Electron beam deflection control system of a welding and surface modification installation

    Science.gov (United States)

    Koleva, E.; Dzharov, V.; Gerasimov, V.; Tsvetkov, K.; Mladenov, G.

    2018-03-01

    In the present work, we examined the patterns of the electron beam motion when controlling the transverse with respect to the axis of the beam homogeneous magnetic field created by the coils of the deflection system the electron gun. During electron beam processes, the beam motion is determined the process type (welding, surface modification, etc.), the technological mode, the design dimensions of the electron gun and the shape of the processed samples. The electron beam motion is defined by the cumulative action of two cosine-like control signals generated by a functional generator. The signal control is related to changing the amplitudes, frequencies and phases (phase differences) of the generated voltages. We realized the motion control by applying a graphical user interface developed by us and an Arduino Uno programmable microcontroller. The signals generated were calibrated using experimental data from the available functional generator. The free and precise motion on arbitrary trajectories determines the possible applications of an electron beam process to carrying out various scientific research tasks in material processing.

  1. Auditing radiation sterilization facilities

    Science.gov (United States)

    Beck, Jeffrey A.

    The diversity of radiation sterilization systems available today places renewed emphasis on the need for thorough Quality Assurance audits of these facilities. Evaluating compliance with Good Manufacturing Practices is an obvious requirement, but an effective audit must also evaluate installation and performance qualification programs (validation_, and process control and monitoring procedures in detail. The present paper describes general standards that radiation sterilization operations should meet in each of these key areas, and provides basic guidance for conducting QA audits of these facilities.

  2. Human factors aspects of the major upgrade to control systems at the Los Alamos National Laboratory Plutonium Facility

    International Nuclear Information System (INIS)

    Higgins, J.; Pope, N.

    1997-01-01

    The Plutonium Facility (TA-55) at Los Alamos National Laboratory (LANL) has been in operation for over 15 years. It handles projects such as: stockpile maintenance, surveillance, and dismantlement; pit rebuild; plutonium power source fabrication for long duration spacecraft missions (e.g., Cassini); nuclear materials technology research; nuclear materials storage; and remediation of nuclear waste. The Operations Center of TA-55 is the nerve center of the facility where operators are on duty around the clock and monitor several thousand data points using the Facility Control System (FCS). The FCS monitors, displays, alarms, and provides some limited control of the following systems; HVAC, fire detection and suppression, radiation detection, electrical, and other miscellaneous systems. The FCS was originally based on late 1970s digital technology, which is not longer supported by the vendors. Additionally, the equipment failure rates increased notably in the 1990s. Thus, plans were put into place to upgrade and replace the FCS hardware, software, and display components with modernized equipment. The process was complicated by the facts that: the facility was operational and could not be totally closed for the modifications; complete documentation was not available for the existing system; the Safety Analyses for the facility were in the process of being upgraded at the same time; and of course limited time and budgets. This paper will discuss the human factors aspects of the design, installation, and testing of the new FCS within the above noted constraints. Particular items to be discussed include the functional requirements definition, operating experience review, screen designs, test program, operator training, and phased activation of the new circuits in an operational facility

  3. Analysis of support installation and strata control in ventilation tunnels and coal chutes in steep seams

    Energy Technology Data Exchange (ETDEWEB)

    Moroz, V D; Belyaev, A N; Kostyuk, I S

    1984-01-01

    The VNIMI and the Donugi branch in Gorlovka developed and tested a system for strata control in gate roads for ventilation and in coal chutes in inclined and steep medium and thick coal seams. The roof is supported by cribbings made of slabs of reinforced concrete with yielding elements. Timber is used as yielding material. Tests showed that thickness of yielding layers between concrete slabs should range from 15 to 20% of coal seam thickness. Yielding elements increase yield strength of the system to about 2 MN (load distribution is more regular). The tests show that the cribbings are an efficient system for strata control in workings driven in coal seams with dip angle from 35 to 60 degrees. Performance of concrete cribbings in ventilation gate roads and coal chutes in selected mines of the Ukrainian SSR is analyzed.

  4. Licensing of digital Instrumentation and Control in Radioisotope Production Facility

    International Nuclear Information System (INIS)

    Abdel-Aziz, L.Kh.; Lashin, R.; Mostafa, W.

    2012-01-01

    In spite of the rapid development of digital I and C systems in all major industries, it has for several reasons been slower in nuclear power plants. The most important reason is that only a few new plants have been ordered worldwide during the last ten years. A second reason is connected to the efforts needed in providing adequate evidence that the digital I and C system can be used in safety and safety related applications. This issue is connected to the effort needed in obtaining adequate assurance that the digital I and C will fulfill its intended function and contain no unintended function in all possible operational states during its entire life cycle. This paper presents an acceptance criteria for licensing a digital instrumentation and control system in a Radioisotope Production Facility(1), which is under commissioning. The acceptance criteria ensure that the I and C systems are designed to reach the highest degree of reliability with respect to the function they perform, operators will have clear and accessible availability to data on every plant parameter, and also ensure that the safety objectives have been covered

  5. History Data Facility in the SLC control system

    International Nuclear Information System (INIS)

    Johnson, R.G.; White, G.R.

    1991-10-01

    Two major enhancements to the SLC History Data Facility are described separately. First the internal design and procedures used for saving and using long term history data. Second the user interface, facilities and application of the History Data Comparisons sub-system, which is used for analyzing and correlating two or more accelerator device histories

  6. X-ray diagnostic installation with an image intensifier TV chain and a dose rate control device

    Energy Technology Data Exchange (ETDEWEB)

    Duemmling, K; Schott, O

    1977-04-28

    The person performing the examination can key up the dose rate briefly via the X-ray tube current, e.g., if the movement of a contrast medium is to be observed on the video screen and only certain phases in this movement, which are of diagnostic significance, are to be viewed more closely. The upward change necessary to reduce quantum noise by a certain factor is made by means of a switch. This at the same time results in a reduction of brightness (over-exposure) of the X-ray image on the video screen by actuating an aperture system between the image intensifier, and the TV camera. To prevent the X-ray tube from being overloaded during key-up of the dose rate, a time limit switch is installed in the control system.

  7. 40 CFR 270.315 - What air emissions control information must I keep at my facility?

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false What air emissions control information... Facility § 270.315 What air emissions control information must I keep at my facility? If you have air emission control equipment subject to 40 CFR part 264, subpart CC, you must keep the following information...

  8. Radiometric installations for automatic control of industrial processes and some possibilities of the specialized computers application

    International Nuclear Information System (INIS)

    Kuzino, S.; Shandru, P.

    1979-01-01

    It is noted that application of radioisotope devices in circuits for automation of some industrial processes permits to obtain the on-line information about some parameters of these processes. This information being passed to a computer, controlling the process, permits to obtain and maintain some optimum technological perameters of this process. Some elements of the automation stem projecting are given from the poin of wiev of the radiometric devices tuning, calibration of the radiometric devices with the purpose to get a digital answer in the on-line regime with the preset accuracy and thrustworthyness levels for supplying them to the controlling computer; determination of the system's reaction on the base of the preset statistical criteria; development, on the base of the data obtained from the computer, of an algorithm for the functional checking of radiometric devices' characteristics, - stability and reproductibility of readings in the operation regime as well as determination of the value threshold of an answer, depending on the measured parameter [ru

  9. A new Master Events Controller is prepared for installation in STS-99 Endeavour

    Science.gov (United States)

    2000-01-01

    A new Enhanced Main Events Controller (E-MEC) for Shuttle Endeavour sits on a table in a Quality trailer in the Launch Pad 39B area. The original E-MEC in Endeavour became suspect during the Jan. 31 launch countdown and mission STS-99 was delayed when NASA managers decided to replace it. Each Shuttle carries two enhanced master events controllers (E-MECs), which provide relays for onboard flight computers to send signals to arm and fire pyrotechnics that separate the solid rockets and external tank during assent. The E-MECs are located in the orbiter's aft compartment and both are needed for the Shuttle to be cleared for flight. Currently Endeavour and Columbia are the only two orbiters with the E-MECs. Built by Rockwell's Satellite Space Electronics Division, Anaheim, Calif., each unit weighs 65 pounds and is approximately 20 inches long, 13 inches wide and 8 inches tall. Previously, three Shuttle flights have been scrubbed or delayed due to faulty MECs: STS-73, STS-49 and STS-41-D. Before workers can begin E-MEC replacement efforts at the launch pad, cryogenic reactants must be offloaded from the orbiter and Space Shuttle ordnance disconnected. The next scheduled date for launch of STS-99 is Feb. 11 at 12:30 p.m. EST.

  10. Control of activities at the neighbourhood of basic nuclear installations. Guide Nr 15, Release of the 2016/03/24

    International Nuclear Information System (INIS)

    2016-01-01

    After having indicated the relevant regulatory texts, and described the context (the taking of nuclear activities into account in various town and land planning documents), this guide defines the ASN national doctrine for the control of activities about basic nuclear installations (BNI) and at presenting tools aiming at limiting the presence and growth of populations exposed to nuclear risks. It recalls and discusses the four main pillars of the management of risks posed by BNIs: risk reduction at the origin (on charge of the operator), implementation of emergency and rescue plans, preventive information of population and local communities, and control of activities in areas exposed to the risks. It states the principles adopted by the ASN regarding the control of activities about BNIs. This doctrine is based on three principles: to preserve the rescue plan operability, to favour a local development beyond an area of risk with fast kinetics, and to enable a controlled development which responds to the needs of the resident population. Then, the issue of land use conditions is addressed and discussed: objectives to be reached, discussion of vulnerability levels depending on activities, management of new projects by using various tools (servitude of public interest, town planning documents and code)

  11. Operation and Maintenance of Water Pollution Control Facilities: A WPCF White Paper.

    Science.gov (United States)

    Hill, William R.; And Others

    1979-01-01

    Presented are the recommendations of the Water Pollution Control Federation for operation and maintenance consideration during the planning design, construction, and operation of wastewater treatment facilities. (CS)

  12. Installation Art

    DEFF Research Database (Denmark)

    Petersen, Anne Ring

    Despite its large and growing popularity – to say nothing of its near-ubiquity in the world’s art scenes and international exhibitions of contemporary art –installation art remains a form whose artistic vocabulary and conceptual basis have rarely been subjected to thorough critical examination....... In Installation Art: Between Image and Stage, Anne Ring Petersen aims to change that. She begins by exploring how installation art developed into an interdisciplinary genre in the 1960s, and how its intertwining of the visual and the performative has acted as a catalyst for the generation of new artistic...... phenomena. It investigates how it became one of today’s most widely used art forms, increasingly expanding into consumer, popular and urban cultures, where installation’s often spectacular appearance ensures that it meets contemporary demands for sense-provoking and immersive cultural experiences. The main...

  13. Installation Art

    DEFF Research Database (Denmark)

    Petersen, Anne Ring

    . In Installation Art: Between Image and Stage, Anne Ring Petersen aims to change that. She begins by exploring how installation art developed into an interdisciplinary genre in the 1960s, and how its intertwining of the visual and the performative has acted as a catalyst for the generation of new artistic......Despite its large and growing popularity – to say nothing of its near-ubiquity in the world’s art scenes and international exhibitions of contemporary art –installation art remains a form whose artistic vocabulary and conceptual basis have rarely been subjected to thorough critical examination...... phenomena. It investigates how it became one of today’s most widely used art forms, increasingly expanding into consumer, popular and urban cultures, where installation’s often spectacular appearance ensures that it meets contemporary demands for sense-provoking and immersive cultural experiences. The main...

  14. Border installations

    International Nuclear Information System (INIS)

    Lenaerts, Koen

    1988-01-01

    Border installations cover all nuclear plants located near the border with a neighbouring state. However, the actual distance depends on the context. The distance can vary considerably. Also the prohibition on siting near a heavily populated area also defines the actual distance variably. The distance criteria may be modified by other factors of topography, prevailing climate and so on. Various examples which illustrate the problems are given. For example, the Creys-Melville nuclear power plant is 80km from Geneva and the Cattonam installation is 12km from the French border with Luxembourg and Germany. The Cattenom case is explained and the legal position within the European Institutions is discussed. The French licensing procedures for nuclear power stations are described with special reference to the Cattenom power plant. Border installations are discussed in the context of European Community Law and Public International Law. (U.K.)

  15. Higher Education Facilities: The SmartGrid Earns a Doctorate in Economics

    Science.gov (United States)

    Tysseling, John C.; Zibelman, Audrey; Freifeld, Allen

    2011-01-01

    Most higher education facilities have already accomplished some measure of a "microgrid" investment with building control systems (BCS), energy management systems (EMS), and advanced metering infrastructure (AMI) installations. Available energy production facilities may include boilers, chillers, cogeneration, thermal storage, electrical…

  16. Installation and test of new human machine interface of the HANARO control computer

    International Nuclear Information System (INIS)

    Kim, Min Jin; Kim, Y. K.; Choi, Y. S.; Jung, H. S.; Kim, H. K.; Wu, J. S.

    2002-06-01

    As a first step of the long-term replace plan, we upgraded BCS, the HMI of HANARO control computer. ProcessSuite system that was imported this time consists of a workstation class PC and application program that is compatible with MLC and operates on Windows NT 4.0. Operation data storage function that was disabled due to disk drive failure of BCS is now enabled and log scale display and a secure means to enter demand power are made available. Mostly the configuration of ProcessSuite system was found correct although we found some discrepancy and corrected them. The further works to be done are the addition of graphic display screens based on flow diagram, selection and procurement of alarm printer, provision for chart recorders, transmission of important operating parameters and so on. After that, we will produce some documents to prove the performance of new system and prepare user manual for operator

  17. DEVELOPING UNIVERSAL INSTALLATION WITH AUTOMATIC MONITORING AND CONTROL PROCESS OF MIXING, WHIPPING AND MOLDING BISCUIT DOUGH

    Directory of Open Access Journals (Sweden)

    E. I. Ponomareva

    2013-01-01

    Full Text Available As products of high nutritional value can be used bakery products from a mixture of rye and wheat flour with the application of a grain of rye. Use whole grains assumes control of its quality according to organoleptic, physico-chemical and hygienic indices. Method of determining the color characteristics of grain scanner-metric method us-ing tablet scanner HP ScanJet 3570C with application of computer processing of images in RGB color mode is proposed. Application of the method to determine the color characteristics showed that rye, prepared in different ways, has different intensity of coloring, and the maximum intensity of the color components is observed at native grain.

  18. Good practice recommendations - medical-professional control of internal exposure to radionuclides in nuclear base installations

    International Nuclear Information System (INIS)

    Berard, Philippe; Blanchin, Nicolas; Fottorino, Robert; Gonin, Michele; Quesne, Benoit; Agrinier, Anne-Laure; Bourgaut, Laurent; Blanchardon, Eric; Challeton de Vathaire, Cecile; Franck, Didier; Piechowski, Jean; Fritsch, Paul; Poncy, Jean-Luc

    2011-07-01

    The first part of this voluminous report presents the context and method of definition of recommendations for a clinical practice and comprises a literature review of national, European and international recommendations, standards and work-group reports. The second part develops recommendations under four main themes: assessment of the committed effective dose (objectives, implementation, communication, traceability and archiving), control programs, dosimetric estimation based on results, and health risk and taking into care by the occupational physician. The authors adopted the same structure for each sub-theme or issue: target extract of regulatory and standard requirements and international recommendations, analysis of literature and of data from professional practices, opinion of the work-group, and graded recommendations with respect to the proof level

  19. JRR-3 neutron radiography facility

    International Nuclear Information System (INIS)

    Matsubayashi, M.; Tsuruno, A.

    1992-01-01

    JRR-3 neutron radiography facility consists of thermal neutron radiography facility (TNRF) and cold neutron radiography facility (CNRF). TNRF is installed in JRR-3 reactor building. CNRF is installed in the experimental beam hall adjacent to the reactor building. (author)

  20. 14 CFR 171.9 - Installation requirements.

    Science.gov (United States)

    2010-01-01

    ...) The facility must be installed according to accepted good engineering practices, applicable electric... a power distribution system or locally generated, with a supplemental standby system, if needed. (c...

  1. State of exposure control for workers engaging in radiation works and state of radioactive waste management in nuclear reactor facilities for test and research and nuclear reactor facilities at research and development stage, fiscal year 1995

    International Nuclear Information System (INIS)

    1996-01-01

    This is the summary of the reports submitted in fiscal year 1995 by the installers of the nuclear reactor facilities for test and research or at research and development stage, conforming to the related law. The individual dose equivalent of the workers engaging in radiation works in fiscal year 1995 was sufficiently lower than the prescribed limit in all reactor facilities. As for the released quantities of gaseous and liquid wastes, the radioactive substances in the air and water outside the monitor zones never exceeded the prescribed concentration limit in all reactor facilities. In the reactor facilities, for which the target values of release control have been determined, the values were less than the targets in all cases. The increase of stored radioactive solid waste decreased as the dismantling works of the reactor auxiliary system of the nuclear powered ship 'Mutsu' were finished in fiscal year 1994. As the amount of stored radioactive solid waste approaches the installed capacity, the preservation capacity of the existing waste preservation building was increased. (K.I.)

  2. Nuclear installations

    International Nuclear Information System (INIS)

    2001-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  3. Nuclear installations

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 2 of the document contains some details about the existing Brazilian nuclear installations. Also, safety improvements at Angra 1 and aspects of Angra 2 and 3 are reported

  4. Safety culture in nuclear installations - The role of the regulator

    International Nuclear Information System (INIS)

    Karigi, Alice W.

    2002-01-01

    Safety culture is an amalgamation of values, standards, morals and norms of acceptable behavior by the licensees, Radiation workers and the Regulator. The role played by a Regulator in establishing safety culture in a nuclear installation is that related to Authorization, review, assessment, inspection and enforcement. The regulator is to follow the development of a facility or activity from initial selection of the site through design, construction, commissioning, radioactive waste management through to decommissioning and closure. He is to ensure safety measures are followed through out the operation of the facility by laying down in the license conditions of controlling construction of nuclear installations and ensuring competence of the operators. (author)

  5. Installation and commissioning of instantaneous dose rate monitoring system

    CERN Document Server

    Iaydjiev, Plamen

    2018-01-01

    INRNE-Sofia was working on the installation and commissioning of new instantaneous dose rate monitoring system for the GIF++ facility at CERN. The final device, containing an 8-channels readout board was designed and tested at the CERN facility during November 2017, in an irradiation campaign supported by the AIDA-2020 TA program. The system is designed to be fully integrated in the GIF++ control system and the data measured are available to the users.

  6. Fuel cycle facility control system for the Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    Benedict, R.W.; Tate, D.A.

    1993-01-01

    As part of the Integral Fast Reactor (IFR) Fuel Demonstration, a new distributed control system designed, implemented and installed. The Fuel processes are a combination of chemical and machining processes operated remotely. To meet this special requirement, the new control system provides complete sequential logic control motion and positioning control and continuous PID loop control. Also, a centralized computer system provides near-real time nuclear material tracking, product quality control data archiving and a centralized reporting function. The control system was configured to use programmable logic controllers, small logic controllers, personal computers with touch screens, engineering work stations and interconnecting networks. By following a structured software development method the operator interface was standardized. The system has been installed and is presently being tested for operations

  7. Study of the Ubiquitous Hog Farm System Using Wireless Sensor Networks for Environmental Monitoring and Facilities Control

    Directory of Open Access Journals (Sweden)

    Jeonghwan Hwang

    2010-12-01

    Full Text Available Many hog farmers are now suffering from high pig mortality rates due to various wasting diseases and increased breeding costs, etc. It is therefore necessary for hog farms to implement systematic and scientific pig production technology to increase productivity and produce high quality pork in order to solve these problems. In this study, we describe such a technology by suggesting a ubiquitous hog farm system which applies WSN (Wireless Sensor Network technology to the pig industry. We suggest that a WSN and CCTV (Closed-circuit television should be installed on hog farms to collect environmental and image information which shall then help producers not only in monitoring the hog farm via the Web from outside the farm, but also facilitate the control of hog farm facilities in remote locations. In addition, facilities can be automatically controlled based on breeding environment parameters which are already set up and a SMS notice service to notify of deviations shall provide users with convenience. Hog farmers may increase production and improve pork quality through this ubiquitous hog farm system and prepare a database with information collected from environmental factors and the hog farm control devices, which is expected to provide information needed to design and implement suitable control strategies for hog farm operation.

  8. Assessment of wireless Sensor Networks for Digital Instrument and Control System at Nuclear Facilities

    International Nuclear Information System (INIS)

    Gomma, R.I.M.

    2015-01-01

    Instrumentation and Control (I and C) systems play a crucial role in the operation of Nuclear Power Plants (NPPs). The most important task of I and C systems is to ensure safety, availability, and performance of the plant. The advanced generation of NPP design is expected to have the higher degree of automation; consequently, it requires new solutions in both sensing technologies and digital control. In general, the world’s nuclear power fleet is relying on the progress of digital electronics and information technology, to create incentives for integrated replacement of traditional analog electronics with novel digital I and C systems that rely on wireless technology. Moreover, as the domain of Wireless Sensor Networks (WSN) increases its market share in many industrial, health, and critical applications, it has matured significantly. As a result, the barriers to the nuclear industry entry will surely continue to decrease further. Nowadays, several WSN deployments for on-line monitoring of the nuclear environment have been recently addressed by incremental and experimental networks. Furthermore, upon tightening new regulations, the demand for using smart wireless sensing for safety, and surveillance applications of nuclear installations are growing rapidly. The first part of this thesis describes the design of a practical small-scale WSN that allows smart real-time monitoring of radiation levels at nuclear facilities. A wireless system combined with a radiation sensor and associated peripherals been developed and implemented on ZigBee technology using the TI CC2530 chip. The radiation sensor uses a Geiger Muller Tube (GMT) as a reliable detector for the radioactive particulates in the gaseous effluent vented from nuclear facilities. The WSN allows the operators to record and control the radiation levels emitted into the environment, and it is supported by a warning system, for the early detection of radiation release. We evaluated the performance of the radiation

  9. Installation of foundation fieldbus to KUR

    International Nuclear Information System (INIS)

    Ishihara, Shinji; Fujita, Yoshiaki

    1999-11-01

    The instrumentation and control system for the research reactor in Research Reactor Institute, Kyoto University has been used for the safe and steady operation since the initial critical attainment in 1964. It has been modified and added many devices in the chance of increasing the reactor power from 1 MW to 5 MW, installing new experimental facilities or fitting to modified nuclear regulations. In order to avoid the unscheduled shutdown of the research reactor by cause the failure of the devices, most of instrumentation system was renewed in 1999. Operating the research reactor more safely and reliably, Supervisory Control Automation and Data Acquisition System which employed personal computers with the Windows NT operating system was added to the conventional instrumentation system, and the fieldbus system called Foundation Fieldbus was installed. Compared with conventional instrumentation system, each fieldbus system has some advantages. Many kinds of fieldbus systems have been developed and sold on the markets in some countries. Foundation Fieldbus standardizing international, which was able to use the devices made by multi-vendor was tentatively installed to study particular techniques about Foundation Fieldbus. The primary coolant flow rate, the temperature difference between the reactor tank inlet and outlet temperatures, the calorimetric power and the reactor power in nuclear instrumentation are monitored on human-machine interface devices on the fieldbus. The programmable logic controller is employed to control the information system for the reactor. This paper introduces Foundation Fieldbus installed. (author)

  10. Process control and dosimetry in a multipurpose irradiation facility

    Science.gov (United States)

    Cabalfin, E. G.; Lanuza, L. G.; Solomon, H. M.

    1999-08-01

    Availability of the multipurpose irradiation facility at the Philippine Nuclear Research Institute has encouraged several local industries to use gamma radiation for sterilization or decontamination of various products. Prior to routine processing, dose distribution studies are undertaken for each product and product geometry. During routine irradiation, dosimeters are placed at the minimum and maximum dose positions of a process load.

  11. Sizewell 'B' cable installation

    International Nuclear Information System (INIS)

    Gemmell, D.R.

    1992-01-01

    N G Bailey and Co. Ltd., UK were awarded the contract for the procurement, manufacture, works testing, works finishing, supply, delivery, off-loading, storage, installation, site finishing, preservation, setting to work and site testing of the following; the main cable installation throughout the Station including the addition of the Radioactive Waste Building, earthing and lightning protection installation, cable supporting steelwork and carriers and glanding and termination of cables. The cabling installation comprises power distribution, control and instrumentation cabling including all the associated cabling accessories, terminal boxes and similar components. The way that the contract was set-up, awarded and is now being carried out is described. Planning and industrial relations have been key features of the contract. (Author)

  12. Design concept of radiation control system for the high intensity proton accelerator facility

    Energy Technology Data Exchange (ETDEWEB)

    Miyamoto, Yukihiro; Ikeno, Koichi; Akiyama, Shigenori; Harada, Yasunori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    Description is given for the characteristic radiation environment for the High Intensity Proton Accelerator Facility and the design concept of the radiation control system of it. The facility is a large scale accelerator complex consisting of high energy proton accelerators carrying the highest beam intensity in the world and the related experimental facilities and therefore provides various issues relevant to the radiation environment. The present report describes the specifications for the radiation control system for the facility, determined in consideration of these characteristics. (author)

  13. Information note about the protection of nuclear facilities against aircraft crashes; Note d'information sur la protection des installations nucleaires contre les chutes d'avions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight < 5.7 t), the military aircraft, and the commercial aircraft (w > 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

  14. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumentation and measurement techniques in fuel fabrication facilities

    International Nuclear Information System (INIS)

    Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

    1978-01-01

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. A general discussion is given of instrumentation and measurement techniques which are presently used being considered for fuel fabrication facilities. Those aspects which are most significant from the point of view of satisfying regulatory constraints have been emphasized. Sensors and measurement devices have been discussed, together with their interfacing into a computerized system designed to permit real-time data collection and analysis. Estimates of accuracy and precision of measurement techniques have been given, and, where applicable, estimates of associated costs have been presented. A general description of material control and accounting is also included. In this section, the general principles of nuclear material accounting have been reviewed first (closure of material balance). After a discussion of the most current techniques used to calculate the limit of error on inventory difference, a number of advanced statistical techniques are reviewed. The rest of the section deals with some regulatory aspects of data collection and analysis, for accountability purposes, and with the overall effectiveness of accountability in detecting diversion attempts in fuel fabrication facilities. A specific example of application of the accountability methods to a model fuel fabrication facility is given. The effect of random and systematic errors on the total material uncertainty has been discussed, together with the effect on uncertainty of the length of the accounting period

  15. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumentation and measurement techniques in fuel fabrication facilities

    Energy Technology Data Exchange (ETDEWEB)

    Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

    1978-01-01

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. A general discussion is given of instrumentation and measurement techniques which are presently used being considered for fuel fabrication facilities. Those aspects which are most significant from the point of view of satisfying regulatory constraints have been emphasized. Sensors and measurement devices have been discussed, together with their interfacing into a computerized system designed to permit real-time data collection and analysis. Estimates of accuracy and precision of measurement techniques have been given, and, where applicable, estimates of associated costs have been presented. A general description of material control and accounting is also included. In this section, the general principles of nuclear material accounting have been reviewed first (closure of material balance). After a discussion of the most current techniques used to calculate the limit of error on inventory difference, a number of advanced statistical techniques are reviewed. The rest of the section deals with some regulatory aspects of data collection and analysis, for accountability purposes, and with the overall effectiveness of accountability in detecting diversion attempts in fuel fabrication facilities. A specific example of application of the accountability methods to a model fuel fabrication facility is given. The effect of random and systematic errors on the total material uncertainty has been discussed, together with the effect on uncertainty of the length of the accounting period.

  16. Case-control study of leukaemia and non-Hodgkin's lymphoma in children in Caithness near the Dounreay nuclear installation

    International Nuclear Information System (INIS)

    Urquhart, J.D.; Black, R.J.; Muirhead, M.J.; Sharp, Linda; Maxwell, Margaret; Jones, D.A.; Eden, O.B.

    1991-01-01

    A case-control study was performed to examine whether the observed excess of childhood leukaemia and non-Hodgkin's lymphoma in the area around the Dounreay nuclear installation is associated with established risk factors, or with factors related to the plant, or with parental occupation in the nuclear industry. No raised relative risks were found for prenatal exposure to X-rays, social class of parents, employment at Dounreay before conception or diagnosis, father's dose of ionising radiation before conception, or child's residence within 50 m of the path of microwave transmission beams. Results also proved negative for all lifestyle factors except an apparent association with use of beaches within 25 km of Dounreay. However, this result was based on small numbers, arose in the context of multiple hypothesis testing, and is certainly vulnerable to possible systematic bias. It was concluded that the raised incidence of childhood leukaemia and non-Hodgkin's lymphoma around Dounreay cannot be explained by paternal occupation at Dounreay or by paternal exposure to external ionising radiation before conception. The observation of an apparent association between the use of beaches around Dounreay and the development of childhood leukaemia and non-Hodgkin's lymphoma might be an artefact of multiple testing and influenced by recall bias. (author)

  17. Control of the Saclay CEA's base nuclear installations - Inspection n. INS-2010-CEASAC-0006 31 May 2010-4 June 2010 - Safety management

    International Nuclear Information System (INIS)

    2010-01-01

    This document reports an inspection dedicated to safety management, and performed by the ASN (the French Nuclear Safety Authority) on several nuclear installations present on the CEA's Saclay site. The inspected installations have been the INBs (base nuclear installations) number 35 (STEL), 40 (Osiris), 49 (LHA), 50 (LECI), 77 (Poseidon) and 101 (Orphee), and four departments (CCSIMN, USL2TI, SP2S and DANS) involved in safety or in charge of it. The report describes the requested corrective actions about the quality of the internal diagnosis, about the follow-up of actions and directives, about internal authorizations, about the follow-up of commitments, about second level control, about the management of the return on experience, about interesting events, about the control of subcontractors. Some additional information requests are also formulated

  18. The actual state and problems of radiation control in medical facilities

    International Nuclear Information System (INIS)

    Kaneko, Masao

    1978-01-01

    Utilization of radiation was started in university hospitals, but recently, the established general inspections come to be very popular among general hospitals. Numerous kinds of nuclides are utilized for a number of purposes in university hospitals, while the kinds of nuclides utilized in general hospitals are quite limited. Concerning radiation safety control, film badge method is most popular among personal exposure control methods, while the combinations of film badge and pocket chamber methods, and film badge and TLD methods are also adopted. In many general hospitals, however, the exposure control tools are not equipped. Many kinds of safety control devices are installed for general controls. The laws so far mainly regulated the standards of buildings and installations, but did not specify the standard for accommodating RI-administered patients, and the preventive measures to secondary exposure and pollution, which often causes careless control. Therefore, the preventive measures to secondary injuries are required. (Kobatake, H.)

  19. Solution for remote handling in accelerator installations

    International Nuclear Information System (INIS)

    Burgerjon, J.J.; Ekberg, E.L.; Grisham, D.L.; Horne, R.A.; Meyer, R.E.; Flatau, C.R.; Wilson, K.B.

    1977-01-01

    A description is given of a remote-handling system designed for the Los Alamos Clinton P. Anderson Meson Physics Facility (LAMPF), versatile enough to be used in a variety of situations found around particle accelerators. The system consists of a bilateral (force-reflecting) servomanipulator installed on an articulated hydraulic boom. The boom also carries the necessary tools and observation devices. The whole slave unit can be moved by crane or truck to the area of operation. A control cable connects the slave unit with the control station, located at a safe distance in a trailer. Various stages of development as well as some operating experience are discussed

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

    Science.gov (United States)

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

    2010-11-15

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

  1. Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

  2. Leap Motion Gesture Control With Carestream Software in the Operating Room to Control Imaging: Installation Guide and Discussion.

    Science.gov (United States)

    Pauchot, Julien; Di Tommaso, Laetitia; Lounis, Ahmed; Benassarou, Mourad; Mathieu, Pierre; Bernot, Dominique; Aubry, Sébastien

    2015-12-01

    Nowadays, routine cross-sectional imaging viewing during a surgical procedure requires physical contact with an interface (mouse or touch-sensitive screen). Such contact risks exposure to aseptic conditions and causes loss of time. Devices such as the recently introduced Leap Motion (Leap Motion Society, San Francisco, CA), which enables interaction with the computer without any physical contact, are of wide interest in the field of surgery, but configuration and ergonomics are key challenges for the practitioner, imaging software, and surgical environment. This article aims to suggest an easy configuration of Leap Motion on a PC for optimized use with Carestream Vue PACS v11.3.4 (Carestream Health, Inc, Rochester, NY) using a plug-in (to download at https://drive.google.com/open?id=0B_F4eBeBQc3yNENvTXlnY09qS00&authuser=0) and a video tutorial (https://www.youtube.com/watch?v=yVPTgxg-SIk). Videos of surgical procedure and discussion about innovative gesture control technology and its various configurations are provided in this article. © The Author(s) 2015.

  3. A free-piston Stirling engine/linear alternator controls and load interaction test facility

    Science.gov (United States)

    Rauch, Jeffrey S.; Kankam, M. David; Santiago, Walter; Madi, Frank J.

    1992-01-01

    A test facility at LeRC was assembled for evaluating free-piston Stirling engine/linear alternator control options, and interaction with various electrical loads. This facility is based on a 'SPIKE' engine/alternator. The engine/alternator, a multi-purpose load system, a digital computer based load and facility control, and a data acquisition system with both steady-periodic and transient capability are described. Preliminary steady-periodic results are included for several operating modes of a digital AC parasitic load control. Preliminary results on the transient response to switching a resistive AC user load are discussed.

  4. Control technology for radioactive emissions to the atmosphere at US Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    Moore, E.B.

    1984-10-01

    The purpose of this report is to provide information to the US Environmental Protection agency (EPA) on existing technology for the control of radionuclide emissions into the air from US Department of Energy (DOE) facilities, and to provide EPA with information on possible additional control technologies that could be used to further reduce these emissions. Included in this report are generic discussions of emission control technologies for particulates, iodine, rare gases, and tritium. Also included are specific discussions of existing emission control technologies at 25 DOE facilities. Potential additional emission control technologies are discussed for 14 of these facilities. The facilities discussed were selected by EPA on the basis of preliminary radiation pathway analyses. 170 references, 131 figures, 104 tables.

  5. Control technology for radioactive emissions to the atmosphere at US Department of Energy facilities

    International Nuclear Information System (INIS)

    Moore, E.B.

    1984-10-01

    The purpose of this report is to provide information to the US Environmental Protection agency (EPA) on existing technology for the control of radionuclide emissions into the air from US Department of Energy (DOE) facilities, and to provide EPA with information on possible additional control technologies that could be used to further reduce these emissions. Included in this report are generic discussions of emission control technologies for particulates, iodine, rare gases, and tritium. Also included are specific discussions of existing emission control technologies at 25 DOE facilities. Potential additional emission control technologies are discussed for 14 of these facilities. The facilities discussed were selected by EPA on the basis of preliminary radiation pathway analyses. 170 references, 131 figures, 104 tables

  6. Environmental Control Plan for the Industrial Hygiene Field Services Facility; TOPICAL

    International Nuclear Information System (INIS)

    J. W. Donnelly

    2001-01-01

    This environmental control plan is for the Hanford Site's industrial hygiene field services facility, located in the 100-N Area. The facility is used for the maintenance and storage of respirators, respiratory equipment and testing, calibration and testing of industrial hygiene equipment, and asbestos fiber counting

  7. Current control of superconducting coils for fusion experimental facility

    International Nuclear Information System (INIS)

    Ise, T.; Etou, D.; Chikaraishi, H.; Takami, S.; Inoue, T.

    2003-01-01

    The LHD (Large Helical Device) has twelve superconducting coils and six dc power supplies, and following specifications are required for its control system; each coil current must be controlled independently, the steady state control error is less than 0.01% of the reference value, the current settling time for 0.1% of control error is less than 1 second, and the control system must be robust against turbulence caused by appearance and disappearance of the plasma, parameter errors and external electro-magnetic noises. In this paper, the design and test results of the coil current control system for the LHD are described. The good response and robustness are in the relation of trade off each other. H-infinity controller is one of schemes to guarantee robustness for stability. However, the independent responses of six coils were impossible by the H-infinity controller only. To resolve this problem, we applied a feed-forward control with the H-infinity control. Moreover, the advanced design method of H-infinity controller using μ-synthesis was applied to guarantee the control performance in the whole operating condition. As a result, good control results were obtained by experiments. (author)

  8. Process control and safeguards system plutonium inventory conrol for MOX fuel facility

    International Nuclear Information System (INIS)

    Mishima, T.; Aoki, M.; Muto, T.; Amanuma, T.

    1979-01-01

    The plutonium inventory control (PINC) system is a real-time material accountability control system that is expected to be applied to a new large-scale plutonium fuel production facility for both fast breeder reactor and heavy water reactor at the Power Reactor and Nuclear Development Corporation. The PINC is basically a system for material control but is expected to develop into a whole facility control system, including criticality control, process control, quality control, facility protection, and so forth. Under PINC, every process and storage area is divided into a unit area, which is the smallest unit for both accountability and process control. Item and material weight automatically are accounted for at every unit area, and data are simultaneously treated by a computer network system. Sensors necessary for the system are being developed. 9 figures

  9. System Configuration Management Implementation Procedure for the Cold Vacuum Drying Facility Monitoring and Control System

    International Nuclear Information System (INIS)

    ANGLESEY, M.O.

    2000-01-01

    The purpose of this document is to establish the System Configuration Management Implementation Procedure (SCMIP) for the Cold Vacuum Drying Facility (CVDF) Monitoring and Control System (MCS). This procedure provides configuration management for the process control system. The process control system consists of equipment hardware and software that controls and monitors the instrumentation and equipment associated with the CVDF processes. Refer to SNF-3090, Cold Vacuum Drying Facility Monitoring and Control System Design Description, HNF-3553, Annex B, Safety Analysis Report for the Cold Vacuum Drying Facility, and AP-CM-6-037-00, SNF Project Process Automation Software and Equipment Configuration. This SCMIP identifies and defines the system configuration items in the control system, provides configuration control throughout the system life cycle, provides configuration status accounting, physical protection and control, and verifies the completeness and correctness of these items

  10. Advanced Process Control Application and Optimization in Industrial Facilities

    Directory of Open Access Journals (Sweden)

    Howes S.

    2015-01-01

    Full Text Available This paper describes application of the new method and tool for system identification and PID tuning/advanced process control (APC optimization using the new 3G (geometric, gradient, gravity optimization method. It helps to design and implement control schemes directly inside the distributed control system (DCS or programmable logic controller (PLC. Also, the algorithm helps to identify process dynamics in closed-loop mode, optimizes controller parameters, and helps to develop adaptive control and model-based control (MBC. Application of the new 3G algorithm for designing and implementing APC schemes is presented. Optimization of primary and advanced control schemes stabilizes the process and allows the plant to run closer to process, equipment and economic constraints. This increases production rates, minimizes operating costs and improves product quality.

  11. Advanced Control Facility for the CERN-UNICOS Framework

    CERN Document Server

    Pezzetti, M; Coppier, H

    2010-01-01

    CERN, during last decade, has extensively applied the CERN/UNICOS framework to large scale cryoplant control system. An increase of interested to advanced control techniques and innovative simulation environment applied to cryogenic processes has also occur. Since new control algorithm development into UNICOS framework requires significant time, a control testing platform which can be externally connected can improve and simplify the procedure of testing advanced controllers implementation. In this context, the present paper describes the development of a control testing tool at CERN, which allows rapid control strategies implementation through the Matlab/Simulink® environment, coupled with the large scale cryogenics UNICOS control system or with the CERN PROCOS simulation environment. The time delays which are inherently introduced by network links and communication protocols are analyzed and experimentally identified. Security and reliability issues are also discussed.

  12. Peak load shifting control using different cold thermal energy storage facilities in commercial buildings: A review

    International Nuclear Information System (INIS)

    Sun, Yongjun; Wang, Shengwei; Xiao, Fu; Gao, Diance

    2013-01-01

    Highlights: • Little study reviews the load shifting control using different facilities. • This study reviews load shifting control using building thermal mass. • This study reviews load shifting control using thermal energy storage systems. • This study reviews load shifting control using phase change material. • Efforts for developing more applicable load shifting control are addressed. - Abstract: For decades, load shifting control, one of most effective peak demand management methods, has attracted increasing attentions from both researchers and engineers. Different load shifting control strategies have been developed when diverse cold thermal energy storage facilities are used in commercial buildings. The facilities include building thermal mass (BTM), thermal energy storage system (TES) and phase change material (PCM). Little study has systematically reviewed these load shifting control strategies and therefore this study presents a comprehensive review of peak load shifting control strategies using these thermal energy storage facilities in commercial buildings. The research and applications of the load shifting control strategies are presented and discussed. The further efforts needed for developing more applicable load shifting control strategies using the facilities are also addressed

  13. Border installations

    International Nuclear Information System (INIS)

    Lenaerts, K.

    1988-01-01

    This chapter highlights the legal problems raised by the concept of a border installation. Using the Cattenom nuclear power plant as an example, the author describes the different stages of the legal conflict raised by construction of the plant and analyses the relationship between French administrative law and some provisions of the Euratom Treaty. Based on the Treaty, the Community institutions have adopted directives to strengthen inter-State co-operation and consultation between neighbouring countries. He observes that these principles of co-operation, consultation and vigilance already exist in public international law; however, international case law has not yet made it possible to establish the strict liability of the constructing state in case of a nuclear accident (NEA) [fr

  14. FY 1989 report on the results of the development of the entrained bed coal gasification power plant. Part 3. Fabrication/installation of pilot plant (Fabrication/installation drawings and fabrication/installation pictures - 2/2); 1989 nendo seika hokokusho. Funryusho sekitan gaska hatsuden plant kaihatsu - Sono 3. Pilot plant seisaku suetsuke hen (Seisaku suetsukezu oyobi seisaku suetsuke shashin) (2/2)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-03-01

    For the purpose of establishing the technology of the integrated coal gasification combined cycle power generation, the fabrication, installation work, etc. were conducted of a 200t/d entrained bed coal gasification pilot plant, and fabrication/installation drawings and fabrication/installation pictures were summarized. In fabrication/installation drawings, drawings of the following were included: safety environmental equipment (total system diagram, layout scheme drawing, layout of electric room equipment, layout of control equipment room, etc.), total control system (structural drawing of the total control system, outline drawing of operation control panel, operator console of the integrated load pressure control system, operator console of the integrated sequential control system, central control panel, etc.), 66kV/6.9kV indoor switching station facilities (layout of equipment of indoor switching station facilities, outline drawing of the main transformer, outline drawing of cooler control panel of the main transformer, etc.), common facilities (total layout, diagram of the equipment cooling water pipe system, diagram of the fire-extinguishing water pipe system, etc.) In pictures of fabrication/installation, pictures of the following were included: gasifier equipment, gas refining facilities, gas turbine facilities, actual-pressure/actual-size combustor test equipment, safety environmental equipment, total control system, common facilities, etc. (NEDO)

  15. A facile route to shape controlled CdTe nanoparticles

    Energy Technology Data Exchange (ETDEWEB)

    Mntungwa, Nhlakanipho; Rajasekhar, Pullabhotla V.S.R. [Department of Chemistry, University of Zululand, Private Bag X1001, KwaDlangezwa 3886, Empangeni, KZN (South Africa); Revaprasadu, Neerish, E-mail: nrevapra@pan.uzulu.ac.za [Department of Chemistry, University of Zululand, Private Bag X1001, KwaDlangezwa 3886, Empangeni, KZN (South Africa)

    2011-04-15

    Research highlights: {yields} A facile hybrid solution based/thermolysis route has been used for the synthesis of hexadecylamine capped CdTe nanoparticles. {yields} This method involves the reaction by the addition of an aqueous suspension of a cadmium salt to a freshly prepared NaHTe solution. {yields} The cadmium salt plays an important role in the growth mechanism of the particles and hence its final morphology. - Abstract: Hexadecylamine (HDA) capped CdTe nanoparticles have been synthesized using a facile hybrid solution based/thermolysis route. This method involves the reaction by the addition of an aqueous suspension or solution of a cadmium salt (chloride, acetate, nitrate or carbonate) to a freshly prepared NaHTe solution. The isolated CdTe was then dispersed in tri-octylphosphine (TOP) and injected into pre-heated HDA at temperatures of 190, 230 and 270 deg. C for 2 h. The particle growth and size distribution of the CdTe particles synthesized using cadmium chloride as the cadmium source were monitored using absorption and photoluminescence spectroscopy. The final morphology of the CdTe nanoparticles synthesized from the various cadmium sources was studied by transmission electron microscopy (TEM) and high resolution TEM. The cadmium source has an influence on the final morphology of the particles.

  16. A facile route to shape controlled CdTe nanoparticles

    International Nuclear Information System (INIS)

    Mntungwa, Nhlakanipho; Rajasekhar, Pullabhotla V.S.R.; Revaprasadu, Neerish

    2011-01-01

    Research highlights: → A facile hybrid solution based/thermolysis route has been used for the synthesis of hexadecylamine capped CdTe nanoparticles. → This method involves the reaction by the addition of an aqueous suspension of a cadmium salt to a freshly prepared NaHTe solution. → The cadmium salt plays an important role in the growth mechanism of the particles and hence its final morphology. - Abstract: Hexadecylamine (HDA) capped CdTe nanoparticles have been synthesized using a facile hybrid solution based/thermolysis route. This method involves the reaction by the addition of an aqueous suspension or solution of a cadmium salt (chloride, acetate, nitrate or carbonate) to a freshly prepared NaHTe solution. The isolated CdTe was then dispersed in tri-octylphosphine (TOP) and injected into pre-heated HDA at temperatures of 190, 230 and 270 deg. C for 2 h. The particle growth and size distribution of the CdTe particles synthesized using cadmium chloride as the cadmium source were monitored using absorption and photoluminescence spectroscopy. The final morphology of the CdTe nanoparticles synthesized from the various cadmium sources was studied by transmission electron microscopy (TEM) and high resolution TEM. The cadmium source has an influence on the final morphology of the particles.

  17. Control de configuraciones peligrosas en instalaciones con riesgo asociado // Hazardous configurations control in risk related facilities

    Directory of Open Access Journals (Sweden)

    Antonio Torres - Valle

    2010-05-01

    Full Text Available ResumenEl control de configuraciones peligrosas en instalaciones con riesgo asociado es una aplicación delos Análisis Probabilistas de Seguridad (APS previos de las mismas. Una opción de mayor alcancees el uso de monitores de riesgo los que permiten la detección en tiempo real de talesconfiguraciones. Dada la complejidad de los APS y de los monitores de riesgo, esta tarea requiere depersonal experto. El documento presenta un método cualitativo de control de configuracionespeligrosas basado en matrices de dependencias. El algoritmo, informatizado en el códigoCONFIGURACION, puede ser aplicado sin necesidad de APS previos ni uso de monitores de riesgo.La sencillez del método justifica su extensión a instalaciones donde tales herramientas no se handesarrollado, permitiendo así la detección de las configuraciones peligrosas durante su explotación yelevando la seguridad de las plantas. Un sistema similar al descrito se utiliza como ayuda en laoperación de la central nuclear de Embalse. El artículo muestra el uso del método utilizando comobase un sistema de seguridad simplificado.Palabras claves: control de configuración, Análisis Probabilista de Seguridad (APS, matriz de___________________________________________________________________________AbstractThe hazardous configurations control in risk related facilities is an application of the previousProbabilistic Safety Analysis (PSA. A more complete option is the risk monitoring for the on-linedetection of these configurations. The expert personnel are required for this task take into account thecomplexity of the PSA and risk monitor. The paper presents a method of configuration control, basedon dependence matrixes. The algorithm is included in a computer code called CONFIGURACION, todetermine these situations in a qualitative way, without previous PSA results or using a Risk Monitor.The simplicity of the method warrants its application to facilities where these tools have not

  18. Power supply control system for experimental physical facilities

    International Nuclear Information System (INIS)

    Zelepukin, S.A.; Osipov, Eh.V.; Petrov, V.S.; Sergeev, V.A.; Uglekov, V.Ya.

    1979-01-01

    A multichannel (to 1024 channels) system for control of power supply voltage is descrited. The system consists of an analog commulator, a digital voltmeter and a special controller. The controller serves at the same time as an interface for connecting the system as a ''unit'' of the VECTOR and SUMMA unified electronic systems. The system has been realized for control of the photomultiplier power supply voltage of the MARK multipurpose experimental device (256 channels, the measurement accuracy is 0.2%, the measuring time is 500 ms per point). Software devised for the HP-2100 computer permits automatical comparison of photomultiplier power supply voltages with sample ones in the mode of continuous control of a single voltage or in the mode of programmed selection of voltages to provide the control in arbitrary order or automatic scanning

  19. Costs of fuel cycle industrial facilities: an international review; Couts des installations industrielles du cycle du combustible point a l'international

    Energy Technology Data Exchange (ETDEWEB)

    Macias, R.M

    2004-07-01

    This document presents, comments, and compares economic and financial data for industrial facilities concerning different aspects of the nuclear fuel cycle. It first comments the present situation and the short term trends for the natural uranium market, the conversion market, the enrichment market, the reprocessing market, the storage market. It gives an assessment of the elementary costs of the existing facilities for the different stages and processes: reprocessing, spent fuel warehousing (example of the CLAB in Sweden and comparison with other available data), warehousing of all types of wastes (examples of Habog in Netherlands, Zwilag in Switzerland), spent fuel storage (example of Yucca Mountain in the USA, Onkalo in Finland, projects and studies in Sweden), storage of vitrified wastes in Belgium, storing of transuranic wastes in the USA, storage of low and intermediate level and short life wastes in Sweden.

  20. 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.

  1. Optimizing design concepts for a building with photovoltaic facility; Systeme d'optimisation pour la conception d'un batiment avec une installation photovoltaique

    Energy Technology Data Exchange (ETDEWEB)

    Le Bail, Yann; Bedard, Claude [Departement du genie de la construction, ETS, Montreal (Canada); Zmeureanu, Radu [Departement du genie du batiment, civil et de l' environement, Universite de Concordia, Montreal (Canada)

    2010-07-01

    In Canada, the energy used in buildings represents 30% of total national consumption. The use of renewable sources of energy is clearly of interest in efforts to reduce dependency on fossil fuels, greenhouse gas emissions and the total level of energy consumption. This study presents a system for economic and environmental performance optimization of a photovoltaic apparatus installed on the roof of a commercial building. This optimization system was tested on a building in Montreal. The results demonstrate that the apparatus does not give sufficient returns either economically or environmentally in Quebec, due to the fact that the electricity supply there is low-priced and clean but it would provide such returns in Munich, where the repurchase price of photovoltaic and conventional electricity is high and conventional electricity is also a polluter. The optimization system proposed in this study allows the environmental and economic returns from a photovoltaic apparatus to be studied.

  2. The CEBAF [Continuous Electron Beam Accelerator Facility] control system architecture

    International Nuclear Information System (INIS)

    Bork, R.

    1987-01-01

    The focus of this paper is on CEBAF's computer control system. This control system will utilize computers in a distributed, networked configuration. The architecture, networking and operating system of the computers, and preliminary performance data are presented. We will also discuss the design of the operator consoles and the interfacing between the computers and CEBAF's instrumentation and operating equipment

  3. Automatically controlled facilities for irradiation of silicon crystals at the Rossendorf Research Reactor

    International Nuclear Information System (INIS)

    Ross, R.

    1988-01-01

    This report describes the facilities for neutron transmutation doping of silicon in GDR. The irradiation of silicon single crystals began at Rossendorf in 1978 with simple equipment. Only a small amount of silicon could be irradiated in it. The fast increasing need of NTD-silicon made it necessary to design and construct new and better facilities. The new facilities are capable of irradiating silicon from 2'' to 3'' in diameter. The irradiation process takes place automatically with the assistance of a computer. Material produced has an axial homogeneity of ± 7%. Irradiation riggs, techniques, irradiation control and quality control are discussed. (author). 4 figs

  4. Logistics of LEP installation

    International Nuclear Information System (INIS)

    Genier, C.; Capper, S.

    1988-01-01

    The size of the LEP project, coupled with the tight construction schedules, calls for organized planning, logistics, monitoring and control. This is being carried out at present using tools such as ORACLE the Relational Database Management System, running on a VAX cluster for data storage and transfer, micro-computers for on-site follow-up, and PC's running Professional ORACLE, DOS and XENIX linked to a communications network to receive data feedback concerning transport and handling means. Following over 2 years of installations, this paper presents the methods used for the logistics of installation and their results

  5. Wireless installation standard

    International Nuclear Information System (INIS)

    Lim, Hwang Bin

    2007-12-01

    This is divided six parts which are radio regulation law on securing of radio resource, use of radio resource, protection of radio resource, radio regulation enforcement ordinance with securing, distribution and assignment of radio regulation, radio regulation enforcement regulation on utility of radio resource and technical qualification examination, a wireless installation regulation of technique standard and safety facility standard, radio regulation such as certification regulation of information communicative machines and regulation of radio station on compliance of signal security, radio equipment in radio station, standard frequency station and emergency communication.

  6. Installation of a second superconducting wiggler at SAGA-LS

    Energy Technology Data Exchange (ETDEWEB)

    Kaneyasu, T., E-mail: kaneyasu@saga-ls.jp; Takabayashi, Y.; Iwasaki, Y.; Koda, S. [SAGA Light Source, 8-7 Yayoigaoka, Tosu 841-0005 (Japan)

    2016-07-27

    The SAGA Light Source is a synchrotron radiation facility consisting of a 255 MeV injector linac and a 1.4 GeV storage ring with a circumference of 75.6 m. A superconducting wiggler (SCW) with a peak magnetic field of 4 T has been routinely operating for generating hard X-rays since its installation in 2010. In light of this success, it was decided to install a second SCW as a part of the beamline construction by Sumitomo Electric Industries. To achieve this, machine modifications including installation of a new magnet power supply, improvement of the magnet control system, and replacement of the vacuum chambers in the storage ring were carried out. Along with beamline construction, installation and commissioning of the second SCW are scheduled to take place in 2015.

  7. Optimal control of indoor climate in agricultural storage facilities for potatoes and onions

    NARCIS (Netherlands)

    Lukasse, L.J.S.; Maldegem, van J.; Dierkes, E.; Voort, van der A.J.; Kramer-Cuppen, de J.E.; Kolk, van der G.

    2009-01-01

    This paper presents the use of receding horizon optimal control (RHOC) for optimal climate control in storage facilities for potatoes and onions. RHOC is used on a supervisory level above the classical feedback climate controller. Some theoretical issues on RHOC are discussed, amongst which a

  8. Administrative Arrangement between the Atomic Control Board of Canada and le Service central de surete des installations nucleaires du Ministere de l'Industrie et de l'Amenagement du Territoire de la Republique francaise for the Exchange of Technical Information and Cooperation in the Regulation of Nuclear Safety

    International Nuclear Information System (INIS)

    1991-01-01

    This Arrangement between the Atomic Energy Control Board of Canada (AECB) and the French Central Service for the Safety of Nuclear Installations (SCSIN) entered into force on the date of its signature and will remain in effect for five years. The Arrangement provides for the exchange of information between both agencies on the regulation of nuclear facilities and intervention measures in cases of emergency. This includes information on regulatory procedures for the safety of designated nuclear facilities, notification of important events, such as serious operating incidents, reactor shutdowns ordered by the regulatory authorities, etc. (NEA) [fr

  9. 30 CFR 57.4504 - Fan installations.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fan installations. 57.4504 Section 57.4504... Control Installation/construction/maintenance § 57.4504 Fan installations. (a) Fan houses, fan bulkheads... of combustible materials, except installed wiring, ground and track support, headframes, and direct...

  10. IPAD Paperless Work Control for Test Complex Facilities Management

    Data.gov (United States)

    National Aeronautics and Space Administration — The purpose of this project was to identify a way to improve the work control processes used at Stennis Space Center that are traditionally done via paper by...

  11. Air pollution control system testing at the DOE offgas components test facility

    International Nuclear Information System (INIS)

    Burns, D.B.; Speed, D.; VanPelt, W.; Burns, H.H.

    1997-01-01

    In 1997, the Department of Energy (DOE) Savannah River Site (SRS) plans to begin operation of the Consolidated Incineration Facility (CIF) to treat solid and liquid RCRA hazardous and mixed wastes. The Savannah River Technology Center (SRTC) leads an extensive technical support program designed to obtain incinerator and air pollution control equipment performance data to support facility start-up and operation. A key component of this technical support program includes the Offgas Components Test Facility (OCTF), a pilot-scale offgas system test bed. The primary goal for this test facility is to demonstrate and evaluate the performance of the planned CIF Air Pollution Control System (APCS). To accomplish this task, the OCTF has been equipped with a 1/10 scale CIF offgas system equipment components and instrumentation. In addition, the OCTF design maximizes the flexibility of APCS operation and facility instrumentation and sampling capabilities permit accurate characterization of all process streams throughout the facility. This allows APCS equipment performance to be evaluated in an integrated system under a wide range of possible operating conditions. This paper summarizes the use of this DOE test facility to successfully demonstrate APCS operability and maintainability, evaluate and optimize equipment and instrument performance, and provide direct CIF start-up support. These types of facilities are needed to permit resolution of technical issues associated with design and operation of systems that treat and dispose combustible hazardous, mixed, and low-level radioactive waste throughout and DOE complex

  12. Implementation of tuberculosis infection control in health facilities in Mukono and Wakiso districts, Uganda.

    Science.gov (United States)

    Buregyeya, Esther; Nuwaha, Fred; Verver, Suzanne; Criel, Bart; Colebunders, Robert; Wanyenze, Rhoda; Kalyango, Joan N; Katamba, Achilles; Mitchell, Ellen Mh

    2013-08-01

    Tuberculosis infection control (TBIC) is rarely implemented in the health facilities in resource limited settings. Understanding the reasons for low level of implementation is critical. The study aim was to assess TBIC practices and barriers to implementation in two districts in Uganda. We conducted a cross-sectional study in 51 health facilities in districts of Mukono and Wakiso. The study included: a facility survey, observations of practices and eight focus group discussions with health workers. Quantitative: Only 16 facilities (31%) had a TBIC plan. Five facilities (10%) were screening patients for cough. Two facilities (4%) reported providing masks to patients with cough. Ventilation in the waiting areas was inadequate for TBIC in 43% (22/51) of the facilities. No facility possessed N95 particulate respirators. Qualitative: Barriers that hamper implementation of TBIC elicited included: under-staffing, lack of space for patient separation, lack of funds to purchase masks, and health workers not appreciating the importance of TBIC. TBIC measures were not implemented in health facilities in the two Ugandan districts where the survey was done. Health system factors like lack of staff, space and funds are barriers to implement TBIC. Effective implementation of TBIC measures occurs when the fundamental health system building blocks--governance and stewardship, financing, infrastructure, procurement and supply chain management are in place and functioning appropriately.

  13. Control of the radiation environment and the worker in high-energy facilities

    International Nuclear Information System (INIS)

    Stevenson, G.R.

    1993-01-01

    The philosophy behind the prediction, measurement, monitoring and limitation by access control of the radiation hazard in high-energy accelerator facilities is compared with that which could be employed for controlling similar hazards due to cosmic radiation in civil aircraft flights. Special mention is made of computer simulations of the radiation environment as a means of predicting necessary control measures, of the reliability and integration of radiation measuring devices into control procedures and of the relevance of different access control procedures. (author)

  14. Design/Installation and Structural Integrity Assessment of Bethel Valley Low-Level Waste collection and transfer system upgrade for Building 3092 (central off-gas scrubber facility) at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1994-10-01

    This document describes and assesses planned modifications to be made to the Building 3092 Central Off-Gas Scrubber Facility of the Oak Ridge National Laboratory, Oak Ridge, Tennessee. The modifications are made in response to the requirements of 40CFR264 Subpart J, relating to environmental protection requirements for buried tank systems. The modifications include the provision of a new scrubber recirculation tank in a new, below ground, lined concrete vault, replacing an existing recirculation sump that does not provide double containment. A new buried, double contained pipeline is provided to permit discharge of spent scrubber recirculation fluid to the Central Waste Collection Header. The new vault, tank, and discharge line are provided with leak detection and provisions to remove accumulated liquid. Ne scrubber recirculation pumps, piping, and accessories are also provided. This assessment concludes that the planned modifications comply with applicable requirements of 40CFR264 Subpart J, as set forth in Appendix F to the Federal Facility Agreement, Docket No. 89-04-FF, covering the Oak Ridge Reservation. A formal design certification statement is included herein on Page 53, a certification covering the installation shall be executed prior to placing the modified facility into service

  15. Seismic evaluation of nuclear installations

    International Nuclear Information System (INIS)

    Mattar Neto, Miguel

    1997-01-01

    Some considerations regarding extreme external events, natural or man-induce, such as earthquakes, floods, air crashes, etc, shall be done for nuclear facilities to minimizing the potential impact of the installation on the public and the environment. In this paper the main aspects of the seismic evaluation of nuclear facilities (except the nuclear power reactors) will be presented based on different codes and standards. (author). 7 refs., 2 tabs

  16. Irradiation facilities in JRR-3M

    International Nuclear Information System (INIS)

    Ohtomo, Akitoshi; Sigemoto, Masamitsu; Takahashi, Hidetake

    1992-01-01

    Irradiation facilities have been installed in the upgraded JRR-3 (JRR-3M) in Japan Atomic Energy Research Institute (JAERI). There are hydraulic rabbit facilities (HR), pneumatic rabbit facilities (PN), neutron activation analysis facility (PN3), uniform irradiation facility (SI), rotating irradiation facility and capsule irradiation facilities to carry out the neutron irradiation in the JRR-3M. These facilities are operated using a process control computer system to centerize the process information. Some of the characteristics for the facilities were satisfactorily measured at the same time of reactor performance test in 1990. During reactor operation, some of the tests are continued to confirm the basic characteristics on facilities, for example, PN3 was confirmed to have enough performance for activation analysis. Measurement of neutron flux at all irradiation positions has been carried out for the equilibrium core. (author)

  17. NPP capital equipment life control facilities and tools

    International Nuclear Information System (INIS)

    Nekrasov, A.V.; Proskuryakov, K.N.

    2009-01-01

    Algorithms and simulation package for calculation of eigen modes of coolant pressure oscillations in equipment of primary coolant circuit of WWER-1000 NPP, tuned-circuit Q-factor of an oscillating contour of the coolant, fluctuation frequencies pass band and attenuation factors of were developed. Calculation results for cases of presence and absence of gaseous state radiolysis products in the coolant were obtained. Results analysis makes it possible to disclose operating conditions which result in raised vibrations, and to develop control response in NPP industrial control system for their prevention [ru

  18. Practical methods for exposure control/management at nuclear facilities

    International Nuclear Information System (INIS)

    Twiggs, J.A.

    1991-01-01

    Exposure management/reduction is very important to Duke Power Company. Practical exposure control/reduction techniques applied to their reactor vessel head disassembly outage activity have consistently reduced personnel exposure for this task. The following exposure control methods have worked for use and will be the industry's direction for the 1990's. A summary of these methods includes: (a) move the responsibility of exposure management from the Radiation Protection group to the Maintenance group; (b) reduce area source term by removal of source; (c) improve working environments in radiation areas by minimizing protective clothing usage; and (d) maximize the use of electronic instruments to allow remote monitoring

  19. Computer control and data acquisition system for the R.F. Test Facility

    International Nuclear Information System (INIS)

    Stewart, K.A.; Burris, R.D.; Mankin, J.B.; Thompson, D.H.

    1986-01-01

    The Radio Frequency Test Facility (RFTF) at Oak Ridge National Laboratory, used to test and evaluate high-power ion cyclotron resonance heating (ICRH) systems and components, is monitored and controlled by a multicomponent computer system. This data acquisition and control system consists of three major hardware elements: (1) an Allen-Bradley PLC-3 programmable controller; (2) a VAX 11/780 computer; and (3) a CAMAC serial highway interface. Operating in LOCAL as well as REMOTE mode, the programmable logic controller (PLC) performs all the control functions of the test facility. The VAX computer acts as the operator's interface to the test facility by providing color mimic panel displays and allowing input via a trackball device. The VAX also provides archiving of trend data acquired by the PLC. Communications between the PLC and the VAX are via the CAMAC serial highway. Details of the hardware, software, and the operation of the system are presented in this paper

  20. Manual instructivo de instalación y control de prótesis totales Instructive manual of installation and control of total prostheses

    Directory of Open Access Journals (Sweden)

    Marcia Hortensia Corona Carpio

    2007-12-01

    Full Text Available Se realizó un estudio de la literatura con el objetivo de describir el paso clínico de instalación y control de prótesis total, durante el período comprendido de enero a mayo del 2005 en la Clínica Estomatológica Provincial Docente de Santiago de Cuba. Se abordaron diversos aspectos, definición de conceptos, así como todo el proceder clínico, instrucciones al paciente y consejo s a los portadores de prótesis. Se enfatizó en el paciente geriátrico, destacándose que precisamente este paso es el indicado para eliminar los defectos evidentes y donde el paciente adquiere el hábito de utilizarlos y el organismo de aceptarlo.A literature study was conducted aimed at describing the clinical step of installation and control of total prosthesis at the Provincial Teaching Dental Clinic of Santiago de Cuba from January to May, 2005. Diverse aspects were dealt with, as well as the definition of concepts, the whole clinical procedure, instructions to the patients and advises to prosthesis wearers. Emphasis was made on the geriatric patient, and it was stressed that this step is the indicated to eliminate the evident defects, and where the patient acquires the habit to use them and the body to accept them.

  1. Environmental Control for Regional Library Facilities. RR-80-3.

    Science.gov (United States)

    King, Richard G., Jr.

    This report presents an overview of the damage to library materials caused by uncontrollable environmental variables. The control of atmospheric pollutants, temperature, and humidity are discussed with regard to damage, standards, and the costs of deterioration due to these factors. Twelve references are listed. (FM)

  2. Economic Assessment of Flood Control Facilities under Climate Uncertainty: A Case of Nakdong River, South Korea

    Directory of Open Access Journals (Sweden)

    Kyeongseok Kim

    2018-01-01

    Full Text Available Climate change contributes to enhanced flood damage that has been increasing for the last several decades. Understanding climate uncertainties improves adaptation strategies used for investment in flood control facilities. This paper proposes an investment decision framework for one flood zone to cope with future severe climate impacts. This framework can help policy-makers investigate the cost of future damage and conduct an economic assessment using real options under future climate change scenarios. The proposed methodology provides local municipalities with an adaptation strategy for flood control facilities in a flood zone. Using the proposed framework, the flood prevention facilities in the Nakdong River Basin of South Korea was selected as a case study site to analyze the economic assessment of the investments for flood control facilities. Using representative concentration pathway (RCP climate scenarios, the cost of future flood damage to 23 local municipalities was calculated, and investment strategies for adaptation were analyzed. The project option value was determined by executing an option to invest in an expansion that would adapt to floods under climate change. The results of the case study showed that the proposed flood facilities are economically feasible under both scenarios used. The framework is anticipated to present guidance for establishing investment strategies for flood control facilities of a flood zone in multiple municipalities’ settings.

  3. FY 1990 report on the results of the development of the entrained bed coal gasification power plant. Part 3. Fabrication/installation of pilot plant (Fabrication/installation drawings and fabrication/installation pictures - 2/2); 1990 nendo seika hokokusho. Funryusho sekitan gaska hatsuden plant kaihatsu - Sono 3. Pilot plant seisaku suetsuke hen (Seisaku suetsukezu oyobi seisaku suetsuke shashin) (2/2)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-03-01

    For the purpose of establishing the technology of the integrated coal gasification combined cycle power generation, the fabrication, installation work, etc. were conducted of a 200t/d entrained bed coal gasification pilot plant, and fabrication/installation drawings and fabrication/installation pictures were summarized. In fabrication/installation drawings, drawings of the following were included: actual-pressure/actual-size combustor test equipment (structural drawing of exhaust temperature reducing device, structural drawing of hot air device, system diagram of piping, etc.), safety environmental equipment (total system diagram, layout of electric room equipment, layout of control equipment room, etc.), total control system (structural drawing of the total control system, front view of auxiliary panel of safety environment equipment, etc.), 66kV/6.9kV indoor switching station facilities (layout of equipment of indoor switching station facilities, outline drawing of the main transformer, outline drawing of gas circuit breaker, etc.), common facilities (total layout, diagram of the nitrogen gas pipe system, system diagram of utility equipment, etc.) In pictures of fabrication/installation, pictures of the following were included: state of the construction work, gasifier equipment, gas refining facilities, gas turbine facilities, actual-pressure/actual-size combustor test equipment, safety environmental equipment, total control system, 66kV/6.9kV indoor switching station facilities, common facilities. (NEDO)

  4. 7. international congress on sports facilities and bath installation with international trade exhibition. 7. Internationaler Kongress Sportstaettenbau und Baederanlagen mit internationaler Ausstellung

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    This congress report is divided into 4 allied topics: the first one mainly deals with practicable provision of facilities for handicapped people in Germany, Switzerland, Sweden and Great Britain. The second and third topic deals with practicable design of public buildings like sports areas and sports halls in 7 countries including one example of solar assisted heating in a sports hall in Japan. The last topic treats design and restoration of outdoor and indoor swimming pools under the aspect of energy conservation (mainly achieved by solar systems for water heating and heat recovery) and used comfort in the Federal Republic of Germany, in Austria and France. Furthermore attention is given to biological and hygienical aspects of natural swimming pools and to E.E.C. regulations.

  5. Target Diagnostic Control System Implementation for the National Ignition Facility

    International Nuclear Information System (INIS)

    Shelton, R.T.; Kamperschroer, J.H.; Lagin, L.J.; Nelson, J.R.; O'Brien, D.W.

    2010-01-01

    The extreme physics of targets shocked by NIF's 192-beam laser are observed by a diverse suite of diagnostics. Many diagnostics are being developed by collaborators at other sites, but ad hoc controls could lead to unreliable and costly operations. A Diagnostic Control System (DCS) framework for both hardware and software facilitates development and eases integration. Each complex diagnostic typically uses an ensemble of electronic instruments attached to sensors, digitizers, cameras, and other devices. In the DCS architecture each instrument is interfaced to a low-cost Windows XP processor and Java application. Each instrument is aggregated with others as needed in the supervisory system to form an integrated diagnostic. The Java framework provides data management, control services and operator GUI generation. DCS instruments are reusable by replication with reconfiguration for specific diagnostics in XML. Advantages include minimal application code, easy testing, and high reliability. Collaborators save costs by assembling diagnostics with existing DCS instruments. This talk discusses target diagnostic instrumentation used on NIF and presents the DCS architecture and framework.

  6. Structural integrity of heavy liquid-metal target installed in spallation neutron facility. Part 4: Consideration by fracture mechanics of target container window

    International Nuclear Information System (INIS)

    Ishikura, Syuichi; Kogawa, Hiroyuki; Futakawa, Masatoshi; Kikuchi, Kenji; Haga, Katsuhiro; Kaminaga, Masanori; Hino, Ryutaro

    2004-01-01

    Developments of the neutron scattering facility is carried out under the high-intensity proton accelerator project promoted by JAERI and KEK. To estimate the structural integrity of the heavy liquid-metal (mercury) target used as a spallation neutron source in a MW-class neutron scattering facility, static and dynamic stress (including pressure wave in mercury) behaviors due to the incident of 1MW-pulsed proton beam (Maximum heat density is 461W/cc) were analyzed. In the analyses, two type target containers with semi-cylindrical type and flat-type beam windows were used as analytical models. As a result, it is confirmed that the stress generated by the pressure wave becomes the largest at the center of the beam window, and the flat-type beam window is more advantageous from the structural viewpoint than the semi-cylindrical type beam window. It has been understood that the stress generated in the beam window by the pressure wave can be treated as the secondary stress. Then, it has been understood that the stress and the stress range generated in the target window were bellow the allowable stress level defined by the standard of JIS on the maximum stress and fatigue strength. It has been experimentally confirmed that a cavitation was generated by generating the negative pressure in mercury near the target beam window and a collapse of cavitation damaged to the target container material, as pits. Then, the fracture mechanical analyses were carried out on the pit and a crack on pit tip. Consequently, it was clarified that the crack would not propagate because the inner surface of the beam window was become the compressive stress field due to the steady state thermal stress. Moreover, the evaluation technique of the cavitation which would be needed in the future was summarized. (author)

  7. Installation of a Synchrotron Radiation Beamline Facility at the J. Bennett Johnston Sr. Center for Advanced Microstructures and Devices for the Science and Engineering Alliance. Phase I and II. Final Report

    International Nuclear Information System (INIS)

    Gooden, R.

    2000-01-01

    The Johnston Center presents a unique opportunity for scientists and engineers at southern institutions to initiate and carry out original research using synchrotron radiation ranging from visible light to hard x-rays. The Science and Engineering Alliance proposes to carry out a comprehensive new synchrotron radiation research initiative at CAMD in carefully phased steps of increasing risks. (1) materials research on existing CAMD beam lines and end stations; (2) design, construction and installation of end stations on existing CAMD beam lines, and research with this new instrumentation; (3) design, construction and operation of dedicated synchrotron radiation beam lines that covers the full spectral range of the CAMD storage ring and expanded research in the new facility

  8. Dome load control and crane land path evaluation for Tank 241-SY-101 during hydrogen mitigation pump removal and installation

    Energy Technology Data Exchange (ETDEWEB)

    Weis, M.P.; Lawler, D.M.

    1994-08-01

    This report revisits and consolidates two analyses previously performed for the installation of the Hydrogen Mitigation Pump (HMT) pump. The first report determines, as a function of the crane-imposed dome load, the point to which the crane can encroach into the exclusion zone without exceeding the 50-ton limit. The second performs a load evaluation for the crane and the components in the load path (crane lift accessories and pump). In doing so, it determines the weakest component in the load path and the effect of this component on the allowable encroachment distance. Furthermore, the second report sets operational limits on the allowable load decrease (unload) during installation in the event the pump sticks in the riser. The analysis presented here expands on the latter subject by setting an operational limit on the amount of allowable load increase (overload) during pump removal in the event the pump sticks in the riser.

  9. Ministerial Decree of 30 March 1978 on the exclusion of nuclear installations from the application of the requirements on combustion control

    International Nuclear Information System (INIS)

    1978-01-01

    This Decree was made by the Italian Minister for Industry, Commerce and Crafts; it lays down that nuclear installations governed by Act No. 1860 of 31 December 1962 on the Peaceful Uses of Nuclear Energy and by Presidential Decree No. 185 of 13 February 1964 on Radiation Protection and excluded from the scope of are Royal Order No. 824 of 12 May 1927 on combustion control. (NEA) [fr

  10. Time presses for the installation of a central controller [in the energy supply industry]. Strategic re-orientation of the present system

    International Nuclear Information System (INIS)

    Van den Berg, R.J.; Van Essen, M.; Meulmeester, P.; Olde Rikkert, B.

    2007-01-01

    The installation of a so-called central controller for the electric power industry has a number of advantages for stakeholders in the energy market: improving the exchange of information between energy utilities, save costs by setting up central registers for connections, meters, measured data and central processes for e.g. reconciliation and management of measured data (in particular with regard to smart metering). As an example attention is paid to the NEMMCO-case (National Electricity Code Administrator) in Australia [nl

  11. Expertise concerning the request by the ZWILAG Intermediate Storage Wuerenlingen AG for delivery of the operation licence for the conditioning installation as well as for the burning and melting installation of the central intermediate storage facility for radioactive wastes in Wuerenlingen; Gutachten zum Gesuch der ZWILAG Zwischenlager Wuerenlingen AG um Erteilung der Betriebsbewilligung fuer die Konditionierungsanlage sowie fuer die Verbrennungs- und Schmelzanlage des Zentralen Zwischenlagers fuer radioaktive Abfaelle in Wuerenlingen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-08-15

    On December 15, 1997, the Central Intermediate Storage Facility for radioactive materials (ZWILAG) delivered a request to the Swiss Federal Council for an operational licence for the conditioning installation and the incineration and melting installation at the Central Intermediate Storage Facility (ZZL). For the whole project, the general licence was granted on June 23, 1993. The construction of the whole installation as well as the operation in the storage halls with reception, hot cell and transhipment station were licensed on August 12, 1999. The Federal Agency for the Safety of Nuclear Installations (HSK) examined the request documentation of ZWILAG from the point of view of nuclear safety and radiation protection. The results of the examination are contained in this report. In general, the examination leads to a positive decision. During the realisation process many project adaptations have brought improvements to the installation as far as radiation protection and the treatment of wastes are concerned. HSK requests from a former licensing process were taken into account by ZWILAG. The present examination contains many remarks and requests that the HSK considers necessary. The most important remarks are issued as special references as far as they do not appear as proposals in the licence obligations. In general, the reference form was chosen when the fulfilment of the request can be guarantied by HSK within the framework of a release process. Several references inform ZWILAG of problems for which HSK wishes to receive the results of extended inquiries or where HSK will assist in testing or demonstrations. Other references concern requests for plant documentation. Further, calculations of radioactive material release during normal operation is considered as being necessary. Based on its examination, HSK concludes that the conditions are fulfilled for the safe operation of the conditioning installation and of the incineration and melting installation as long as

  12. Invasive Species Guidebook for Department of Defense Installations in the Delaware River Basin: Identification, Control, and Restoration

    Science.gov (United States)

    2009-06-01

    affects (NISC 2001). A key management objective on both national and installation levels must be prevention of invasive species introduction and...species (National Research Council 2002): ◘ Long flowering/ fruiting period, which increases seed production and dispersal. ◘ Ability to reach...mycorrhizal fungi that they rely on. NOTE: Garlic mustard may grow with native species that are similar in appearance, such as toothworts (Dentaria

  13. How to implement security controls for an information security program at CBRN facilities

    International Nuclear Information System (INIS)

    Lenaeus, Joseph D.; O'Neil, Lori Ross; Leitch, Rosalyn M.; Glantz, Clifford S.; Landine, Guy P.; Bryant, Janet L.; Lewis, John; Mathers, Gemma; Rodger, Robert; Johnson, Christopher

    2015-01-01

    This document was prepared by PNNL within the framework of Project 19 of the European Union Chemical Biological Radiological and Nuclear Risk Mitigation Centres of Excellence Initiative entitled, ''Development of procedures and guidelines to create and improve secure information management systems and data exchange mechanisms for CBRN materials under regulatory control.'' It provides management and workers at CBRN facilities, parent organization managers responsible for those facilities, and regulatory agencies (governmental and nongovernmental) with guidance on the best practices for protecting information security. The security mitigation approaches presented in this document were chosen because they present generally accepted guidance in an easy-to-understand manner, making it easier for facility personnel to grasp key concepts and envision how security controls could be implemented by the facility. This guidance is presented from a risk management perspective.

  14. How to implement security controls for an information security program at CBRN facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lenaeus, Joseph D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); O' Neil, Lori Ross [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Leitch, Rosalyn M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Glantz, Clifford S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Landine, Guy P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bryant, Janet L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lewis, John [National Nuclear Lab., Workington (United Kingdom); Mathers, Gemma [National Nuclear Lab., Workington (United Kingdom); Rodger, Robert [National Nuclear Lab., Workington (United Kingdom); Johnson, Christopher [National Nuclear Lab., Workington (United Kingdom)

    2015-12-01

    This document was prepared by PNNL within the framework of Project 19 of the European Union Chemical Biological Radiological and Nuclear Risk Mitigation Centres of Excellence Initiative entitled, ''Development of procedures and guidelines to create and improve secure information management systems and data exchange mechanisms for CBRN materials under regulatory control.'' It provides management and workers at CBRN facilities, parent organization managers responsible for those facilities, and regulatory agencies (governmental and nongovernmental) with guidance on the best practices for protecting information security. The security mitigation approaches presented in this document were chosen because they present generally accepted guidance in an easy-to-understand manner, making it easier for facility personnel to grasp key concepts and envision how security controls could be implemented by the facility. This guidance is presented from a risk management perspective.

  15. The safety of nuclear installations

    International Nuclear Information System (INIS)

    1993-01-01

    This Safety Fundamental publication sets out basic objectives, concepts and principles for ensuring safety that can be used both by the IAEA in its international assistance operations and by Member States in their national nuclear programmes. These Safety Fundamentals apply primarily to those nuclear installations in which the stored energy developed in certain situations could potentially results in the release of radioactive material from its designated location with the consequent risk of radiation exposure of people. These principles are applicable to a broad range of nuclear installations, but their detailed application will depend on the particular technology and the risks posed by it. In addition to nuclear power plants, such installations may include: research reactors and facilities, fuel enrichment, manufacturing and reprocessing plants; and certain facilities for radioactive waste treatment and storage

  16. Mathematical modelling and quality indices optimization of automatic control systems of reactor facility

    International Nuclear Information System (INIS)

    Severin, V.P.

    2007-01-01

    The mathematical modeling of automatic control systems of reactor facility WWER-1000 with various regulator types is considered. The linear and nonlinear models of neutron power control systems of nuclear reactor WWER-1000 with various group numbers of delayed neutrons are designed. The results of optimization of direct quality indexes of neutron power control systems of nuclear reactor WWER-1000 are designed. The identification and optimization of level control systems with various regulator types of steam generator are executed

  17. Characteristics of pressure control system on PWR/PHWR in pile loop facility

    International Nuclear Information System (INIS)

    Sarwani; Hendro, P.; Suwoto; Sutrisno

    1998-01-01

    PWR/PHWR in-pile loop facility is used for testing of fuel element bundle which is correspond to the condition of power reactor operation. So, this facility is designed at 150 bar of pressure and 350 o C of temperature. Pressure control system is one of the components of the facility and it is equipped with 6 electrical heaters (30 KW), water spray, pressure and temperature monitors. The characterization test of pressure control system has been carried out with operating of 2 electrical heaters (10 KW). The K eff calculation value is different 5.2% from pressure in the pressure control system can be increased to 160 bar within 27 hours. After the system pressure reached the nominal pressure, the pressure control system was in the steady state condition

  18. Air pollution control systems and technologies for waste-to-energy facilities

    International Nuclear Information System (INIS)

    Getz, N.P.; Amos, C.K. Jr.; Siebert, P.C.

    1991-01-01

    One of the primary topics of concern to those planning, developing, and operating waste-to-energy (W-T-E) [also known as municipal waste combustors (MWCs)] facilities is air emissions. This paper presents a description of the state-of-the-art air pollution control (APC) systems and technology for particulate, heavy metals, organics, and acid gases control for W-T-E facilities. Items covered include regulations, guidelines, and control techniques as applied in the W-T-E industry. Available APC technologies are viewed in detail on the basis of their potential removal efficiencies, design considerations, operations, and maintenance costs

  19. A control system of a mini survey facility for photometric monitoring

    Science.gov (United States)

    Tsutsui, Hironori; Yanagisawa, Kenshi; Izumiura, Hideyuki; Shimizu, Yasuhiro; Hanaue, Takumi; Ita, Yoshifusa; Ichikawa, Takashi; Komiyama, Takahiro

    2016-08-01

    We have built a control system for a mini survey facility dedicated to photometric monitoring of nearby bright (Kdome and a small (30-mm aperture) wide-field (5 × 5 sq. deg. field of view) infrared (1.0-2.5 microns) camera on an equatorial fork mount, as well as power sources and other associated equipment. All the components other than the camera are controlled by microcomputerbased I/O boards that were developed in-house and are in many of the open-use instruments in our observatory. We present the specifications and configuration of the facility hardware, as well as the structure of its control software.

  20. INVESTIGATION OF QUANTIFICATION OF FLOOD CONTROL AND WATER UTILIZATION EFFECT OF RAINFALL INFILTRATION FACILITY BY USING WATER BALANCE ANALYSIS MODEL

    OpenAIRE

    文, 勇起; BUN, Yuki

    2013-01-01

    In recent years, many flood damage and drought attributed to urbanization has occurred. At present infiltration facility is suggested for the solution of these problems. Based on this background, the purpose of this study is investigation of quantification of flood control and water utilization effect of rainfall infiltration facility by using water balance analysis model. Key Words : flood control, water utilization , rainfall infiltration facility

  1. Strategies to control odours in livestock facilities: a critical review

    Directory of Open Access Journals (Sweden)

    Y. Ubeda

    2013-11-01

    Full Text Available Odours generated in livestock buildings constitute one of the most relevant air quality issues of intensive livestock production. Reducing nuisance episodes related to odour exposure is therefore essential for a sustainable livestock production. In this study, the state-of-the-art on odour mitigation techniques in livestock housing is critically reviewed. Scientific advances in the last decade are revised and research needs are also identified. The complex nature of livestock odours is firstly reviewed and examined. Then, the most relevant odour control strategies are analyzed in terms of present knowledge and future needs. The strategies considered are: nutritional strategies, manure additives, building design, air filtration, manure covers, manure treatment systems and windbreaks. Finally, future research needs and priorities when establishing mitigation techniques are identified. Despite important recent advances, there are still some challenges for scientists, producers and regulators, particularly related to field evaluation of odours. Therefore, to control livestock odours effectively, using standardized field assessment techniques will be required. Also, investigating measurement and model errors may be useful to better understand the limitations of the current methods, as well as to identify research priorities.

  2. 32 CFR 245.17 - U.S. civil and military air traffic control facilities.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 2 2010-07-01 2010-07-01 false U.S. civil and military air traffic control facilities. 245.17 Section 245.17 National Defense Department of Defense (Continued) OFFICE OF THE SECRETARY OF DEFENSE (CONTINUED) MISCELLANEOUS PLAN FOR THE EMERGENCY SECURITY CONTROL OF AIR TRAFFIC (ESCAT) Procedures for Implementation of ESCAT §...

  3. Control system of test and research facilities for nuclear energy industry

    International Nuclear Information System (INIS)

    1983-01-01

    IHI manufactures several kinds of test and research facilities used for research and development of new type power reactor and solidification system of high level radioactive liquid waste and safety research of light water reactor. These facilities are usually new type plants themselves, so that their control systems have to be designed individually for each plant with the basic conception. They have many operation modes because of their purposes of research and development, so the operation has to be automatized and requires the complicated sequence control system. In addition to these requirements, the detail design is hardly fixed on schedule and often modified during the initial start up period. Therefore, the computer control system was applied to these facilities with CRT display for man-machine communication earlier than to commercial power plants, because in the computer system the control logic is not hard wired but soft programmed and can be easily modified. In this paper, two typical computer control systems, one for PWR reflood test facility and another for mock-up test facility for solidification of liquid waste, are introduced. (author)

  4. Sound field control for a low-frequency test facility

    DEFF Research Database (Denmark)

    Pedersen, Christian Sejer; Møller, Henrik

    2013-01-01

    The two largest problems in controlling the reproduction of low-frequency sound for psychoacoustic experiments is the effect of the room due to standing waves and the relatively large sound pressure levels needed. Anechoic rooms are limited downward in frequency and distortion may be a problem even...... at moderate levels, while pressure-field playback can give higher sound pressures but is limited upwards in frequency. A new solution that addresses both problems has been implemented in the laboratory of Acoustics, Aalborg University. The solution uses one wall with 20 loudspeakers to generate a plane wave...... that is actively absorbed when it reaches the 20 loudspeakers on the opposing wall. This gives a homogeneous sound field in the majority of the room with a flat frequency response in the frequency range 2-300 Hz. The lowest frequencies are limited to sound pressure levels in the order of 95 dB. If larger levels...

  5. Occupational control of the uranium mine industrial facility in Brazil

    International Nuclear Information System (INIS)

    Neto, C.A.; Figueiredo, N.; Py, J.; Azevedo, D. de; Torrico, J.M.

    1996-01-01

    This Occupational Radiation Protection Plan is applied to uranium ore mining and milling, for uranium concentrate production in form of ammonium diuranate (DUA), in 'Complexo Minero-industrial do Planalto de Pocos de Caldas' - CIPC, in 'Caldas', sited in the southwest of Minas Gerais State. The aims of this program are: to estimate the exposure doses of workers by applying dose calculation models; to control the workplace conditions based on monitoring results, variation studies, and to minimize the radiological risks, with available radiation protection resources optimization. The utilized techniques are: talks, area and individual monitoring, individual protection clothes and equipment, use and application of proper conducts in the workplace, according to the radiation protection norms. (authors)

  6. Modeling, simulation and control for a cryogenic fluid management facility, preliminary report

    Science.gov (United States)

    Turner, Max A.; Vanbuskirk, P. D.

    1986-01-01

    The synthesis of a control system for a cryogenic fluid management facility was studied. The severe demand for reliability as well as instrumentation and control unique to the Space Station environment are prime considerations. Realizing that the effective control system depends heavily on quantitative description of the facility dynamics, a methodology for process identification and parameter estimation is postulated. A block diagram of the associated control system is also produced. Finally, an on-line adaptive control strategy is developed utilizing optimization of the velocity form control parameters (proportional gains, integration and derivative time constants) in appropriate difference equations for direct digital control. Of special concern are the communications, software and hardware supporting interaction between the ground and orbital systems. It is visualized that specialist in the OSI/ISO utilizing the Ada programming language will influence further development, testing and validation of the simplistic models presented here for adaptation to the actual flight environment.

  7. Theme day: corrosion and surface treatments in nuclear facilities. Proceedings; Journee Thematique: Corrosion et Traitements de surface dans les Installations Nucleaires. Recueil des presentations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    This document brings together the available presentations given at the theme day organized by the Bourgogne Nuclear Pole on the topic of corrosion and surface treatments in nuclear facilities. Eleven presentations (slides) are compiled in this document: 1 - Introduction - PNB centre of competitiveness and R and D activities (A. Mantovan, PNB); 2 - Corrosion damage (M. Foucault, Areva NP - Centre Technique Le Creusot); 3 - Corrosion mechanisms (R. Oltra, UB-ICB); 4 - Examples of expertise management (C. Duret-Thual, Institut de la corrosion/Corrosion Institute); 5 - General framework of surface treatments (C. Nouveau, ENSAM Cluny Paris Tech); 6 - Surfaces et interfaces characterisation - Part A (C. Langlade, Y. Gachon, UTBM and HEF); 7 - Surfaces et interfaces characterisation - Part B (C. Langlade, Y. Gachon, UTBM and HEF); 8 - Ion beam surface treatment (Y. Le Guellec, Quertech Ingenierie); 9 - Impact surface treatment (G. Saout, Sonats); 10 - Metal oxides Characterisation by US laser (R. Oltra, UB-ICB); 11 - Detection and Characterisation of intergranular corrosion (Y. Kernin, Stephane Bourgois, Areva Intercontrole)

  8. Spallation Neutron Source Accelerator Facility Target Safety and Non-safety Control Systems

    International Nuclear Information System (INIS)

    Battle, Ronald E.; DeVan, B.; Munro, John K. Jr.

    2006-01-01

    The Spallation Neutron Source (SNS) is a proton accelerator facility that generates neutrons for scientific researchers by spallation of neutrons from a mercury target. The SNS became operational on April 28, 2006, with first beam on target at approximately 200 W. The SNS accelerator, target, and conventional facilities controls are integrated by standardized hardware and software throughout the facility and were designed and fabricated to SNS conventions to ensure compatibility of systems with Experimental Physics Integrated Control System (EPICS). ControlLogix Programmable Logic Controllers (PLCs) interface to instruments and actuators, and EPICS performs the high-level integration of the PLCs such that all operator control can be accomplished from the Central Control room using EPICS graphical screens that pass process variables to and from the PLCs. Three active safety systems were designed to industry standards ISA S84.01 and IEEE 603 to meet the desired reliability for these safety systems. The safety systems protect facility workers and the environment from mercury vapor, mercury radiation, and proton beam radiation. The facility operators operated many of the systems prior to beam on target and developed the operating procedures. The safety and non-safety control systems were tested extensively prior to beam on target. This testing was crucial to identify wiring and software errors and failed components, the result of which was few problems during operation with beam on target. The SNS has continued beam on target since April to increase beam power, check out the scientific instruments, and continue testing the operation of facility subsystems

  9. Regulation for installation and operation of marine reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The regulation is defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the provisions of the order for execution of the law. The regulation is applied to marine reactors and reactors installed in foreign nuclear ships. Basic concepts and terms are explained, such as: radioactive waste; fuel assembly; exposure dose; accumulative dose; controlled area; safeguarded area; inspected surrounding area and employee. The application for permission of installation of reactors shall list maximum continuous thermal power, location and general structure of reactor facilities, structure and equipment of reactors and treatment and storage facilities of nuclear fuel materials, etc. The application for permission of reactors installed in foreign ships shall describe specified matters according to the provisions for domestic reactors. The operation program of reactors for three years shall be filed to the Minister of Transportation for each reactor every fiscal year from that year when the operation is expected to start. Records shall be made for each reactor and kept for particular periods on inspection of reactor facilities, operation, fuel assembly, control of radiation, maintenance and others. Exposure doses, inspection and check up of reactor facilities, operation of reactors, transport and storage of nuclear fuel materials, etc. are designated in detail. (Okada, K.)

  10. Installation of a radioactive waste disposal facility. The necessity of building up durable links between the general public and radioactive waste. Feedback from experience in France

    International Nuclear Information System (INIS)

    Comte, Annabelle; Farin, Sebastien

    2015-01-01

    2013 has been a banner year for Andra with widespread discussions on the question of long-term management of radioactive waste: a nationwide public discussion about the planned Cigeo deep disposal facility has been organized and national discussions on the energy source transition had inevitably brought up the question of what to do with future radioactive waste to be produced under the various scenarios put forward. In spite of an open institutional framework, with numerous legal provisions for citizen participation, 2013 showed that creation of a radioactive waste disposal facility is not, and cannot be, a question dealt with like breaking news, within a given temporal or spatial perimeter. Any attempts to bring up the subject under the spotlight of public scrutiny inevitably shift the discussions away from their central theme and abandon the underlying question - what should be done with the existing radioactive waste and the waste that is bound to be produced? - to move on to the other major question: ''Should we stop using nuclear power or not?'', which takes us away from our responsibilities towards future generations. Daring to face the question, anchor it in citizen discussions, and create awareness of our duties towards coming generations: this is the challenge that Andra had already set itself several years ago. Our position is a strong one; rather than seeking to mask the problem of radioactive waste, we must face up to our responsibilities: the waste is already there, and we have to do something with it. It will take time to be successful here. Long-term management of radioactive waste is clearly a really long-term matter. All the experience in the field has shown that it involves patience and careful listening, and requires building up a basis for solid trust among the potential neighboring population, who are the most directly concerned. Durable proximity human investment is one of the key factors of success. For over 20 years now

  11. Installation of a radioactive waste disposal facility. The necessity of building up durable links between the general public and radioactive waste. Feedback from experience in France

    Energy Technology Data Exchange (ETDEWEB)

    Comte, Annabelle; Farin, Sebastien [Andra, Chatenay-Malabry (France)

    2015-07-01

    2013 has been a banner year for Andra with widespread discussions on the question of long-term management of radioactive waste: a nationwide public discussion about the planned Cigeo deep disposal facility has been organized and national discussions on the energy source transition had inevitably brought up the question of what to do with future radioactive waste to be produced under the various scenarios put forward. In spite of an open institutional framework, with numerous legal provisions for citizen participation, 2013 showed that creation of a radioactive waste disposal facility is not, and cannot be, a question dealt with like breaking news, within a given temporal or spatial perimeter. Any attempts to bring up the subject under the spotlight of public scrutiny inevitably shift the discussions away from their central theme and abandon the underlying question - what should be done with the existing radioactive waste and the waste that is bound to be produced? - to move on to the other major question: ''Should we stop using nuclear power or not?'', which takes us away from our responsibilities towards future generations. Daring to face the question, anchor it in citizen discussions, and create awareness of our duties towards coming generations: this is the challenge that Andra had already set itself several years ago. Our position is a strong one; rather than seeking to mask the problem of radioactive waste, we must face up to our responsibilities: the waste is already there, and we have to do something with it. It will take time to be successful here. Long-term management of radioactive waste is clearly a really long-term matter. All the experience in the field has shown that it involves patience and careful listening, and requires building up a basis for solid trust among the potential neighboring population, who are the most directly concerned. Durable proximity human investment is one of the key factors of success. For over 20 years now

  12. Low-level wastewater treatment facility process control operational test report

    International Nuclear Information System (INIS)

    Bergquist, G.G.

    1996-01-01

    This test report documents the results obtained while conducting operational testing of a new TK 102 level controller and total outflow integrator added to the NHCON software that controls the Low-Level Wastewater Treatment Facility (LLWTF). The test was performed with WHC-SD-CP-OTP 154, PFP Low-Level Wastewater Treatment Facility Process Control Operational Test. A complete test copy is included in appendix A. The new TK 102 level controller provides a signal, hereafter referred to its cascade mode, to the treatment train flow controller which enables the water treatment process to run for long periods without continuous operator monitoring. The test successfully demonstrated the functionality of the new controller under standard and abnormal conditions expected from the LLWTF operation. In addition, a flow totalizer is now displayed on the LLWTF outlet MICON screen which tallies the process output in gallons. This feature substantially improves the ability to retrieve daily process volumes for maintaining accurate material balances

  13. Development of the irradiation facility SIBO INRA/Tangier, Morocco by upgrading cobalt-60 in a temporary pool and enhancing safety and control features

    Directory of Open Access Journals (Sweden)

    Mohammed Mouhib

    2017-12-01

    Full Text Available An automatic control system is one of the most important parts of an irradiation facility. The level of this control is always maintained to comply with safety procedures during routine work in this field. Also sometimes it is limited to the minimum level of regulation required due to economical aspects; some commercial systems are generally made by manufacturers of industrial facilities and considered affordable by irradiators. In some cases specific irradiation facilities tailor their control systems to their needs. For this kind of irradiator the control system can be developed and upgraded according to personal and industrial experiences. These upgrading procedures are also used by others to develop their systems. The objective of this paper is to share a local experience in upgrading security, safety systems and the use of cobalt-60 for the irradiator. It is a composite experiment at SIBO INRA/Tangier, Morocco and concerns the: (i upgrade of cobalt-60 in a temporary pool in the SIBO irradiator in Tangier. This operation was conducted in collaboration with the International Atomic Energy Agency (IAEA and was a success story of 2014 according to the general conference of IAEA; (ii safety and technical upgrade of the system in the SIBO irradiator made in collaboration with IAEA; (iii installation and upgrade of the security system in accordance with the Global Threat Reduction Programme (GTRP to reduce the threat of a Radiological Dispersal Device (RDD in collaboration with The United States Department of Energy’s National Nuclear Security Administration (NNSA.

  14. Tools and methods for implementing the control systems on the Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    Minor, E.G.; Labiak, W.G.

    1981-01-01

    Installation of the major hardware subsystems for MFTF is nearing completion. These subsystems include the Fusion Chamber System, the eighty KV Neutral Beam System, the Superconducting Magnet System, and the Personnel Safety System. The Local Controls group has undertaken a uniform aproach to implementing the control systems for all of these hardware subsystems. This approach has two major aspects: (1) to provide a stand-alone computer control system with a remote, portable terminal so that computer control can be provided at the site of the hardware for initial testing, (2) to provide hardware simulators so that the complicated MFTF computer control system can be tested independent of the hardware. The software and hardware tools which were developed to carry out this plan will be described. Our experiences with bringing up subsystems containing up to 900 separate channels of control and status will also be described

  15. Wind-driven roof turbines: a novel way to improve ventilation for TB infection control in health facilities.

    Science.gov (United States)

    Cox, Helen; Escombe, Rod; McDermid, Cheryl; Mtshemla, Yolanda; Spelman, Tim; Azevedo, Virginia; London, Leslie

    2012-01-01

    Tuberculosis transmission in healthcare facilities contributes significantly to the TB epidemic, particularly in high HIV settings. Although improving ventilation may reduce transmission, there is a lack of evidence to support low-cost practical interventions. We assessed the efficacy of wind-driven roof turbines to achieve recommended ventilation rates, compared to current recommended practices for natural ventilation (opening windows), in primary care clinic rooms in Khayelitsha, South Africa. Room ventilation was assessed (CO₂ gas tracer technique) in 4 rooms where roof turbines and air-intake grates were installed, across three scenarios: turbine, grate and window closed, only window open, and only turbine and grate open, with concurrent wind speed measurement. 332 measurements were conducted over 24 months. For all 4 rooms combined, median air changes per hour (ACH) increased with wind speed quartiles across all scenarios. Higher median ACH were recorded with open roof turbines and grates, compared to open windows across all wind speed quartiles. Ventilation with open turbine and grate exceeded WHO-recommended levels (60 Litres/second/patient) for 95% or more of measurements in 3 of the 4 rooms; 47% in the remaining room, where wind speeds were lower and a smaller diameter turbine was installed. High room ventilation rates, meeting recommended thresholds, may be achieved using wind-driven roof turbines and grates, even at low wind speeds. Roof turbines and air-intake grates are not easily closed by staff, allowing continued ventilation through colder periods. This simple, low-cost technology represents an important addition to our tools for TB infection control.

  16. Wind-driven roof turbines: a novel way to improve ventilation for TB infection control in health facilities.

    Directory of Open Access Journals (Sweden)

    Helen Cox

    Full Text Available OBJECTIVE: Tuberculosis transmission in healthcare facilities contributes significantly to the TB epidemic, particularly in high HIV settings. Although improving ventilation may reduce transmission, there is a lack of evidence to support low-cost practical interventions. We assessed the efficacy of wind-driven roof turbines to achieve recommended ventilation rates, compared to current recommended practices for natural ventilation (opening windows, in primary care clinic rooms in Khayelitsha, South Africa. METHODS: Room ventilation was assessed (CO₂ gas tracer technique in 4 rooms where roof turbines and air-intake grates were installed, across three scenarios: turbine, grate and window closed, only window open, and only turbine and grate open, with concurrent wind speed measurement. 332 measurements were conducted over 24 months. FINDINGS: For all 4 rooms combined, median air changes per hour (ACH increased with wind speed quartiles across all scenarios. Higher median ACH were recorded with open roof turbines and grates, compared to open windows across all wind speed quartiles. Ventilation with open turbine and grate exceeded WHO-recommended levels (60 Litres/second/patient for 95% or more of measurements in 3 of the 4 rooms; 47% in the remaining room, where wind speeds were lower and a smaller diameter turbine was installed. CONCLUSION: High room ventilation rates, meeting recommended thresholds, may be achieved using wind-driven roof turbines and grates, even at low wind speeds. Roof turbines and air-intake grates are not easily closed by staff, allowing continued ventilation through colder periods. This simple, low-cost technology represents an important addition to our tools for TB infection control.

  17. Hierarchical tree-structured control network for the Antares laser facility

    Energy Technology Data Exchange (ETDEWEB)

    McGirt, F.

    1979-01-01

    The design and implementation of a distributed, computer-based control system for the Antares 100-kJ gas laser fusion facility is presented. Control system requirements and their operational interrelationships that consider both integrated system control and individual subsystem control are described. Several configurations of minicomputers are established to provide direct control of sets of microcomputers and to provide points of operator-laser interaction. Over 100 microcomputers are located very close to the laser device control points or sources of data and perform the real-time functions of the control system, such as data and control signal multiplexing, stepping motor control, and vacuum and gas system control. These microcomputers are designed to be supported as an integral part of the control network and to be software compatible with the larger minicomputers.

  18. Hierarchical tree-structured control network for the Antares laser facility

    International Nuclear Information System (INIS)

    McGirt, F.

    1979-01-01

    The design and implementation of a distributed, computer-based control system for the Antares 100-kJ gas laser fusion facility is presented. Control system requirements and their operational interrelationships that consider both integrated system control and individual subsystem control are described. Several configurations of minicomputers are established to provide direct control of sets of microcomputers and to provide points of operator-laser interaction. Over 100 microcomputers are located very close to the laser device control points or sources of data and perform the real-time functions of the control system, such as data and control signal multiplexing, stepping motor control, and vacuum and gas system control. These microcomputers are designed to be supported as an integral part of the control network and to be software compatible with the larger minicomputers

  19. Preliminary design for hot dirty-gas control-valve test facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    This report presents the results of a preliminary design and cost estimating effort for a facility for the testing of control valves in Hot Dirty Gas (HDGCV) service. This design was performed by Mittelhauser Corporation for the United States Department of Energy's Morgantown Energy Technology Center (METC). The objective of this effort was to provide METC with a feasible preliminary design for a test facility which could be used to evaluate valve designs under simulated service conditions and provide a technology data base for DOE and industry. In addition to the actual preliminary design of the test facility, final design/construction/operating schedules and a facility cost estimate were prepared to provide METC sufficient information with which to evaluate this design. The bases, assumptions, and limitations of this study effort are given. The tasks carried out were as follows: METC Facility Review, Environmental Control Study, Gas Generation Study, Metallurgy Review, Safety Review, Facility Process Design, Facility Conceptual Layout, Instrumentation Design, Cost Estimates, and Schedules. The report provides information regarding the methods of approach used in the various tasks involved in the completion of this study. Section 5.0 of this report presents the results of the study effort. The results obtained from the above-defined tasks are described briefly. The turnkey cost of the test facility is estimated to be $9,774,700 in fourth quarter 1979 dollars, and the annual operating cost is estimated to be $960,000 plus utilities costs which are not included because unit costs per utility were not available from METC.

  20. Report of questionnaire result concerning the radiation control in medicare facilities

    International Nuclear Information System (INIS)

    Nakamura, Yutaka

    2009-01-01

    Radiation control in Japanese medicare facilities is regulated generally by multiple laws of radiation and the Committee has investigated their actual radiation control practice through questionnaire, of which result and its analysis are described here. The questionnaire on web (Committee's homepage) was conducted in the period Apr., 13-May, 1, 2009, by asking to medical radiology personnel (MRP) with 20 items, mainly about personnel working for radiation medicare (RM), monitoring of their external dose, notice of exposure dose to individual person, archiving of the dose record, and questions about the Law Concerning Prevention from Radiation Hazard due to Radioisotopes, Etc.; was answered by 378 facilities where 15,281 persons in total worked for RM (41/facility in average); and the facilities were under regulation by 1 (Medical, 39%) and 2 (Medical and for Prevention, 61%) laws. Major findings were: 71% of facilities had no clear rule to select MRP; 98% trusted dosimetry outside; in 76%, personnel participating in RM had pocket dosimeter as well; 70% investigated the exposure history at personnel employment; to personnel whose dose could exceed or exceeded 20 mSv/y, 45% transferred the person to other work site, 34% issued warning and 21% had no such personnel; 73% felt the necessity of qualified expert for radiation control; 81% conducted education and training to MRP; 54% used radiation-generating equipments, 27%, unsealed radioisotopes and 19%, sealed ones; and 77% felt the radiation control should be unified in the Medical Law. Based on the findings, the Committee discussed and commented about definition and selection of MRP, dosimetry and its record of MRP having multiple, increasing works, uncertainty of the exact number of MRP in Japan, and desirable unification of radiation control practice in the medicare facility into the Medical Law if amended in future. (K.T.)

  1. Development of operation control expert system for off-site facilities

    Energy Technology Data Exchange (ETDEWEB)

    Takeuchi, Masaaki

    1988-09-01

    Concerning off-site facilities of oil refinary, changes of facilities and equipment are frequently made in order to cope flexibly with the market trends and changes of the social environment. In addition, it is desirable to introduce computerization into control and manipulation of off-site facilities for its fast, safe and sure operation. In order to achieve the above, against the existing exclusively control-oriented system, it is necessary to add the processing and generating functions to combinations between valves to be shut and piping as well as equipment to be used along the whole extent of the oil flow in the system and to add the function which makes verification of the above functions easy through a dialogue between users and the system. In order to realize the above, Cosmo Oil and Yokokawa Denki developed jointly an operation control expert system for off-site facilities and the system started its actual operation from October 1986. This article is an outline of the system. The result of its actual operation for one and a half years since its inception showed that the system was operated only by the staff responsible for the operation of the facilities, the workload was reduced to 1/3-1/4 of the workload before the adoption of the system and absolutely no omission of work nor mistake was experienced. (2 figs)

  2. Control of Listeria species food safety at a poultry food production facility.

    Science.gov (United States)

    Fox, Edward M; Wall, Patrick G; Fanning, Séamus

    2015-10-01

    Surveillance and control of food-borne human pathogens, such as Listeria monocytogenes, is a critical aspect of modern food safety programs at food production facilities. This study evaluated contamination patterns of Listeria species at a poultry food production facility, and evaluated the efficacy of procedures to control the contamination and transfer of the bacteria throughout the plant. The presence of Listeria species was studied along the production chain, including raw ingredients, food-contact, non-food-contact surfaces, and finished product. All isolates were sub-typed by pulsed-field gel electrophoresis (PFGE) to identify possible entry points for Listeria species into the production chain, as well as identifying possible transfer routes through the facility. The efficacy of selected in-house sanitizers against a sub-set of the isolates was evaluated. Of the 77 different PFGE-types identified, 10 were found among two or more of the five categories/areas (ingredients, food preparation, cooking and packing, bulk packing, and product), indicating potential transfer routes at the facility. One of the six sanitizers used was identified as unsuitable for control of Listeria species. Combining PFGE data, together with information on isolate location and timeframe, facilitated identification of a persistent Listeria species contamination that had colonized the facility, along with others that were transient. Copyright © 2015 Elsevier Ltd. All rights reserved.

  3. CHALLENGES IN SETTING UP QUALITY CONTROL IN DIAGNOSTIC RADIOLOGY FACILITIES IN NIGERIA.

    Science.gov (United States)

    Inyang, S O; Egbe, N O; Ekpo, E

    2015-01-01

    The Nigerian Nuclear Regulatory Authority (NNRA) was established to regulate and control the use of radioactive and radiation emitting sources in Nigeria. Quality control (QC) on diagnostic radiology equipment form part of the fundamental requirements for the authorization of diagnostic radiology facilities in the Country. Some quality control tests (output, exposure linearity and reproducibility) were measured on the x-ray machines in the facilities that took part in the study. Questionnaire was developed to evaluate the frequencies at which QC tests were conducted in the facilities and the challenges in setting up QC. Results show great variation in the values of the QC parameters measured. Inadequate cooperation by facilities management, lack of QC equipment and insufficient staff form the major challenges in setting up QC in the facilities under study. The responses on the frequencies at which QC tests should be conducted did not correspond to the recommended standards; indicating that personnel were not familiar with QC implementation and may require further training on QC.

  4. Data Acquisition System On Beta Installation

    International Nuclear Information System (INIS)

    Abtokhi, Ahmad; Nurhanan; Sudarno; Sumarno, Edy

    2000-01-01

    Data acquisition system is needed on every installation. This is important used to monitoring and processing data to get information desired. This system applied to β installation which is facility to carry out experiments on accident condition like as reflooding phenomena in test section. The 16 exp.th channel data acquisition system is drived by ADC 0804 and programme application DELPHI

  5. Design of a control system for HIRFL-CSRe internal target facility in Lanzhou

    International Nuclear Information System (INIS)

    Wang Yanyu; Liu Wufeng; Shao Caojie; Lin Feiyu; Zhang Jianchuan; Xiao Wenjun

    2010-01-01

    It is described in this paper the design of the control system for HIRFL-CSRe internal target facility, in which there are many different kinds of units need to be monitored and controlled. The control system is composed of several subsystems which are designed to control the gas-jet temperature, chamber vacuum, valves and molecular pumps. A human-computer interaction interface is also realized to do the data acquisition, data processing and display. The whole system has been working stably and safely, it fully meets the requirements of physical experiments in the internal target facility. In January of 2010, the first physics experiment of the radioactive electron capture was finished successfully with the aids of this control system. (authors)

  6. An instrumentation and control philosophy for high-level nuclear waste processing facilities

    International Nuclear Information System (INIS)

    Weigle, D.H.

    1990-01-01

    The purpose of this paper is to present an instrumentation and control philosophy which may be applied to high-level nuclear waste processing facilities. This philosophy describes the recommended criteria for automatic/manual control, remote/local control, remote/local display, diagnostic instrumentation, interlocks, alarm levels, and redundancy. Due to the hazardous nature of the process constituents of a high-level nuclear waste processing facility, it is imperative that safety and control features required for accident-free operation and maintenance be incorporated. A well-instrumented and controlled process, while initially more expensive in capital and design costs, is generally safer and less expensive to operate. When the long term cost savings of a well designed process is coupled with the high savings enjoyed by accident avoidance, the benefits far outweigh the initial capital and design costs

  7. Investigating the Influence of Various Stormwater Runoff Control Facilities on Runoff Control Efficiency in a Small Catchment Area

    Directory of Open Access Journals (Sweden)

    Rei Itsukushima

    2018-02-01

    Full Text Available Urbanization causes an increase in the flood discharge because of the infiltration capacity. Furthermore, extreme precipitation events have been an increasing concern for many regions worldwide. This study aimed to investigate the influence of different outflow control facilities on runoff reduction in a small watershed. We focused on the soil-improvement technology and rainwater tanks as outflow control facilities and conducted a runoff calculation using a rainfall event of a magnitude that is likely to occur once in a hundred years. The calculation showed that the soil-improvement technology reduced runoff during long-term continuous rainfall, whereas in a concentrated short-term rainfall event, a significant difference in the runoff reduction effect between rainfall tanks of various volumes was observed. Since effective countermeasures for runoff reduction differ depending on the rainfall distribution pattern, we suggested both facilities for storing initial rainfall and initiating countermeasures for penetration improvement over the long term.

  8. A study on surveillance equipment at the exit/entry control point of nuclear facility

    International Nuclear Information System (INIS)

    Park, C. S.; Kim, D. Y.; Cha, H. L.; Kim, H. D.; Hong, J. S.

    1999-01-01

    Exit/Entry control is an essential measure at both entrances of the protected area and vital area of nuclear facility at which physical protection is required under the relevant laws and regulations. Especially, when there are heavy traffics of personnel and process equipment in those areas, automated surveillance devices have to be introduced to timely and efficiently screen out internal and external adversaries from achieving their goals of stealing of nuclear material and/or sabotage of the facility. The major portion of this study involves with integration and processing of signals from radiation detector, metal detector, and image monitor. This integrated device together with positive personal identification device which will be reinforced in near future would contribute to the establishment of total exit/entry control point of nuclear facility

  9. Environmental Assessment - Construct a Ground-to-Air Transmitter and Receiver (GATR) Facility at Grand Forks Air Force Base

    National Research Council Canada - National Science Library

    2006-01-01

    ...) facility on Grand Forks Air Force Base (AFB), North Dakota. The Communication Squadron is preparing to install new GATR communication antennas and systems, for tactical aircraft control and commercial air traffic control...

  10. Study on a conceptual design of a data acquisition and instrument control system for experimental suites at materials and life science facility (MLF) of J-PARC

    International Nuclear Information System (INIS)

    Nakajima, Kenji; Nakatani, Takeshi; Torii, Shuki; Higemoto, Wataru; Otomo, Toshiya

    2006-02-01

    The JAEA (Japan Atomic Energy Agency)-KEK (High Energy Accelerator Research Organization) joint project, Japan Proton Accelerator Research Complex (J-PARC), is now under construction. Materials and Life Science Facility (MLF) is one of planned facilities in this research complex. The neutron and muon sources will be installed at MLF and world's highest class intensive beam, which is utilized for variety of scientific research subject, will be delivered. To discuss the necessary computing environments for neutron and muon instruments at J-PARC, the MLF computing environment group (MLF-CEG) has been organized. We, members of the DAQ subgroup (DAQ-SG) are responsible for considering data acquisition and instrument control systems for the experimental suites at MLF. In the framework of the MLF-CEG, we are surveying the computer resources which is required for data acquisition and instrument control at future instruments, current situation of existing facilities and possible solutions those we can achieve. We are discussing the most suitable system that can bring out full performance of our instruments. This is the first interim report of the DAQ-SG, in which our activity of 2003-2004 is summarized. In this report, a conceptual design of the software, the related a data acquisition and instrument control system for experimental instruments at MLF are proposed. (author)

  11. $36 Million Command and Control Facility at Camp Leatherneck, Afghanistan: Unwanted, Unneeded, and Unused

    Science.gov (United States)

    2015-05-01

    Memorandum of Major Danisha L. Morris , JA, Chief, Contract and Fiscal Law (June 29, 2010). SIGAR-15-57-SP Report: $36 Million Command and Control...Facility at Camp Leatherneck, Afghanistan Page 60 EXHIBIT 10 -----Original Message----- From: Mills LtGen Richard P Sent: Tuesday , February 11

  12. Acoustics in Research Facilities--Control of Wanted and Unwanted Sound. Laboratory Design Notes.

    Science.gov (United States)

    Newman, Robert B.

    Common and special acoustics problems are discussed in relation to the design and construction of research facilities. Following a brief examination of design criteria for the control of wanted and unwanted sound, the technology for achieving desired results is discussed. Emphasis is given to various design procedures and materials for the control…

  13. Use of pupal parasitoids as biological control agents of filth flies on equine facilities

    Science.gov (United States)

    House flies, Musca domestica L., and stable flies, Stomoxys calcitrans (L.), (Diptera: Muscidae), are common pests on horse farms. The use of pupal parasitoids as biological control agents for filth flies is becoming more popular on equine facilities; however, there is a lack of information on the e...

  14. Safeguards material control and accounting at licensed processing facilities. Quarterly report, July--September 1977

    International Nuclear Information System (INIS)

    Sacks, I.J.

    1978-12-01

    Objective was to develop the methodology and software needed for assessing Material Control and Accounting (MC and A) systems at fixed site nuclear fuel facilities. The assessment of an MC and A system requires five steps: target identification, event set generation, MC and A response determination, component performance models, and thermo-physical property data base. Progress on each is reported

  15. Communication grounding facility

    International Nuclear Information System (INIS)

    Lee, Gye Seong

    1998-06-01

    It is about communication grounding facility, which is made up twelve chapters. It includes general grounding with purpose, materials thermal insulating material, construction of grounding, super strength grounding method, grounding facility with grounding way and building of insulating, switched grounding with No. 1A and LCR, grounding facility of transmission line, wireless facility grounding, grounding facility in wireless base station, grounding of power facility, grounding low-tenton interior power wire, communication facility of railroad, install of arrester in apartment and house, install of arrester on introduction and earth conductivity and measurement with introduction and grounding resistance.

  16. Supervisory control and diagnostics system for the mirror fusion test facility: overview and status 1980

    International Nuclear Information System (INIS)

    McGoldrick, P.R.

    1981-01-01

    The Mirror Fusion Test Facility (MFTF) is a complex facility requiring a highly-computerized Supervisory Control and Diagnostics System (SCDS) to monitor and provide control over ten subsystems; three of which require true process control. SCDS will provide physicists with a method of studying machine and plasma behavior by acquiring and processing up to four megabytes of plasma diagnostic information every five minutes. A high degree of availability and throughput is provided by a distributed computer system (nine 32-bit minicomputers on shared memory). Data, distributed across SCDS, is managed by a high-bandwidth Distributed Database Management System. The MFTF operators' control room consoles use color television monitors with touch sensitive screens; this is a totally new approach. The method of handling deviations to normal machine operation and how the operator should be notified and assisted in the resolution of problems has been studied and a system designed

  17. Fiscal 1999 technical survey report. Green Helmet Project (China, Steel industry - Coal moisture control facilities); 1999 nendo green helmet jigyo (Chugoku seitetsugyo) sekitan choshitsu setsubi chosa hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    For the purpose of meeting the needs of Chinese steelmaking corporations disclosed at an energy conservation diagnosing session of a Japan-China steelmaking energy conservation seminar held in July 1999, Japanese specialists were sent to Chinese steelmaking plants, namely, Benxi Iron and Steel (Group) Complex, Wuhan Iron and Steel (Group) Company, and Nanjing Iron and Steel Works. They described the CMC (coal moisture control) technique for its popularization and for effectively utilizing the same for coke ovens. Also, feasibility studies were conducted for CMC installation at the respective plants. Engineers were invited from the Chinese plants to Japan for the observation of associated facilities and for the exchange of opinions. As the result, leading members of the Chinese steelmaking plants now learned the usefulness of CMC. In the feasibility studies, CMC installation led to a reduction in dry distillation energy, that is, a reduction in the amount of fuel gas required, to an improvement on coke production, and to the selection of the fluidized bed dryer as the optimum system. At Chungching Iron and Steel Works, the existing CMC facilities were not in continuous operation because of an inclined conveyer failure, yet there was a strong will to utilize the CMC technique. (NEDO)

  18. Regulation for installation and operation of experimental-research reactor

    International Nuclear Information System (INIS)

    1979-01-01

    The ordinance is stipulated under the Law for regulation of nuclear raw materials, nuclear fuel materials and reactors and the provisions for installation and operation of reactor in the order for execution of the law. Basic concepts and terms are defined, such as, radioactive waste; fuel assembly; exposure dose; accumulative dose; controlled area; preserved area; inspected surrounding area and employee. An application for permission of installation of reactor shall list such matters as: the maximum continuous thermal output of reactor; location and general construction of reactor facilities; construction and equipment of the main reactor and other facilities for nuclear fuel materials; cooling and controlling system and radioactive waste, etc. An operation plan of reactor for three years shall be filed till January 31 of the fiscal year preceding that one the operation begins. Records shall be made and kept for specified periods respectively on inspection of reactor facilities, operation, fuel assembly, radiation control, maintenance, accidents of reactor equipment and weather. Detailed rules are settled for entrance limitation to controlled area, exposure dose, inspection, check up and regular independent examination of reactor facilities, operation of reactor, transportation of substances contaminated by nuclear fuel materials within the works and storage, etc. (Okada, K.)

  19. Dose control during decommissioning stage 1.2 of decommissioning SGHWR facility

    Energy Technology Data Exchange (ETDEWEB)

    Rodgers, M.J. [AEA Technology (United Kingdom)

    1995-12-31

    Dose control during decommissioning stage 1.2 of the SGHWR facility, i.e preparation for an extended period of care and maintenance, is discussed. The method of control of dose uptake is described and also the systems of dose uptake review, the use of dose restraint objections and other tools for limitation of dose uptake. Dose uptake data are presented for periods of maintenance shutdowns. Finally the option of chemical clearing of the circuit following shutdown is considered. (UK).

  20. The linac control system for the large-scale synchrotron radiation facility (SPring-8)

    Energy Technology Data Exchange (ETDEWEB)

    Sakaki, Hironao; Yoshikawa, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Itoh, Yuichi [Atomic Energy General Services Corporation, Tokai, Ibaraki (Japan); Terashima, Yasushi [Information Technology System Co., Ltd. (ITECS), Tokyo (Japan)

    2000-09-01

    The linac for large-scale synchrotron radiation facilities has been operated since August of 1996. The linac deal with the user requests without any big troubles. In this report, the control system development policy, details, and the operation for the linac are presented. It is also described so that these experiences can be used for control system of a large scale proton accelerators which will be developed in the High Intensity Proton Accelerator Project. (author)

  1. The data acquisition and control system for Thomson Scattering on ATF [Advanced Toroidal Facility

    International Nuclear Information System (INIS)

    Stewart, K.A.; Kindsfather, R.R.; Rasmussen, D.A.

    1989-01-01

    The 2-dimensional Thomson Scattering System measuring electron temperatures and densities in the Advanced Toroidal Facility (ATF) is interfaced to a VAX-8700 computer system running in a clustered configuration. Calibration, alignment, and operation of this diagnostic is under computer control. Extensive CAMAC instrumentation is used for timing control, data acquisition, and laser alignment. This paper will discuss the computer hardware and software, system operations, and data storage and retrieval. 3 refs

  2. Automatic beam position control at Los Alamos Spallation Radiation Effects Facility (LASREF)

    International Nuclear Information System (INIS)

    Oothoudt, M.; Pillai, C.; Zumbro, M.

    1997-01-01

    Historically the Los Alamos Spallation Radiation Effects Facility (LASREF) has used manual methods to control the position of the 800 kW, 800 MeV proton beam on targets. New experiments, however, require more stringent position control more frequently than can be done manually for long periods of time. Data from an existing harp is used to automatically adjust steering magnets to maintain beam position to required tolerances

  3. Automation of a cryogenic facility by commercial process-control computer

    International Nuclear Information System (INIS)

    Sondericker, J.H.; Campbell, D.; Zantopp, D.

    1983-01-01

    To insure that Brookhaven's superconducting magnets are reliable and their field quality meets accelerator requirements, each magnet is pre-tested at operating conditions after construction. MAGCOOL, the production magnet test facility, was designed to perform these tests, having the capacity to test ten magnets per five day week. This paper describes the control aspects of MAGCOOL and the advantages afforded the designers by the implementation of a commercial process control computer system

  4. Industrial fans used in nuclear facilities

    International Nuclear Information System (INIS)

    Carlson, J.A.

    1987-01-01

    Industrial fans are widely used in nuclear facilities, and their most common use is in building ventilation. To control the spread of contamination, airflows are maintained at high levels. Therefore, the selection of the fan and fan control are important to the safety of people, equipment and the environment. As a result, 80% of all energy used in nuclear facilities is fan energy. Safety evolves from the durability, control and redundancy in the system. In new or retrofit installations, testing and qualification of fans and systems are completed prior to start-up. Less important but necessary is the energy conservation aspect of fan selection and installations. Fan efficiency, type of control and system installation are evaluated for energy use

  5. Rejuvenation of the controls of the CERN PS/ISOLDE facility using industrial components

    CERN Document Server

    Allard, J.; Locci, F.; Mornacchi, G.

    2001-01-01

    In the context of the general consolidation of the CERN ISOLDE facility, a project has been started to upgrade the ISOLDE control system. We describe the new ISOLDE control system, emphasizing the systematic use of industrial components such as PLCs and field buses, their integration with the existing, VME based, CERN PS control system and their potential applicability to both existing and new controls problems at the CERN PS complex. We also discuss how to extend a PLC-based solution to the case where real-time response is an issue.

  6. Shuttle Flight Operations Contract Generator Maintenance Facility Land Use Control Implementation Plan (LUCIP)

    Science.gov (United States)

    Applegate, Joseph L.

    2014-01-01

    This Land Use Control Implementation Plan (LUCIP) has been prepared to inform current and potential future users of the Kennedy Space Center (KSC) Shuttle Flight Operations Contract Generator Maintenance Facility (SFOC; SWMU 081; "the Site") of institutional controls that have been implemented at the Site1. Although there are no current unacceptable risks to human health or the environment associated with the SFOC, an institutional land use control (LUC) is necessary to prevent human health exposure to antimony-affected groundwater at the Site. Controls will include periodic inspection, condition certification, and agency notification.

  7. The Main Biological Hazards in Animal Biosafety Level 2 Facilities and Strategies for Control.

    Science.gov (United States)

    Li, Xiao Yan; Xue, Kang Ning; Jiang, Jin Sheng; Lu, Xuan Cheng

    2016-04-01

    Concern about the biological hazards involved in microbiological research, especially research involving laboratory animals, has increased in recent years. Working in an animal biosafety level 2 facility (ABSL-2), commonly used for research on infectious diseases, poses various biological hazards. Here, the regulations and standards related to laboratory biosafety in China are introduced, the potential biological hazards present in ABSL-2 facilities are analyzed, and a series of strategies to control the hazards are presented. Copyright © 2016 The Editorial Board of Biomedical and Environmental Sciences. Published by China CDC. All rights reserved.

  8. Future Direction of the Instrumentation and Control System for Security of Nuclear Facilities

    International Nuclear Information System (INIS)

    Kim, Woo Jin; Kim, Jae Kwang

    2014-01-01

    Instrumentation and control systems are pervasively used as a vital component in modern industries. Nuclear facilities, such as nuclear power plants (NPPs), originally use I and C systems for plant status monitoring, processes control, and many other purposes. After some events that raised security concerns, application areas of I and C systems have been expanded to physical protection of nuclear material and facilities. As nuclear policies over the world are strengthening security issues, the future direction of roles and technical requirements of security related I and C systems is described: An introduction of I and C systems, especially digitalized I and C systems, to security of nuclear facilities requires many careful considerations, such as system integration, verification and validation (V/V), etc. Institute of Nuclear Nonproliferation and Control (KINAC) established 'International Nuclear Nonproliferation and Security Academy, INSA' in 2014. One of the main achievements of INSA is test-bed implementation for technical criteria development of nuclear facilities' physical protection systems (PPSs) as well as for education and training of those systems. The test bed was modified and improved more suitably from the previous version to modern PPSs including state-of-the-art I and C technologies. KINAC is confident in the new test bed to become a fundamental technical basis of security related I and C systems in near future

  9. Tuberculosis in Healthcare Workers and Infection Control Measures at Primary Healthcare Facilities in South Africa

    Science.gov (United States)

    Claassens, Mareli M.; van Schalkwyk, Cari; du Toit, Elizabeth; Roest, Eline; Lombard, Carl J.; Enarson, Donald A.; Beyers, Nulda; Borgdorff, Martien W.

    2013-01-01

    Background Challenges exist regarding TB infection control and TB in hospital-based healthcare workers in South Africa. However, few studies report on TB in non-hospital based healthcare workers such as primary or community healthcare workers. Our objectives were to investigate the implementation of TB infection control measures at primary healthcare facilities, the smear positive TB incidence rate amongst primary healthcare workers and the association between TB infection control measures and all types of TB in healthcare workers. Methods One hundred and thirty three primary healthcare facilities were visited in five provinces of South Africa in 2009. At each facility, a TB infection control audit and facility questionnaire were completed. The number of healthcare workers who had had TB during the past three years was obtained. Results The standardised incidence ratio of smear positive TB in primary healthcare workers indicated an incidence rate of more than double that of the general population. In a univariable logistic regression, the infection control audit score was significantly associated with reported cases of TB in healthcare workers (OR=1.04, 95%CI 1.01-1.08, p=0.02) as was the number of staff (OR=3.78, 95%CI 1.77-8.08). In the multivariable analysis, the number of staff remained significantly associated with TB in healthcare workers (OR=3.33, 95%CI 1.37-8.08). Conclusion The high rate of TB in healthcare workers suggests a substantial nosocomial transmission risk, but the infection control audit tool which was used did not perform adequately as a measure of this risk. Infection control measures should be monitored by validated tools developed and tested locally. Different strategies, such as routine surveillance systems, could be used to evaluate the burden of TB in healthcare workers in order to calculate TB incidence, monitor trends and implement interventions to decrease occupational TB. PMID:24098461

  10. Tuberculosis in healthcare workers and infection control measures at primary healthcare facilities in South Africa.

    Science.gov (United States)

    Claassens, Mareli M; van Schalkwyk, Cari; du Toit, Elizabeth; Roest, Eline; Lombard, Carl J; Enarson, Donald A; Beyers, Nulda; Borgdorff, Martien W

    2013-01-01

    Challenges exist regarding TB infection control and TB in hospital-based healthcare workers in South Africa. However, few studies report on TB in non-hospital based healthcare workers such as primary or community healthcare workers. Our objectives were to investigate the implementation of TB infection control measures at primary healthcare facilities, the smear positive TB incidence rate amongst primary healthcare workers and the association between TB infection control measures and all types of TB in healthcare workers. One hundred and thirty three primary healthcare facilities were visited in five provinces of South Africa in 2009. At each facility, a TB infection control audit and facility questionnaire were completed. The number of healthcare workers who had had TB during the past three years was obtained. The standardised incidence ratio of smear positive TB in primary healthcare workers indicated an incidence rate of more than double that of the general population. In a univariable logistic regression, the infection control audit score was significantly associated with reported cases of TB in healthcare workers (OR=1.04, 95%CI 1.01-1.08, p=0.02) as was the number of staff (OR=3.78, 95%CI 1.77-8.08). In the multivariable analysis, the number of staff remained significantly associated with TB in healthcare workers (OR=3.33, 95%CI 1.37-8.08). The high rate of TB in healthcare workers suggests a substantial nosocomial transmission risk, but the infection control audit tool which was used did not perform adequately as a measure of this risk. Infection control measures should be monitored by validated tools developed and tested locally. Different strategies, such as routine surveillance systems, could be used to evaluate the burden of TB in healthcare workers in order to calculate TB incidence, monitor trends and implement interventions to decrease occupational TB.

  11. Remote crane control techniques and closed-circuit television for the U.S. Department of Energy, Defense Waste Processing Facility

    International Nuclear Information System (INIS)

    DaSilva, D.A.

    1988-01-01

    The Defense Waste Processing Facility (DWPF) located at the Savannah River Plant (SRP), South Carolina is a nuclear waste facility being built to vitrify and containerize high level radioactive waste products. DWPF has a unique requirement for an unmanned crane system to install and replace equipment in the high humidity, high radiation and harsh chemical environment of permanently inaccessible processing cells. A radio control system is provided to control a 117 ton capacity bridge crane that is equipped with various power tools for remote handling of crane replaceable and maintained equipment. High resolution black and white closed circuit television (CTV) assemblies mounted on the crane and on the walls of the various processing cells are provided for viewing the equipment during normal operations and maintenance. The main process cell (MPC) crane is designed as the vehicle to be the eyes, ears and hands for remote in-cell operations and maintenance. The crane runs on elevated rails above the process cells. A trailer-like-electrical equipment compartment (EEC) containing control and radio communications equipment for the crane; is dragged along on rails in a heavily shielded corridor by a drag bar mounted to the crane. A two way RF system is the communications link for all control and video signals between the crane and two stationary crane control consoles

  12. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    International Nuclear Information System (INIS)

    Michael Kruzic

    2007-01-01

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D and D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release

  13. Space Station Environmental Control and Life Support System Test Facility at Marshall Space Flight Center

    Science.gov (United States)

    Springer, Darlene

    1989-01-01

    Different aspects of Space Station Environmental Control and Life Support System (ECLSS) testing are currently taking place at Marshall Space Flight Center (MSFC). Unique to this testing is the variety of test areas and the fact that all are located in one building. The north high bay of building 4755, the Core Module Integration Facility (CMIF), contains the following test areas: the Subsystem Test Area, the Comparative Test Area, the Process Material Management System (PMMS), the Core Module Simulator (CMS), the End-use Equipment Facility (EEF), and the Pre-development Operational System Test (POST) Area. This paper addresses the facility that supports these test areas and briefly describes the testing in each area. Future plans for the building and Space Station module configurations will also be discussed.

  14. Studies for improvement of regulatory control on the radioactive effluent released from nuclear facilities

    International Nuclear Information System (INIS)

    Cheong, Jae Hak; Park, H. M.; Song, M. C.; Lee, K. H.; Jang, J. K.; Chun, J. K.; Jeong, K. H.

    2005-05-01

    This report contains the second-year results of the research project titled 'Studies for Improvement of Regulatory Control on the Radioactive Effluent Released from Nuclear Facilities' and mainly provides technical and strategic approaches to improve performance of regulatory control on the gaseous effluent released from domestic nuclear facilities. The main result contained here includes overview and technical bases of radioactive gaseous effluent control (Chapter 1), reconsideration of the sensitivity requirements for measurement of radioactivity in gaseous effluent sample (Chapter 2), uncertainty analysis of the calculated radioactivity in gaseous effluent (Chapter 3), and improvement of quantification method of noble gas releases (Chapter 4). In addition, analysis of the impact due to combined sampling of particulate from multiple release points (Chapter 5), comparison of domestic nuclear reactors gaseous effluent data to foreign PWRs (Chapter 6), standardized sampling technique for collection of gaseous tritium (Chapter 7), and application of Xe-133 equivalent concept to gaseous effluent control (Chapter 8) are also provided. As a whole, this report provides a generic approach to improve the performance of regulatory control on the gaseous effluent. Therefore, actual enforcement of the recommendations should be preceded by establishment of a series of action plans reflecting on the site- and facility-specific design and operational features

  15. Proposal for the award of a contract for the design, supply, installation and commissioning of a Heating, Ventilation and Air-Conditioning (HVAC) system for the computer room of the CERN Control Centre

    CERN Document Server

    2012-01-01

    Proposal for the award of a contract for the design, supply, installation and commissioning of a Heating, Ventilation and Air-Conditioning (HVAC) system for the computer room of the CERN Control Centre

  16. Contributions to the research programs in nuclear and industrial electronics, domestic production of instrumentation, safety and control systems and equipment for nuclear reactors and auxiliary installations

    International Nuclear Information System (INIS)

    Talpariu, C; Talpariu, J.; Matei, C.

    2001-01-01

    Domestic production of component system and equipment for the control and safety of nuclear facilities was one of the priority objective of the Nuclear Research Institute Pitesti. The problems addressed were particularly related to design and production of analog and digital equipment for measurements, triggering and display of the values of process parameters as well as to regulating complex functions of this equipment. Associated to this effort were the research works concerning: - reliability and in-service life-time of the electronic components and equipment in the safety and control systems for nuclear processes; - radiation endurance of industrial electronic components; utilization of whirling currents in calandria tube testing; - expert systems and applications in nuclear reactor control and safety; design and testing methods of process real time software packages for safety in control critical systems for nuclear domain. There are presented characteristics of the following equipment: 1. amplifier for ionization chambers with triggering comparator circuits for the CANDU 600 reactor shut down system; 2. amplifier for ionization chambers without triggering comparator circuits for power regulating system; 3. safety and regulating computerized system for C9 and C5 cans; 4. acquisition system for dosimetric data in nuclear facilities; 5. program able digital comparator for the reactor shut down system; 6. stationary gamma areal monitors for CANDU 600 reactors and other nuclear facilities

  17. Rehyd development and installation report

    International Nuclear Information System (INIS)

    Schuch, R.L.; Woodall, H.N.

    1977-12-01

    Rehyd, a low-impedance, HYDRA-type, water transmission line for bremsstrahlung exposures, was installed on the north side of the REBA facility. Rehyd produces 300 kA beams of 1.2 MeV electrons with a pulse width of 170 ns. Nominal x-ray exposure dose capabilities of 7 cal/g and 20 to 25 kJ were realized thus far. A description is given of the specific design parameters and facility layouts including the unique features of the REBA Marx generator/Rehyd line energy-transfer system. Diode configurations, magnetic-field applications, and output measurements are also presented

  18. SPRT Calibration Uncertainties and Internal Quality Control at a Commercial SPRT Calibration Facility

    Science.gov (United States)

    Wiandt, T. J.

    2008-06-01

    The Hart Scientific Division of the Fluke Corporation operates two accredited standard platinum resistance thermometer (SPRT) calibration facilities, one at the Hart Scientific factory in Utah, USA, and the other at a service facility in Norwich, UK. The US facility is accredited through National Voluntary Laboratory Accreditation Program (NVLAP), and the UK facility is accredited through UKAS. Both provide SPRT calibrations using similar equipment and procedures, and at similar levels of uncertainty. These uncertainties are among the lowest available commercially. To achieve and maintain low uncertainties, it is required that the calibration procedures be thorough and optimized. However, to minimize customer downtime, it is also important that the instruments be calibrated in a timely manner and returned to the customer. Consequently, subjecting the instrument to repeated calibrations or extensive repeated measurements is not a viable approach. Additionally, these laboratories provide SPRT calibration services involving a wide variety of SPRT designs. These designs behave differently, yet predictably, when subjected to calibration measurements. To this end, an evaluation strategy involving both statistical process control and internal consistency measures is utilized to provide confidence in both the instrument calibration and the calibration process. This article describes the calibration facilities, procedure, uncertainty analysis, and internal quality assurance measures employed in the calibration of SPRTs. Data will be reviewed and generalities will be presented. Finally, challenges and considerations for future improvements will be discussed.

  19. Using Former Military Installations as Correctional Facilities

    Science.gov (United States)

    1990-03-01

    institution’s industrial manufacturing areas. Here, former warehouse buildings were converted into manufacturinq aLeas with production lines for steel o,,f...Idaho County, in the Clearwater Mountains approximately 60 miles southeast of Lewiston in the Idaho panhandle. Judicial District: 2nd Judicial

  20. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumntation, and measurement techniques in fuel fabrication facilities, P.O.1236909. Final report

    International Nuclear Information System (INIS)

    Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

    1978-12-01

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. Some of the material included has appeared elswhere and it has been summarized. An extensive bibliography is included. A spcific example of application of the accountability methods to a model fuel fabrication facility which is based on the Westinghouse Anderson design

  1. Material control in nuclear fuel fabrication facilities. Part II. Accountability, instrumntation, and measurement techniques in fuel fabrication facilities, P. O. 1236909. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Borgonovi, G.M.; McCartin, T.J.; McDaniel, T.; Miller, C.L.; Nguyen, T.

    1978-12-01

    This report describes the measurement techniques, the instrumentation, and the procedures used in accountability and control of nuclear materials, as they apply to fuel fabrication facilities. Some of the material included has appeared elswhere and it has been summarized. An extensive bibliography is included. A spcific example of application of the accountability methods to a model fuel fabrication facility which is based on the Westinghouse Anderson design.

  2. Large coil test facility

    International Nuclear Information System (INIS)

    Nelms, L.W.; Thompson, P.B.

    1980-01-01

    Final design of the facility is nearing completion, and 20% of the construction has been accomplished. A large vacuum chamber, houses the test assembly which is coupled to appropriate cryogenic, electrical, instrumentation, diagnostc systems. Adequate assembly/disassembly areas, shop space, test control center, offices, and test support laboratories are located in the same building. Assembly and installation operations are accomplished with an overhead crane. The major subsystems are the vacuum system, the test stand assembly, the cryogenic system, the experimental electric power system, the instrumentation and control system, and the data aquisition system

  3. Concerning modification of plan for installation of reactors (addition of No.4 reactor and modification of No.1, No.2 and No.3 reactor facilities) at Hamaoka nuclear power plant of Chubu Electric Power Co., Ltd. (reply to inquiry)

    International Nuclear Information System (INIS)

    1988-01-01

    The Nuclear Safety Commission on Oct. 22, 1987 directed the Nuclear Reactor Safety Expert Group to carry out a study on it, made deliberations after receiving a report from the Group on Jun. 28, and submitted the findings to the Minister of International Trade and Industry on Jul. 14. The study and deliberations were intended to determine the conformity of the modifications to the applicable laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The investigation on the location covered the site conditions, geology, seismic environment, meteorology, hydrology, and social environment. The investigations on the safety design of the reactor facilities addressed the design of the overall reactor facilities, anti-earthquake design, and design of other equipment including reactor core, fuel equipment, monitors, reactivity controllers, safety protection equipment, and emergency core cooler. Other investigations included exposure evaluation and accident analysis. It was concluded that the modifications would not have adverse effects on the safety of the reactor facilities. (Nogami, K.)

  4. Studies of neutron methods for process control and criticality surveillance of fissile material processing facilities

    International Nuclear Information System (INIS)

    Zoltowski, T.

    1988-01-01

    The development of radiochemical processes for fissile material processing and spent fuel handling need new control procedures enabling an improvement of plant throughput. This is strictly related to the implementation of continuous criticality control policy and developing reliable methods for monitoring the reactivity of radiochemical plant operations in presence of the process perturbations. Neutron methods seem to be applicable for fissile material control in some technological facilities. The measurement of epithermal neutron source multiplication with heuristic evaluation of measured data enables surveillance of anomalous reactivity enhancement leading to unsafe states. 80 refs., 47 figs., 33 tabs. (author)

  5. Advanced Motor Control Test Facility for NASA GRC Flywheel Energy Storage System Technology Development Unit

    Science.gov (United States)

    Kenny, Barbara H.; Kascak, Peter E.; Hofmann, Heath; Mackin, Michael; Santiago, Walter; Jansen, Ralph

    2001-01-01

    This paper describes the flywheel test facility developed at the NASA Glenn Research Center with particular emphasis on the motor drive components and control. A four-pole permanent magnet synchronous machine, suspended on magnetic bearings, is controlled with a field orientation algorithm. A discussion of the estimation of the rotor position and speed from a "once around signal" is given. The elimination of small dc currents by using a concurrent stationary frame current regulator is discussed and demonstrated. Initial experimental results are presented showing the successful operation and control of the unit at speeds up to 20,000 rpm.

  6. Software quality assurance plan for the National Ignition Facility integrated computer control system

    International Nuclear Information System (INIS)

    Woodruff, J.

    1996-11-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This Software Quality Assurance Plan (SQAP) applies to the activities of the Integrated Computer Control System (ICCS) organization and its subcontractors. The Plan describes the activities implemented by the ICCS section to achieve quality in the NIF Project's controls software and implements the NIF Quality Assurance Program Plan (QAPP, NIF-95-499, L-15958-2) and the Department of Energy's (DOE's) Order 5700.6C. This SQAP governs the quality affecting activities associated with developing and deploying all control system software during the life cycle of the NIF Project

  7. Automated personal identification: a new technique for controlling access to nuclear materials and facilities

    International Nuclear Information System (INIS)

    Eccles, D.R.

    1975-01-01

    Special nuclear materials must be protected against the threat of diversion or theft, and nuclear facilities against the threat of industrial sabotage. Implicit in this protection is the means of controlling access to protected areas, material access areas, and vital areas. With the advent of automated personal identification technology, the processes of access control can be automated to yield both higher security and reduced costs. This paper first surveys the conventional methods of access control; next, automated personal identification concepts are presented and various systems approaches are highlighted; finally, Calspan's FINGERSCAN /sub TM/ system for identity verification is described

  8. Engineered and Administrative Safety Systems for the Control of Prompt Radiation Hazards at Accelerator Facilities

    International Nuclear Information System (INIS)

    Liu, James C.; SLAC; Vylet, Vashek; Walker, Lawrence S.

    2007-01-01

    The ANSI N43.1 Standard, currently in revision (ANSI 2007), sets forth the requirements for accelerator facilities to provide adequate protection for the workers, the public and the environment from the hazards of ionizing radiation produced during and from accelerator operations. The Standard also recommends good practices that, when followed, provide a level of radiation protection consistent with those established for the accelerator communities. The N43.1 Standard is suitable for all accelerator facilities (using electron, positron, proton, or ion particle beams) capable of producing radiation, subject to federal or state regulations. The requirements (see word 'shall') and recommended practices (see word 'should') are prescribed in a graded approach that are commensurate with the complexity and hazard levels of the accelerator facility. Chapters 4, 5 and 6 of the N43.1 Standard address specially the Radiation Safety System (RSS), both engineered and administrative systems, to mitigate and control the prompt radiation hazards from accelerator operations. The RSS includes the Access Control System (ACS) and Radiation Control System (RCS). The main requirements and recommendations of the N43.1 Standard regarding the management, technical and operational aspects of the RSS are described and condensed in this report. Clearly some aspects of the RSS policies and practices at different facilities may differ in order to meet the practical needs for field implementation. A previous report (Liu et al. 2001a), which reviews and summarizes the RSS at five North American high-energy accelerator facilities, as well as the RSS references for the 5 labs (Drozdoff 2001; Gallegos 1996; Ipe and Liu 1992; Liu 1999; Liu 2001b; Rokni 1996; TJNAF 1994; Yotam et al. 1991), can be consulted for the actual RSS implementation at various laboratories. A comprehensive report describing the RSS at the Stanford Linear Accelerator Center (SLAC 2006) can also serve as a reference

  9. The WR-1 corrosion test facility

    International Nuclear Information System (INIS)

    Murphy, E.V.; Simmons, G.R.

    1978-07-01

    This report describes a new Corrosion Test Facility which has recently been installed in the WR-1 organic-cooled research reactor. The irradiation facility is a single insert, installed in a reactor site, which can deliver a fast neutron flux density of 2.65 x 10 17 neutrons/(m 2 .s) to specimens under irradiation. A self-contained controlled-chemistry cooling water circuit removes the gamma- and neutron-heat generated in the insert and specimens. Specimen temperatures typically vary from 245 deg C to 280 deg C across the insert core region. (author)

  10. Ministry of ordinance determining the technical standard concerning atomic energy facilities for power generation

    International Nuclear Information System (INIS)

    1985-01-01

    The ministerial ordinance provides for the technical standards for the power generation of nuclear facilities; i.e., electric power facilities generating electricity with nuclear energy for motive power, according to the Electricity Enterprises Act. The contents are as follows: protection against fires, aseismatic design, radiation protective barriers, structural protection for sitings, reactor installation, safety measures, materials and structures, safety valves, pressure resistance tests, reactor core, radiation shields, reactor cooling, emergency core cooling system, facility equipment, alarm system, reactor control system, reactor control room, fuel storage facility, fuel handling facility, ventilation equipment, radioactive contamination prevention, radioactive waste management facility, reactor containment facility, and so on. (Kubozono, M.)

  11. Software solutions manage the definition, operation, maintenance and configuration control of the National Ignition Facility

    International Nuclear Information System (INIS)

    Dobson, Darwin; Churby, Al; Krieger, Ed; Maloy, Donna; White, Kevin

    2012-01-01

    Highlights: ► NIF is a complex experimental facility composed of ∼4 million components. ► We describe business tools to define, build, operate, and maintain all components. ► CAD tools generate virtual models and assemblies under configuration control. ► Items requiring preventive, reactive, and/or calibration maintenance are tracked. ► Radiological or hazardous materials undergo additional controls. - Abstract: The National Ignition Facility (NIF) is the world's largest laser composed of millions of individual parts brought together to form one massive assembly. Maintaining control of the physical definition, status and configuration of this structure is a monumental undertaking yet critical to the validity of experimental data and the safe operation of the facility. A major programmatic challenge is to deploy software solutions to effectively manage the definition, build, operation, and maintenance, and configuration control of all components of NIF. The strategy for meeting this challenge involves deploying and integrating an enterprise application suite of solutions consisting of both Commercial-Off-The-Shelf (COTS) products and custom developed software.This paper describes how this strategy has been implemented along with a discussion on the successes realized and the ongoing challenges associated with this approach.

  12. Design and Validation of Control Room Upgrades Using a Research Simulator Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Vivek Agarwal; Jeffrey C. Joe; Julius J. Persensky

    2012-11-01

    Since 1981, the United States (U.S.) Nuclear Regulatory Commission (NRC) [1] requires a plant- specific simulator facility for use in training at U.S. nuclear power plants (NPPs). These training simulators are in near constant use for training and qualification of licensed NPP operators. In the early 1980s, the Halden Man-Machine Laboratory (HAMMLab) at the Halden Reactor Project (HRP) in Norway first built perhaps the most well known set of research simulators. The HRP offered a high- fidelity simulator facility in which the simulator is functionally linked to a specific plant but in which the human-machine interface (HMI) may differ from that found in the plant. As such, HAMMLab incorporated more advanced digital instrumentation and controls (I&C) than the plant, thereby giving it considerable interface flexibility that researchers took full advantage of when designing and validating different ways to upgrade NPP control rooms. Several U.S. partners—the U.S. NRC, the Electrical Power Research Institute (EPRI), Sandia National Laboratories, and Idaho National Laboratory (INL) – as well as international members of the HRP, have been working with HRP to run control room simulator studies. These studies, which use crews from Scandinavian plants, are used to determine crew behavior in a variety of normal and off-normal plant operations. The findings have ultimately been used to guide safety considerations at plants and to inform advanced HMI design—both for the regulator and in industry. Given the desire to use U.S. crews of licensed operators on a simulator of a U.S. NPP, there is a clear need for a research simulator facility in the U.S. There is no general-purpose reconfigurable research oriented control room simulator facility in the U.S. that can be used for a variety of studies, including the design and validation of control room upgrades.

  13. 41 CFR 102-74.190 - Are portable heaters, fans and other such devices allowed in Government-controlled facilities?

    Science.gov (United States)

    2010-07-01

    ..., fans and other such devices allowed in Government-controlled facilities? 102-74.190 Section 102-74.190... § 102-74.190 Are portable heaters, fans and other such devices allowed in Government-controlled facilities? Federal agencies are prohibited from operating portable heaters, fans, and other such devices in...

  14. Elimination of voltage reversal in multiple membrane electrode assembly installed microbial fuel cells (mMEA-MFCs) stacking system by resistor control.

    Science.gov (United States)

    Kim, Bongkyu; Chang, In Seop

    2018-08-01

    Voltage reversal (VR) in series connection of multiple membrane electrode assembly installed microbial fuel cells (mMEA-MFC) is eliminated by manipulating the resistor control. Discharge test results collected from two mMEA-MFCs initially operated (designated as P1 and P2) confirm that the performance of P2 exceeds that of P1. Thus, driving P1 and P2 as serially stacked MFCs generate the VR in P1. Controlling the inserted resistor adjust the current production of P2 to maintain balance with P1, and the VR in P1 is eliminated in the operation of stacking mode. Thus, manipulating the internal resistance provide an applicable approach to suppress VR in the stacking of mMEA-MFCs system. Copyright © 2018 Elsevier Ltd. All rights reserved.

  15. Installation and working methods of a testing laboratory to establish a private control at the concrete plant (part 1

    Directory of Open Access Journals (Sweden)

    Haarmann, F.

    1973-03-01

    Full Text Available Not availableEl ''Control de Calidad'' puede considerarse tan importante, desde un punto de vista práctico, que unas instalaciones adecuadas para el control, tanto de la producción como de los productos acabados, representan una seguridad en la calidad de los productos y en el rendimiento de la empresa. Con la ayuda de algunos ejemplos, el presente trabajo muestra las posibilidades existentes para mantener la calidad del producto a un elevado nivel, empleando para ello instalaciones de control de calidad, aumentando, además, el rendimiento y reduciendo los costos innecesarios. En la segunda parte de este trabajo se describen ocho centros de control de calidad de grandes y pequeñas dimensiones y de acuerdo con la disposición de la figura 1. Seguidamente se hacen algunas observaciones críticas respecto a la adquisición de instalaciones para realizar un adecuado control. En un apéndice del trabajo se representan esquemáticamente unas instalaciones para el control de áridos, del hormigón fresco y del hormigón endurecido.

  16. Adjustment of automatic control systems of production facilities at coal processing plants using multivariant physico- mathematical models

    Science.gov (United States)

    Evtushenko, V. F.; Myshlyaev, L. P.; Makarov, G. V.; Ivushkin, K. A.; Burkova, E. V.

    2016-10-01

    The structure of multi-variant physical and mathematical models of control system is offered as well as its application for adjustment of automatic control system (ACS) of production facilities on the example of coal processing plant.

  17. Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Vivek Agarwal; Kirk Fitzgerald; Jacques Hugo; Bruce Hallbert

    2013-03-01

    The U.S. Department of Energy’s Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale, using glasstop virtual panels to display the analog control boards found at current plants. The present installation features 15 glasstop panels, uniquely achieving a complete control room representation. The simulator is also full-scope, meaning it uses the same plant models used for training simulators at actual plants. Unlike in the plant training simulators, the deployment on glasstop panels allows a high degree of customization of the panels, allowing the simulator to be used for research on the design of new digital control systems for control room modernization. This report includes separate sections discussing the glasstop panels, their layout to mimic control rooms at actual plants, technical details on creating a multi-plant and multi-vendor reconfigurable simulator, and current efforts to support control room modernization at U.S. utilities. The glasstop simulator provides an ideal testbed for prototyping and validating new control room concepts. Equally importantly, it is helping create a standardized and vetted human factors engineering process that can be used across the nuclear industry to ensure control room upgrades maintain and even improve current reliability and safety.

  18. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    International Nuclear Information System (INIS)

    Michael R. Kruzic

    2007-01-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D and D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D and D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D and D strategy is now being employed on the larger ''sister'' facility, Test Cell C

  19. Waterborne microorganisms and biofilms related to hospital infections: strategies for prevention and control in healthcare facilities.

    Science.gov (United States)

    Capelletti, Raquel Vannucci; Moraes, Ângela Maria

    2016-02-01

    Water is the main stimulus for the development of microorganisms, and its flow has an important role in the spreading of contaminants. In hospitals, the water distribution system requires special attention since it can be a source of pathogens, including those in the form of biofilms often correlated with resistance of microorganisms to various treatments. In this paper, information relevant to cases of nosocomial infections involving water circuits as a source of contaminants is compiled, with emphasis on the importance of microbiological control strategies to prevent the installation, spreading and growth of microorganisms in hospitals. An overview of the worldwide situation is provided, with emphasis on Brazilian hospitals. Different approaches normally used to control the occurrence of nosocomial infections due to waterborne contaminants are analyzed, and the use of the polysaccharide chitosan for this specific application is briefly discussed.

  20. Control and safety systems for TRIGA irradiation facilities C5 and C9

    International Nuclear Information System (INIS)

    Talpalariu Cornel Talpalariu Jeni Crucean Mircea Matei Corina

    2008-01-01

    Full text: The Institute for Nuclear Research conducted research for designing and manufacturing of microprocessor equipment for some irradiation facilities operating by the TRIGA reactor. This equipment has accumulated a wide operating time allowing the conclusions referring to reliability, ergonomics, and design of the operating facilities. Based upon these studies a new program was initiated for the design and manufacturing of a modern equipment with improved reliability and flexibility performances. The system provides the user with a multitude of options, numerical and analog interfaces, keyboard and high reliability local display. The main functional components of the system are: - 8 PID full options regulating loops; - 8 safety analog channels having 4 preset trips; - watch dog restart and fault tolerant facilities; - 8 high precision analog with an input of 0 - 15 mV from thermocouple; - 8 computer controlled power supplies of 220 V, 1 kWA; - alphanumeric display and keyboard; - fault tolerant analog scanner. A real improvement of the system is the future remote control computer, a PC AT Pentium working like a system controller, real time data acquisition, and operator's adviser. This new facility allows the operator to set the trips or to control remotely all the power supply and step-by-step positioner of irradiation device. Software design for acquisition and data processing provides modern techniques for operator interfacing, representation recording and protection of test results. Software implementation keeps a special organization supported by a real time executive that is the best method to achieve the performance required. Following this objective, the software structure consists of: 1. Tasks as follows: - testing parameters setup; - data processing routines; - engineering and electrical conversion; - numerical / graphical data representation; - test results recording routines and data base management. 2. Drivers as follows: - A/I and D

  1. FFTF [Fast Flux Test Facility] performance measurements for safety, productivity and control

    International Nuclear Information System (INIS)

    Newland, D.J.; Praetorius, P.R.; Tomaszewski, T.A.

    1987-05-01

    A useful set of performance measurements for Safety, Productivity and Control has evolved at the Fast Flux Test Facility (FFTF). In response to declining budgets and the resulting need to safely manage a manpower rampdown, an ''Early Warning System'' was developed in 1984. Its purpose was to monitor the effects of the staffing rampdown such that appropriate remedial action could be taken to correct adverse trends before a significant problem occurred. 1 tab

  2. Multiresistant pathogens in geriatric nursing – infection control in residential facilities for geriatric nursing in Germany

    Directory of Open Access Journals (Sweden)

    Peters, Claudia

    2014-09-01

    Full Text Available [english] Background: The increase of multidrug-resistant organisms (MDROs causes problems in geriatric nursing homes. Older people are at increased a growing risk of infection due to multimorbidity and frequent stays in hospital. A high proportion of the elderly require residential care in geriatric nursing facilities, where hygiene requirements in nursing homes are similar to those in hospitals. For this reason we examined how well nursing homes are prepared for MDROs and how effectively protect their infection control residents and staff.Methods: A cross-sectional study was performed on infection control in residential geriatric nursing facilities in Germany 2012. The questionnaire recorded important parameters of hygiene, resident and staff protection and actions in case of existing MDROs.Results: The response was 54% in Hamburg and 27% in the rest of Germany. Nursing homes were generally well equipped for dealing with infection control: There were standards for MDROs and regular hygiene training for staff. The facilities provided adequate protective clothing, affected residents are usually isolated and hygienic laundry processing conducted. There are deficits in the communication of information on infected residents with hospitals and general practitioners. 54% of nursing homes performed risk assessments for staff infection precaution.Conclusion: There is a growing interest in MDROs and infection control will be a challenge in for residential geriatric nursing facilities in the future. This issue has also drawn increasing attention. Improvements could be achieved by improving communication between different participants in the health service, together with specific measures for staff protection at work.

  3. Problems and Concerns Regarding Access Control System Construction in Radiation Facilities Based on the NIFS Experience

    International Nuclear Information System (INIS)

    Kawano, T.; Inoue, N.; Sakuma, Y.; Motojima, O.

    2001-01-01

    Full text: In 1998, access control system for the large helical device (LHD) experimental hall was constructed and put into operation at the National Institute for Fusion Science (NIFS) in Toki, Japan. Since then, the system has been continuously improved. It now controls access into the LHD controlled area through four entrances. The system has five turnstile gates and enables control of access at the four entrances. The system is always checking whether the shielding doors are open or closed at eight positions. The details pertaining to the construction of the system were reported at IRPA-10 held in Hiroshima, Japan, in 2000. Based on our construction experience of the NIFS access control system, we will discuss problems related to software and operational design of the system. We will also discuss some concerns regarding the use of the system in radiation facilities. The problems we will present concern, among other thing, individual registration, time control, turnstile control, interlock signal control, data aggregation and transactions, automatic and manual control, and emergency procedures. For example, in relation to the time control and turnstile control functions, we will discuss the gate-opening time interval for an access event, the timing of access data recording, date changing, turn bar control, double access, and access error handling. (author)

  4. Software solutions manage the definition, operation, maintenance and configuration control of the National Ignition Facility

    International Nuclear Information System (INIS)

    Dobson, D.; Churby, A.; Krieger, E.; Maloy, D.; White, K.

    2011-01-01

    The National Ignition Facility (NIF) is the world's largest laser composed of millions of individual parts brought together to form one massive assembly. Maintaining control of the physical definition, status and configuration of this structure is a monumental undertaking yet critical to the validity of the shot experiment data and the safe operation of the facility. The NIF business application suite of software provides the means to effectively manage the definition, build, operation, maintenance and configuration control of all components of the National Ignition Facility. State of the art Computer Aided Design software applications are used to generate a virtual model and assemblies. Engineering bills of material are controlled through the Enterprise Configuration Management System. This data structure is passed to the Enterprise Resource Planning system to create a manufacturing bill of material. Specific parts are serialized then tracked along their entire lifecycle providing visibility to the location and status of optical, target and diagnostic components that are key to assessing pre-shot machine readiness. Nearly forty thousand items requiring preventive, reactive and calibration maintenance are tracked through the System Maintenance and Reliability Tracking application to ensure proper operation. Radiological tracking applications ensure proper stewardship of radiological and hazardous materials and help provide a safe working environment for NIF personnel.

  5. Software solutions manage the definition, operation, maintenance and configuration control of the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Dobson, D; Churby, A; Krieger, E; Maloy, D; White, K

    2011-07-25

    The National Ignition Facility (NIF) is the world's largest laser composed of millions of individual parts brought together to form one massive assembly. Maintaining control of the physical definition, status and configuration of this structure is a monumental undertaking yet critical to the validity of the shot experiment data and the safe operation of the facility. The NIF business application suite of software provides the means to effectively manage the definition, build, operation, maintenance and configuration control of all components of the National Ignition Facility. State of the art Computer Aided Design software applications are used to generate a virtual model and assemblies. Engineering bills of material are controlled through the Enterprise Configuration Management System. This data structure is passed to the Enterprise Resource Planning system to create a manufacturing bill of material. Specific parts are serialized then tracked along their entire lifecycle providing visibility to the location and status of optical, target and diagnostic components that are key to assessing pre-shot machine readiness. Nearly forty thousand items requiring preventive, reactive and calibration maintenance are tracked through the System Maintenance & Reliability Tracking application to ensure proper operation. Radiological tracking applications ensure proper stewardship of radiological and hazardous materials and help provide a safe working environment for NIF personnel.

  6. DAQ INSTALLATION IN USC COMPLETED

    CERN Multimedia

    A. Racz

    After one year of work at P5 in the underground control rooms (USC55-S1&S2), the DAQ installation in USC55 is completed. The first half of 2006 was dedicated to the DAQ infrastructures installation (private cable trays, rack equipment for a very dense cabling, connection to services i.e. water, power, network). The second half has been spent to install the custom made electronics (FRLs and FMMs) and place all the inter-rack cables/fibers connecting all sub-systems to central DAQ (more details are given in the internal pages). The installation has been carried out by DAQ group members, coming from the hardware and software side as well. The pictures show the very nice team spirit !

  7. Fissile material detection and control facility with pulsed neutron sources and digital data processing

    International Nuclear Information System (INIS)

    Romodanov, V.L.; Chernikova, D.N.; Afanasiev, V.V.

    2010-01-01

    Full text: In connection with possible nuclear terrorism, there is long-felt need of devices for effective control of radioactive and fissile materials in the key points of crossing the state borders (airports, seaports, etc.), as well as various customs check-points. In International Science and Technology Center Projects No. 596 and No. 2978, a new physical method and digital technology have been developed for the detection of fissile and radioactive materials in models of customs facilities with a graphite moderator, pulsed neutron source and digital processing of responses from scintillation PSD detectors. Detectability of fissile materials, even those shielded with various radiation-absorbing screens, has been shown. The use of digital processing of scintillation signals in this facility is a necessary element, as neutrons and photons are discriminated in the time dependence of fissile materials responses at such loads on the electronic channels that standard types of spectrometers are inapplicable. Digital processing of neutron and photon responses practically resolves the problem of dead time and allows implementing devices, in which various energy groups of neutrons exist for some time after a pulse of source neutrons. Thus, it is possible to detect fissile materials deliberately concealed with shields having a large cross-section of absorption of photons and thermal neutrons. Two models of detection and the control of fissile materials were advanced: 1. the model based on graphite neutrons moderator and PSD scintillators with digital technology of neutrons and photons responses separation; 2. the model based on plastic scintillators and detecting of time coincidences of fission particles by digital technology. Facilities that count time coincidences of neutrons and photons occurring in the fission of fissile materials can use an Am Li source of neutrons, e.g. that is the case with the AWCC system. The disadvantages of the facility are related to the issues

  8. Control in personnel exposure of RCD/FCD facility RLG during the period 2005 - 2008

    International Nuclear Information System (INIS)

    Murali, S.; Thanamani, S.; Sapkal, J.A.; Bairwa, Satya Manoj

    2010-01-01

    Full text: Radio Chemistry Wing, RLG, houses Radio Chemistry Division and Fuel Chemistry Division and certain common utility services. The personnel in the facility carry out radiochemical operations involving isotopes of Pu and other actinides. The HP Unit, Radio Chemistry Wing provides essential safety coverage to the personnel of the facility. The lab personnel of RCD/FCD facility at RLG carry out active operations, such operations held in suitable containment systems, under the HP supervision by RHC Unit advising safe work practices. The lab personnel are provided with monitoring programmes viz. TLD, Bio-assay and Lung counting periodically. Presently the dose limit for occupational exposure is 20 mSv per annum with 100 mSv for 5 consecutive calendar years. The present paper on TLD dose report enlists the details of the personnel exposure year wise and highlights the control in personnel exposure due to the safe procedures followed. The decreasing trend in the average personnel exposure over the period 2005 - 2008 validates the practice of adherence to safety procedures, though the amount of activity handled in the facility has increased by a few folds

  9. Standardized facility record and report model system (FARMS) for material accounting and control

    International Nuclear Information System (INIS)

    Nishimura, Hideo; Ihara, Hitoshi; Hisamatsu, Yoshinori.

    1990-07-01

    A facility in which nuclear materials are handled maintains a facility system of accounting for and control of nuclear material. Such a system contains, as one of key elements, a record and report system. This record and report information system is a rather complex one because it needs to conform to various requirements from the national or international safeguards authorities and from the plant operator who has to achieve a safe and economical operation of the plant. Therefore it is mandatory to computerize such information system. The authors have reviewed these requirements and standardized the book-keeping and reporting procedures in line with their computerization. On the basis of this result the authors have developed a computer system, FARMS, named as an acronym of standardized facility record and report model system, mainly reflecting the requirements from the national and international safeguards authorities. The development of FARMS has also been carried out as a JASPAS - Japan Support Programme for Agency Safeguards - project since 1985 and the FARMS code was demonstrated as an accountancy tool in the regional SSAC training courses held in Japan in 1985 and 1987. This report describes the standardization of a record and report system at the facility level, its computerization as a model system and the demonstration of the developed system, FARMS. (author)

  10. Fast control and data acquisition in the neutral beam test facility

    International Nuclear Information System (INIS)

    Luchetta, A.; Manduchi, G.; Taliercio, C.

    2014-01-01

    Highlights: • The paper describes the fast control and data acquisition in the ITER neutral beam test facility. • The usage of real time control in ion beam generation and extraction is proposed. • Real time management of breakdowns is described. • The implementation of event-driven data acquisition is reported. - Abstract: Fast control and data acquisition are required in the ion source test bed of the ITER neutral beam test facility, referred to as SPIDER. Fast control will drive the operation of the power supply systems with particular reference to special asynchronous events, such as the breakdowns. These are short-circuits among grids or between grids and vessel that can occur repeatedly during beam operation. They are normal events and, as such, they will be managed by the fast control system. Cycle time associated to such fast control is down to hundreds of microseconds. Fast data acquisition is required when breakdowns occur. Event-driven data acquisition is triggered in real time by fast control at the occurrence of each breakdown. Pre- and post-event samples are acquired, allowing capturing information on transient phenomena in a whole time-window centered on the event. Sampling rate of event-driven data acquisition is up to 5 MS/s. Fast data acquisition may also be independent of breakdowns as in the case of the cavity ring-down spectroscopy where data chunks are acquired at 100 MS/s in bursts of 1.5 ms every 100 ms and are processed in real time to produce derived measurements. The paper after the description of the SPIDER fast control and data acquisition application will report the system design based on commercially available hardware and the MARTe and MDSplus software frameworks. The results obtained by running a full prototype of the fast control and data acquisition system are also reported and discussed. They demonstrate that all SPIDER fast control and data acquisition requirements can be met in the prototype solution

  11. Fast control and data acquisition in the neutral beam test facility

    Energy Technology Data Exchange (ETDEWEB)

    Luchetta, A., E-mail: adriano.luchetta@igi.cnr.it; Manduchi, G.; Taliercio, C.

    2014-05-15

    Highlights: • The paper describes the fast control and data acquisition in the ITER neutral beam test facility. • The usage of real time control in ion beam generation and extraction is proposed. • Real time management of breakdowns is described. • The implementation of event-driven data acquisition is reported. - Abstract: Fast control and data acquisition are required in the ion source test bed of the ITER neutral beam test facility, referred to as SPIDER. Fast control will drive the operation of the power supply systems with particular reference to special asynchronous events, such as the breakdowns. These are short-circuits among grids or between grids and vessel that can occur repeatedly during beam operation. They are normal events and, as such, they will be managed by the fast control system. Cycle time associated to such fast control is down to hundreds of microseconds. Fast data acquisition is required when breakdowns occur. Event-driven data acquisition is triggered in real time by fast control at the occurrence of each breakdown. Pre- and post-event samples are acquired, allowing capturing information on transient phenomena in a whole time-window centered on the event. Sampling rate of event-driven data acquisition is up to 5 MS/s. Fast data acquisition may also be independent of breakdowns as in the case of the cavity ring-down spectroscopy where data chunks are acquired at 100 MS/s in bursts of 1.5 ms every 100 ms and are processed in real time to produce derived measurements. The paper after the description of the SPIDER fast control and data acquisition application will report the system design based on commercially available hardware and the MARTe and MDSplus software frameworks. The results obtained by running a full prototype of the fast control and data acquisition system are also reported and discussed. They demonstrate that all SPIDER fast control and data acquisition requirements can be met in the prototype solution.

  12. The Medical Cyclotron Facility in RMC, Parel, BARC

    International Nuclear Information System (INIS)

    Gopalakrishna, Arjun; Banerjee, Sharmila

    2017-01-01

    The Medical Cyclotron Facility in Radiation Medicine Centre (RMC) is the first one of its kind, installed in 2002. "1"8F based radiotracers are produced in this facility on a routine basis for Positron Emission Tomography (PET), of in-house patients, as well as for supply to other nuclear medicine centers in Mumbai as well as Pune. The facility consists of the following sub parts - Cyclotron and support equipment; Radiochemistry synthesis laboratory; Quality control (QC) laboratory

  13. An M/M/c/K State-Dependent Model for Pedestrian Flow Control and Design of Facilities.

    Directory of Open Access Journals (Sweden)

    Khalidur Rahman

    Full Text Available Pedestrian overflow causes queuing delay and in turn, is controlled by the capacity of a facility. Flow control or blocking control takes action to avoid queues from building up to extreme values. Thus, in this paper, the problem of pedestrian flow control in open outdoor walking facilities in equilibrium condition is investigated using M/M/c/K queuing models. State dependent service rate based on speed and density relationship is utilized. The effective rate of the Poisson arrival process to the facility is determined so as there is no overflow of pedestrians. In addition, the use of the state dependent queuing models to the design of the facilities and the effect of pedestrian personal capacity on the design and the traffic congestion are discussed. The study does not validate the sustainability of adaptation of Western design codes for the pedestrian facilities in the countries like Bangladesh.

  14. Production planning and control for semiconductor wafer fabrication facilities modeling, analysis, and systems

    CERN Document Server

    Mönch, Lars; Mason, Scott J

    2012-01-01

    Over the last fifty-plus years, the increased complexity and speed of integrated circuits have radically changed our world. Today, semiconductor manufacturing is perhaps the most important segment of the global manufacturing sector. As the semiconductor industry has become more competitive, improving planning and control has become a key factor for business success. This book is devoted to production planning and control problems in semiconductor wafer fabrication facilities. It is the first book that takes a comprehensive look at the role of modeling, analysis, and related information systems

  15. Remotely-Controlled Shear for Dismantling Highly Radioactive Tools In Rokkasho Vitrification Facility - 12204

    Energy Technology Data Exchange (ETDEWEB)

    Mitsui, Takashi; Sawa, Shusuke; Sadaki, Akira; Awano, Toshihiko [IHI Corporation, 1 Shin-Nakahara-cho, Isogo-ku, Yokohama, Kanagawa (Japan); Cole, Matt [S.A. Technology Inc, 3985 S. Lincoln Ave., Ste. 100, Loveland CO 80537 (United States); Miura, Yasuhiko; Ino, Tooru [Japan Nuclear Fuel Limited, 4-108, Aza Okitsuke, Oaza Obuchi, Rokkasho-Mura, Kamikita-gun, Aomori (Japan)

    2012-07-01

    A high-level liquid waste vitrification facility in the Japanese Rokkasho Reprocessing Plant (RRP) is right in the middle of hot commissioning tests toward starting operation in fall of 2012. In these tests, various tools were applied to address issues occurring in the vitrification cell. Because of these tools' unplanned placement in the cell it has been necessary to dismantle and dispose of them promptly. One of the tools requiring removal is a rod used in the glass melter to improve glass pouring. It is composed of a long rod made of Inconel 601 or 625 and has been highly contaminated. In order to dismantle these tools and to remotely put them in a designated waste basket, a custom electric shear machine was developed. It was installed in a dismantling area of the vitrification cell by remote cranes and manipulators and has been successfully operated. It can be remotely dismantled and placed in a waste basket for interim storage. This is a very good example of a successful deployment of a specialty remote tool in a hot cell environment. This paper also highlights how commissioning and operations are done in the Japanese Rokkasho Reprocessing Plant. (authors)

  16. Concerning control of radiation exposure to workers in nuclear reactor facilities for testing and nuclear reactor facilities in research and development phase (fiscal 1987)

    International Nuclear Information System (INIS)

    1988-01-01

    A nuclear reactor operator is required by the Nuclear Reactor Control Law to ensure that the radiation dose to workers engaged in the operations of his nuclear reactor is controlled below the permissible exposure doses that are specified in notifications issued based on the Law. The present note briefly summarizes the data given in the Reports on Radiation Control, which have been submitted according to the Nuclear Reactor Control Law by the operators of nuclear reactor facilities for testing and those in the research and development phase, and the Reports on Control of Radiation Exposure to Workers submitted in accordance with the applicable administrative notices. According to these reports, the measured exposure to workers in 1987 were below the above-mentioned permissible exposure doses in all these nuclear facilities. The 1986 and 1987 measurements of radiation exposure dose to workers in nuclear reactor facilities for testing are tabulated. The measurements cover dose distribution among the facilities' personnel and workers of contractors. They also cover the total exposure dose for all workers in each of four plants operated under the Japan Atomic Energy Research Institute and the Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

  17. A multichannel deflection plates control system for the ALF facility at the APS

    International Nuclear Information System (INIS)

    Deriy, B.

    2006-01-01

    A deflection plates control system was developed as part of SPIRIT (Single Photon Ionization/Resonant Ionization to Threshold), a new secondary neutral mass spectrometry (SNMS) instrument that uses tunable vacuum ultraviolet light from the APS ALF (Argonne Linear Free-electron laser) facility for postionization. The system comprises a crate controller with PC104 embedded computer, 32 amplifiers, and two 1-kV power supplies. Thirty-two D/A converters are used to control voltages at the deflection plates within ± 400 V with 100-mV resolution. An algorithm for simultaneous sweeping of up to 16 XY areas with 10-(micro)s time resolution also has been implemented in the embedded computer. The purpose of the system is to supply potentials to various ion optical elements for electrostatic control of keV primary and secondary ion beams in this SNMS instrument. The control system is of particular value in supplying (1) bipolar potentials for steering ions, (2) multiple potentials for octupole lenses that shape the ion beams, and (3) ramped deflection potentials for rastering the primary ion beam. The system has been in use as part of the SPIRIT instrument at the ALF facility since 2002.

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

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  19. 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.

  20. Development and analysis of an economizer control strategy algorithm to promote an opportunity for energy savings in air conditioning installations

    Energy Technology Data Exchange (ETDEWEB)

    Neto, Jose H.M.; Azevedo, Walter L. [Centro Federal de Educacao Tecnologica de Minas Gerais (CEFET), Belo Horizonte, MG (Brazil). Dept. de Engenharia Mecanica]. E-mail: henrique@daem.des.cefetmg.br

    2000-07-01

    This work presents an algorithm control strategy denominated enthalpy economizer. The objective of this algorithm strategy is to determine the adequate fractions of outside and return air flowrates entering a cooling coil based on the analysis of the outside, return and supply air enthalpies, rather than on the analysis of the dry bulb temperatures. The proposed algorithm predicts the actual opening position of the outside and return air dampers in order to provide the lower mixing air enthalpy. First, the psychometrics properties of the outside and return air are calculated from actual measurements of the dry and wet bulb temperatures. Then, three distinct cases are analyzed: the enthalpy of the outside air is lower than the enthalpy of the supply air (free cooling); the enthalpy of the outside air is higher than the enthalpy of the return air; the enthalpy of the outside air is lower than the enthalpy of the return air and higher than the temperature of the supply air. Different outside air conditions were selected in order to represent typical weather data of Brazilians cities, as well as typical return air conditions. It was found that the enthalpy control strategy could promote an opportunity for energy savings mainly during mild nights and wintertime periods as well as during warm afternoons and summertime periods, depending on the outside air relative humidity. The proposed algorithm works well and can be integrated in some commercial automation software to reduce energy consumption and electricity demand. (author)