WorldWideScience

Sample records for facilities engineering command

  1. Sustainable Acquisition Process Improvement for Naval Facilities Engineering Command

    National Research Council Canada - National Science Library

    Sanders, Erin

    2003-01-01

    .... To meet the new requirements, laws must be implemented through effective policy. For over 6 years, the Navy has been acquiring sustainably designed facilities and has recently set sustainable development policy guidelines...

  2. Acquisition Quality Improvement Within Naval Facilities Engineering Command Southwest

    Science.gov (United States)

    2015-06-01

    support, encouragement, prayers, and the endless cups of coffee you surprised me with. I treasure you and have a lifetime to show you my gratitude. To...Peterson for not allowing me to stop when it seemed like the whole world was caving in on me and for providing the guidance to start this project. Marlene...Arizona, 2 Utah, Colorado and New Mexico . NAVFAC SW provides public works, planning, engineering / design, construction, real estate, environmental

  3. Final Report on the Audit of Architect-Engineer Contracting at the Officer in Charge of Construction, Naval Facilities Engineering Command Contracts, Mediterranean, Madrid, Spain

    Science.gov (United States)

    1990-11-30

    This is our final report on the audit of Architect-Engineer Contracting for the Officer in Charge of Construction, Naval Facilities Engineering...Command Contracts, Mediterranean, for your information and use. This is the fourth in a series of reports issued as part of the audit of architect-engineer...A-E) contracting. The Contract Management Directorate made the audit from August 1989 through July 1990. When we expanded the audit scope to include

  4. Proceedings of Naval Facilities Engineering Command Ocean Engineering Conference Held at Washington DC on 23-25 September 1969

    Science.gov (United States)

    1969-09-01

    use a "plucking" process rather than a pruning " process with our established projects. In this way, the im- portant projects will be accomplished in...Enger, CEC, USN, Commander, NAVFAC 1000-1015 "Ocean Engineering Capt. W.A. Walls Policies" 1015-1030 Coffee Break 1030-1045 Conference Objectives Dr...of Structures a. SEALAB b. TEKTITE Dr. J.D. Stachiw, NCEL c. Concrete Structures D. Potter, NAVFAC d. Penetrations 0945-1000 Coffee Break 1000-1100 e

  5. Engine Test Facility (ETF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Air Force Arnold Engineering Development Center's Engine Test Facility (ETF) test cells are used for development and evaluation testing of propulsion systems for...

  6. Systems Engineering Management Training at Naval Air Systems Command

    National Research Council Canada - National Science Library

    Rebel, James

    2000-01-01

    Within the past few years, the Naval Air Systems Command (NAVAIR) has undergone several major changes including an engineering reorganization from a matrix organization to an Integrated Program Team/Competency Aligned Organization (IPT/CAO...

  7. The engineering test facility

    International Nuclear Information System (INIS)

    Steiner, D.; Becraft, W.R.; Sager, P.H.

    1981-01-01

    The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The ETF would provide a test-bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy established the ETF Design Center activity to prepare the design of the ETF. This paper describes the design status of the ETF. (orig.)

  8. Engineering test facility

    International Nuclear Information System (INIS)

    Steiner, D.; Becraft, W.R.; Sager, P.H.

    1981-01-01

    The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The ETF would provide a test-bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy established the ETF Design Center activity to prepare the design of the ETF. This paper described the design status of the ETF

  9. Environmental Assessment: Communications-Electronics Research, Development and Engineering Command (CERDEC) Flight Activity Facility at the Joint Base McGuire-Dix-Lakehurst, New Jersey

    Science.gov (United States)

    2013-01-01

    portions of the original Lakehurst Proving Ground operations, specifically a goat pasture and associated farm buildings, were located within the project...would continue to receive fuel from the centrally managed fuel farm operation located south of Hangar 6. • The facility would connect to existing...Rounds Road. An undated map6 from the Lakehurst Proving Ground era depicts the project study area as a fenced goat pasture. 3.2.1 Zoning and

  10. A comparison of current Naval Facilities Engineering Command field office staffing methods, state staffing methods and the construction industry institutes owner contractor work structure

    OpenAIRE

    Monreal, Michael

    2001-01-01

    CIVINS (Civilian Institutions) Thesis document This report was generated by accepting a report topic contained in a list of topics on the Civil Engineer Corps Graduate School Information web page. The topic request and description is noted as follows: Topic. How to Measure Staffing Requirements in ROICC offices and Other Acquisition Functions with a description. Description: We base current staffing requirements on history and only adjust from what we have used in the past years. It is sus...

  11. DUPIC facility engineering

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J S; Choi, J W; Go, W I; Kim, H D; Song, K C; Jeong, I H; Park, H S; Im, C S; Lee, H M; Moon, K H; Hong, K P; Lee, K S; Suh, K S; Kim, E K; Min, D K; Lee, J C; Chun, Y B; Paik, S Y; Lee, E P; Yoo, G S; Kim, Y S; Park, J C

    1997-09-01

    In the early stage of the project, a comprehensive survey was conducted to identify the feasibility of using available facilities and of interface between those facilities. It was found out that the shielded cell M6 interface between those facilities. It was found out that the shielded cell M6 of IMEF could be used for the main process experiments of DUPIC fuel fabrication in regard to space adequacy, material flow, equipment layout, etc. Based on such examination, a suitable adapter system for material transfer around the M6 cell was engineered. Regarding the PIEF facility, where spent PWR fuel assemblies are stored in an annex pool, disassembly devices in the pool are retrofitted and spent fuel rod cutting and shipping system to the IMEF are designed and built. For acquisition of casks for radioactive material transport between the facilities, some adaptive refurbishment was applied to the available cask (Padirac) based on extensive analysis on safety requirements. A mockup test facility was newly acquired for remote test of DUPIC fuel fabrication process equipment prior to installation in the M6 cell of the IMEF facility. (author). 157 refs., 57 tabs., 65 figs.

  12. DUPIC facility engineering

    International Nuclear Information System (INIS)

    Lee, J. S.; Choi, J. W.; Go, W. I.; Kim, H. D.; Song, K. C.; Jeong, I. H.; Park, H. S.; Im, C. S.; Lee, H. M.; Moon, K. H.; Hong, K. P.; Lee, K. S.; Suh, K. S.; Kim, E. K.; Min, D. K.; Lee, J. C.; Chun, Y. B.; Paik, S. Y.; Lee, E. P.; Yoo, G. S.; Kim, Y. S.; Park, J. C.

    1997-09-01

    In the early stage of the project, a comprehensive survey was conducted to identify the feasibility of using available facilities and of interface between those facilities. It was found out that the shielded cell M6 interface between those facilities. It was found out that the shielded cell M6 of IMEF could be used for the main process experiments of DUPIC fuel fabrication in regard to space adequacy, material flow, equipment layout, etc. Based on such examination, a suitable adapter system for material transfer around the M6 cell was engineered. Regarding the PIEF facility, where spent PWR fuel assemblies are stored in an annex pool, disassembly devices in the pool are retrofitted and spent fuel rod cutting and shipping system to the IMEF are designed and built. For acquisition of casks for radioactive material transport between the facilities, some adaptive refurbishment was applied to the available cask (Padirac) based on extensive analysis on safety requirements. A mockup test facility was newly acquired for remote test of DUPIC fuel fabrication process equipment prior to installation in the M6 cell of the IMEF facility. (author). 157 refs., 57 tabs., 65 figs

  13. Engine Environment Research Facility (EERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: This facility supports research and development testing of the behavior of turbine engine lubricants, fuels and sensors in an actual engine environment....

  14. Materials Engineering Research Facility (MERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Argonne?s Materials Engineering Research Facility (MERF) enables engineers to develop manufacturing processes for producing advanced battery materials in sufficient...

  15. Rapid Response Command and Control (R2C2): a systems engineering analysis of scaleable communications for Regional Combatant Commanders

    OpenAIRE

    Sullivan, Lisa; Cannon, Lennard; Reyes, Ronel; Bae, Kitan; Colgary, James; Minerowicz, Nick; Leong, Chris; Lim, Harry; Lim, Hang Sheng; Ng, Chin Chin; Neo, Tiong Tien; Tan, Guan Chye; Ng, Yu Loon; Wong, Eric; Wong, Heng Yue

    2006-01-01

    Includes supplementary material. Disaster relief operations, such as the 2005 Tsunami and Hurricane Katrina, and wartime operations, such as Operation Enduring Freedom and Operation Iraqi Freedom, have identified the need for a standardized command and control system interoperable among Joint, Coalition, and Interagency entities. The Systems Engineering Analysis Cohort 9 (SEA-9) Rapid Response Command and Control (R2C2) integrated project team completed a systems engineering (SE) ...

  16. DUPIC facility engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. J.; Lee, H. H.; Kim, K. H. and others

    2000-03-01

    The objectives of this study are (1) the refurbishment for PIEF(Post Irradiation Examination Facility) and M6 hot-cell in IMEF(Irradiated Material Examination Facility), (2) the establishment of the compatible facility for DUPIC fuel fabrication experiments which is licensed by government organization, and (3) the establishment of the transportation system and transportation cask for nuclear material between facilities. The report for this project describes following contents, such as objectives, necessities, scope, contents, results of current step, R and D plan in future and etc.

  17. DUPIC facility engineering

    International Nuclear Information System (INIS)

    Park, J. J.; Lee, H. H.; Kim, K. H.

    2002-03-01

    With starting DUPIC fuel fabrication experiment by using spent fuels, 1) operation and refurbishment for DFDF (DUPIC fuel development facility), and 2) operation and improvement of transportation equipment for radioactive materials between facilities became the objectives of this study. This report describes objectives of the project, necessities, state of related technology, R and D scope, R and D results, proposal for application etc

  18. Earthquake engineering for nuclear facilities

    CERN Document Server

    Kuno, Michiya

    2017-01-01

    This book is a comprehensive compilation of earthquake- and tsunami-related technologies and knowledge for the design and construction of nuclear facilities. As such, it covers a wide range of fields including civil engineering, architecture, geotechnical engineering, mechanical engineering, and nuclear engineering, for the development of new technologies providing greater resistance against earthquakes and tsunamis. It is crucial both for students of nuclear energy courses and for young engineers in nuclear power generation industries to understand the basics and principles of earthquake- and tsunami-resistant design of nuclear facilities. In Part I, "Seismic Design of Nuclear Power Plants", the design of nuclear power plants to withstand earthquakes and tsunamis is explained, focusing on buildings, equipment's, and civil engineering structures. In Part II, "Basics of Earthquake Engineering", fundamental knowledge of earthquakes and tsunamis as well as the dynamic response of structures and foundation ground...

  19. Electronic battlespace facility for research, develoment and engineering

    NARCIS (Netherlands)

    Jense, Hans; Kuijpers, N.H.L.; Elias, R.J.D.

    1997-01-01

    In order to support its research, development and engineering activities in the area of distributed simulation for training and command & control, TNO Physics and Electronics Laboratory has developed (and continues to enhance) an Electronic Battlespace Facility (EBF). This paper presents an overview

  20. Weapons engineering tritium facility overview

    Energy Technology Data Exchange (ETDEWEB)

    Najera, Larry [Los Alamos National Laboratory

    2011-01-20

    Materials provide an overview of the Weapons Engineering Tritium Facility (WETF) as introductory material for January 2011 visit to SRS. Purpose of the visit is to discuss Safety Basis, Conduct of Engineering, and Conduct of Operations. WETF general description and general GTS program capabilities are presented in an unclassified format.

  1. Engineering test facility design center

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The ETF would provide a test bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy established the ETF Design Center activity to prepare the design of the ETF. This section describes the status of this design

  2. Military Engineers with Unity of Command: Why is This So Hard?

    National Research Council Canada - National Science Library

    Tufts, Dean

    2002-01-01

    .... Experience shows that both repositioning his engineer from under the J4 into a separate staff element, and then establishing an engineer functional component command or subordinate Joint Task Force (JTF...

  3. Introduction to nuclear facilities engineering

    International Nuclear Information System (INIS)

    Sapy, Georges

    2012-06-01

    Engineering, or 'engineer's art', aims at transforming simple principle schemes into operational facilities often complex especially when they concern the nuclear industry. This transformation requires various knowledge and skills: in nuclear sciences and technologies (nuclear physics, neutronics, thermal-hydraulics, material properties, radiation protection..), as well as in non-nuclear sciences and technologies (civil engineering, mechanics, electricity, computer sciences, instrumentation and control..), and in the regulatory, legal, contractual and financial domains. This book explains how this huge body of knowledge and skills must be organized and coordinated to create a reliable, exploitable, available, profitable and long-lasting facility, together with respecting extremely high safety, quality, and environmental impact requirements. Each aspect of the problem is approached through the commented presentation of nuclear engineering macro-processes: legal procedures and administrative authorizations, nuclear safety/radiation protection/security approach, design and detailed studies, purchase of equipments, on-site construction, bringing into operation, financing, legal, contractual and logistic aspects, all under the global control of a project management. The 'hyper-complexness' of such an approach leads to hard points and unexpected events. The author identifies the most common ones and proposes some possible solutions to avoid, mitigate or deal with them. In a more general way, he proposes some thoughts about the performance factors of a nuclear engineering process

  4. Blossom Point Satellite Tracking and Command Station

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: The Blossom Point Satellite Command and Tracking Facility (BP) provides engineering and operational support to several complex space systems for the Navy...

  5. Facility engineering for Arctic conditions

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, D.M.; McClusky, K.R.; Shirley, R.; Spitzenberger, R. [Mustang Engineering Inc., Houston, TX (United States)

    2001-07-01

    The Northstar Development Project is located on Seal Island in the Beaufort Sea, north of Prudhoe Bay. The design and engineering of the facilities for the Northstar Development Project was fraught with challenges. Mustang Engineering Incorporated was involved in the design and engineering of the pipe rack, pump house, process and compressor modules. All the characteristics of an offshore facility are present, even though the project is land-based on a man-made island. A number of the strategies developed for offshore platforms of the Gulf of Mexico were adapted to the fabrication, logistics and installation of the modules. To reduce yard fabrication time, a modularized design concept was adopted. Cost savings and onsite fabrication efficiencies were realized through open communication with the operator, early discussions with vendors, regulatory agencies, and local fabrication and installation contractors. Some improvisation and deviations were required to meet the stringent requirements for operation under Arctic conditions. The lessons learned on this project will be of use in future Arctic projects. 1 tab., 6 figs.

  6. Optimal Facility Location Tool for Logistics Battle Command (LBC)

    Science.gov (United States)

    2015-08-01

    64 Appendix B. VBA Code . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72 Appendix C. Story...should city planners have located emergency service facilities so that all households (the demand) had equal access to coverage?” The critical...programming language called Visual Basic for Applications ( VBA ). CPLEX is a commercial solver for linear, integer, and mixed integer linear programming problems

  7. Monitor for safety engineering facility

    International Nuclear Information System (INIS)

    Sato, Akira; Kaneda, Mitsunori.

    1982-01-01

    Purpose: To improve the reactor safety and decrease misoperation upon periodical inspection by instantly obtaining the judgement for the stand-by states in engineering safety facilities of a nuclear power plant. Constitution: Process inputs representing the states of valves, pumps, flowrates or the likes of the facility are gathered into an input device and inputted to a status monitor. The status of the facility inputted to the input device are judged for each of the inputs in a judging section and recognized as a present system stand-by pattern of the system (Valve) to be inspected. While on the other hand, a normal system stand-by pattern previously stored in a memory unit is read out by an instruction from an operator console and judged by comparison with the system stand-by pattern in a comparison section. The results are displayed on a display device. Upon periodical inspection, inspection procedures stored in the memory unit are displayed on the display device by the instruction from the operator console. (Seki, T.)

  8. $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

  9. Engineering test facility design definition

    Science.gov (United States)

    Bercaw, R. W.; Seikel, G. R.

    1980-01-01

    The Engineering Test Facility (ETF) is the major focus of the Department of Energy (DOE) Magnetohydrodynamics (MHD) Program to facilitate commercialization and to demonstrate the commercial operability of MHD/steam electric power. The ETF will be a fully integrated commercial prototype MHD power plant with a nominal output of 200 MW sub e. Performance of this plant is expected to meet or surpass existing utility standards for fuel, maintenance, and operating costs; plant availability; load following; safety; and durability. It is expected to meet all applicable environmental regulations. The current design concept conforming to the general definition, the basis for its selection, and the process which will be followed in further defining and updating the conceptual design.

  10. Engineered Barrier Test Facility status report, 1984

    International Nuclear Information System (INIS)

    Phillips, S.J.; Adams, M.R.; Gilbert, T.W.; Meinhardt, C.C.; Mitchell, R.M.; Waugh, W.J.

    1985-02-01

    This report provides a general summary of activities completed to date at the Hanford Engineered Barrier Test Facility. This facility is used to test and compare construction practices and performance of alternative designs of engineered barrier cover systems. These cover systems are being evaluated for potential use for isolation and confinement of buried waste disposal structures

  11. Integrated engineering system for nuclear facilities building

    International Nuclear Information System (INIS)

    Tomura, H.; Miyamoto, A.; Futami, F.; Yasuda, S.; Ohtomo, T.

    1995-01-01

    In the construction of buildings for nuclear facilities in Japan, construction companies are generally in charge of the building engineering work, coordinating with plant engineering. An integrated system for buildings (PROMOTE: PROductive MOdeling system for Total nuclear Engineering) described here is a building engineering system including the entire life cycle of buildings for nuclear facilities. A Three-dimensional (3D) building model (PRO-model) is to be in the core of the system (PROMOTE). Data sharing in the PROMOTE is also done with plant engineering systems. By providing these basic technical foundations, PROMOTE is oriented toward offering rational, highquality engineering for the projects. The aim of the system is to provide a technical foundation in building engineering. This paper discusses the characteristics of buildings for nuclear facilities and the outline of the PROMOTE. (author)

  12. Sustainable Acquisition Process Improvement for Naval Facilities Engineering Command

    National Research Council Canada - National Science Library

    Sanders, Erin

    2003-01-01

    .... While this guidance is intended to create an open and competitive process to achieve lowest cost or best value, conflicts among traditional acquisition processes and new law requirements are emerging...

  13. The Eichleay Formula in Naval Facilities Engineering Command (NAVFACENGCOM) Contracting

    Science.gov (United States)

    1994-07-01

    overhead is quite simple and straight forward [Carpenter/Cushman, 1990]. However, there is much litigation over whether the Eichleay formula accurately...amun uotility Ouiy is a given hactio and the -ura. of tdo would be allowed bed te contrato purchased tds function can be detwirmied -ehoo~a NHomay be

  14. Detonation Engine Research Facility (DERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: This facility is configured to safely conduct experimental pressuregain combustion research. The DERF is capable of supporting up to 60,000 lbf thrust...

  15. Tokamak Engineering Technology Facility scoping study

    Energy Technology Data Exchange (ETDEWEB)

    Stacey, W.M. Jr.; Abdou, M.A.; Bolta, C.C.

    1976-03-01

    A scoping study for a Tokamak Engineering Technology Facility (TETF) is presented. The TETF is a tokamak with R = 3 m and I/sub p/ = 1.4 MA based on the counterstreaming-ion torus mode of operation. The primary purpose of TETF is to demonstrate fusion technologies for the Experimental Power Reactor (EPR), but it will also serve as an engineering and radiation test facility. TETF has several technological systems (e.g., superconducting toroidal-field coil, tritium fuel cycle, impurity control, first wall) that are prototypical of EPR.

  16. Tokamak Engineering Technology Facility scoping study

    International Nuclear Information System (INIS)

    Stacey, W.M. Jr.; Abdou, M.A.; Bolta, C.C.

    1976-03-01

    A scoping study for a Tokamak Engineering Technology Facility (TETF) is presented. The TETF is a tokamak with R = 3 m and I/sub p/ = 1.4 MA based on the counterstreaming-ion torus mode of operation. The primary purpose of TETF is to demonstrate fusion technologies for the Experimental Power Reactor (EPR), but it will also serve as an engineering and radiation test facility. TETF has several technological systems (e.g., superconducting toroidal-field coil, tritium fuel cycle, impurity control, first wall) that are prototypical of EPR

  17. Air compliance through pollution prevention at Air Force Materiel Command facilities.

    Energy Technology Data Exchange (ETDEWEB)

    Kolpa, R.; Ryckman, S.J. Jr.; Smith, A.E.

    1999-03-19

    Options for air compliance through pollution prevention (P2) have been identified at 14 facilities of the US Air Force Materiel Command, ranging from depots with significant light industrial activity to laboratories. Previous P2 efforts concentrated on reducing hazardous and solid wastes, with any reduction in air impacts generally being a collateral benefit. This work focused on reducing air emissions and air compliance vulnerabilities. P2 options were identified in three stages. First, potentially applicable P2 options were identified from Internet and published information. Attention was given to identifying the types of sources to which an option could be applied, the option's state of development, and constraints that could limit its application. Traditional P2 options involving technology or equipment changes and material substitution were considered. In addition, newer approaches based on administrative ''controls'' were considered. These included inserting P2 into operating permits in exchange for administrative relief, privatization, derating boilers, and reducing an installation's potential to emit and compliance vulnerability by separating sources not under the Air Force's ''common control.'' Next, criteria and toxic emissions inventories by source category were prepared from inventory data supplied by facilities. The major problems at this stage were differences in the levels of detail provided by facilities and in the categories used by different installations. Emitting categories were matched to P2 option categories to identify candidate options. Candidates were screened to account for local regulations and technical information about sources in the inventories. When possible, emission reductions were estimated to help facility personnel prioritize options. Some options identified are being actively pursued by facilities to determine their site-specific feasibility. Although much work has been

  18. A Hybrid Approach to Cognitive Engineering: Supporting Development of a Revolutionary Warfighter-Centered Command and Control System

    National Research Council Canada - National Science Library

    Ockerman, Jennifer; McKneely, Jennifer A; Koterba, Nathan

    2005-01-01

    ...) for the requirements analysis and design of revolutionary command and control systems and domains. This hybrid approach uses knowledge elicitation and representation techniques from several current cognitive engineering methodologies...

  19. Engineering risk assessment for hydro facilities

    International Nuclear Information System (INIS)

    Laurence, K.G.

    1991-01-01

    Faced with escalating property insurance premiums, the Alaska Energy Authority decided to evaluate what losses may realistically be expected due to catastrophic events at their hydroelectric generation and transmission facilities. Ideally insurance rates are established using historic loss statistics. Where these statistics are non-existent, other means must be employed to estimate expected losses so that appropriate steps may be taken to protect investments in facilities. The natural perils of earthquake, flood, tidal wave (tsunami), wind, snow and internal failure potentially can cause catastrophic damage, but due to their infrequency in the higher magnitudes, meaningful statistics are as yet insufficient to be of value in estimating losses from these events. In order to overcome this deficiency a quasi-engineering approach can be adopted as distinct from the actuarial approach preferred and most often used by the insurance industry. This paper describes the quasi-engineering approach used for this assessment with a specific example worked through for earthquake peril

  20. Conceptual studies of plasma engineering test facility

    International Nuclear Information System (INIS)

    Hiraoka, Toru; Tazima, Teruhiko; Sugihara, Masayoshi; Kasai, Masao; Shinya, Kichiro

    1979-04-01

    Conceptual studies have been made of a Plasma Engineering Test Facility, which is to be constructed following JT-60 prior to the experimental power reactor. The physical aim of this machine is to examine self-ignition conditions. This machine possesses all essential technologies for reactor plasma, i.e. superconducting magnet, remote maintenance, shielding, blanket test modules, tritium handling. Emphasis in the conceptual studies was on structural consistency of the machine and whether the machine would be constructed practically. (author)

  1. Fermilab HEPCloud Facility Decision Engine Design

    Energy Technology Data Exchange (ETDEWEB)

    Tiradani, Tiradani,Anthony [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Altunay, Mine [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Dagenhart, David [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Kowalkowski, Jim [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Litvintsev, Dmitry [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Lu, Qiming [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Mhashilkar, Parag [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Moibenko, Alexander [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Paterno, Marc [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Timm, Steven [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

    2017-05-23

    The Decision Engine is a critical component of the HEP Cloud Facility. It provides the functionality of resource scheduling for disparate resource providers, including those which may have a cost or a restricted allocation of cycles. Along with the architecture, design, and requirements for the Decision Engine, this document will provide the rationale and explanations for various design decisions. In some cases, requirements and interfaces for a limited subset of external services will be included in this document. This document is intended to be a high level design. The design represented in this document is not complete and does not break everything down in detail. The class structures and pseudo-code exist for example purposes to illustrate desired behaviors, and as such, should not be taken literally. The protocols and behaviors are the important items to take from this document. This project is still in prototyping mode so flaws and inconsistencies may exist and should be noted and treated as failures.

  2. Upgrades of Hanford Engineering Development Laboratory hot cell facilities

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  3. Design of a fusion engineering test facility

    International Nuclear Information System (INIS)

    Sager, P.H.

    1980-01-01

    The fusion Engineering Test Facility (ETF) is being designed to provide for engineering testing capability in a program leading to the demonstration of fusion as a viable energy option. It will combine power-reactor-type components and subsystems into an integrated tokamak system and provide a test bed to test blanket modules in a fusion environment. Because of the uncertainties in impurity control two basic designs are being developed: a design with a bundle divertor (Design 1) and one with a poloidal divertor (Design 2). The two designs are similar where possible, the latter having somewhat larger toroidal field (TF) coils to accommodate removal of the larger torus sectors required for the single-null poloidal divertor. Both designs have a major radius of 5.4 m, a minor radius of 1.3 m, and a D-shaped plasma with an elongation of 1.6. Ten TF coils are incorporated in both designs, producing a toroidal field of 5.5 T on-axis. The ohmic heating and equilibrium field (EF) coils supply sufficient volt-seconds to produce a flat-top burn of 100 s and a duty cycle of 135 s, including a start of 12 s, a burn termination of 10 s, and a pumpdown of 13 s. The total fusion power during burn is 750 MW, giving a neutron wall loading of 1.5 MW/m 2 . In Design 1 of the poloidal field (PF) coils except the fast-response EF coils are located outside the FT coils and are superconducting. The fast-response coils are located inside the TF coil bore near the torus and are normal conducting so that they can be easily replaced.In Design 2 all of the PF coils are located outside the TF coils and are superconducting. Ignition is achieved with 60 MW of neutral beam injection at 150 keV. Five megawatts of radio frequency heating (electron cyclotron resonance heating) is used to assist in the startup and limit the breakdown requirement to 25 V

  4. Electronics and Telemetry Engineering and Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Electronics Laboratory is a fully equipped facility providing the capability to support electronic product development from highly complex weapon system sensors,...

  5. History of Command and Control at KSC: Kennedy Engineering Academy Series

    Science.gov (United States)

    Hurt, George Richard

    2007-01-01

    Agenda for this presentation is: Evolution of Command and Control (C&C), C&C history, Launch Processing System overview, Core System Overview, Checkout & Launch Control System, Overview and Commercial-Off-The-Shelf guidelines

  6. Interoperability requirements for a South African joint command and control test facility

    CSIR Research Space (South Africa)

    Le Roux, WH

    2008-06-01

    Full Text Available approach is followed to provide all the necessary services, mechanisms and functionalities. Since simulations and simulators form part of such a facility, interoperability standards are very important, as well as the underlying data model. The high...

  7. Unified Facilities Criteria (UFC) Design: Fire Protection Engineering for Facilities

    Science.gov (United States)

    2003-08-20

    following provisions: • Ceiling sprinkler design area must be increased by 10 percent. ESFR sprinklers must increase the required number to be...Control System ESFR Early Suppression Fast-Response Sprinklers ETL Engineering Technical Letters FAAA Fire Administration Authorization Act FM

  8. Cognitive Systems Engineering Tool Survey - A Subtask in Support of Commander's Decision Aids for Predictive Battle-Space Awareness (CDA4PBA)

    National Research Council Canada - National Science Library

    Sanders, Mary; Fitzhugh, Elisabeth

    2005-01-01

    ...) DO 6, Commander's Decision Aids for Predictive Battle-Space Awareness, (CDA4PBA) is to identify system requirements necessary to capture the entire software and systems engineering process from concept...

  9. Synthesis of engineering designs of drilling facilities

    Science.gov (United States)

    Porozhsky, K.

    2018-03-01

    The article sets forth key principles of engineering of drilling equipment based on successive analysis of the goals of the production method, technologies of its implementation and conditions of mineral mining using a new approach to systematization of drilling methods. Potential advancement in the technologies and equipment of drilling is illustrated in terms of oil-well drilling.

  10. Measurement of Civil Engineering Customer Satisfaction in Tactical Air Command: A Prototype Evaluation Program.

    Science.gov (United States)

    1986-09-01

    customers . The article states that in response to a White House Office of Consumer Affairs study and with the wide use of minicomputers: Companies are...Guidelines include knowing the customers and their desires and expounding those desires to the congress, the commanders and the American people . Furthermore...In order to serve the customer , the service organization and the people that provide the service should show "unjustifiable over-ommitment to improving

  11. R and D needs assessment for the Engineering Test Facility

    International Nuclear Information System (INIS)

    1980-10-01

    The Engineering Test Facility (ETF), planned to be the next major US magnetic fusion device, has its mission (1) to provide the capability for moving into the engineering phase of fusion development and (2) to provide a test-bed for reactor components in a fusion environment. The design, construction, and operation of the ETF requires an increasing emphasis on certain key research and development (R and D) programs in magnetic fusion in order to provide the necessary facility design base. This report identifies these needs and discusses the apparent inadequacies of the presently planned US program to meet them, commensurate with the ETF schedule

  12. Remote operations in a Fusion Engineering Research Facility (FERF)

    International Nuclear Information System (INIS)

    Doggett, J.N.

    1975-01-01

    The proposed Fusion Engineering Research Facility (FERF) has been designed for the test and evaluation of materials that will be exposed to the hostile radiation environment created by fusion reactors. Because the FERF itself must create a very hostile radiation environment, extensive remote handling procedures will be required as part of its routine operations as well as for both scheduled and unscheduled maintenance. This report analyzes the remote-handling implications of a vertical- rather than horizontal-orientation of the FERF magnet, describes the specific remote-handling facilities of the proposed FERF installation and compares the FERF remote-handling system with several other existing and proposed facilities. (U.S.)

  13. The cost of engineered disposal facilities

    International Nuclear Information System (INIS)

    Mallory, C.W.; Razor, J.E.; Mills, D.

    1987-01-01

    An improved disposal trench was designed, constructed and placed into operation at the Maxey Flats Disposal Site during the period April 1985 through July 1986. With the improved trench design, the waste packages are placed in clusters and the surrounding space is filled with gravel and grouted with a sand/cement mixture to form walls and cells that surround the waste package. The walls provide structural support for a poly-ethylene reinforced soil beam which in turn supports a multi-layer protective cap. About 2,700 drums of waste (20,250 CF) were placed into the trench. The total cost of the improved trench was $193,500 and the unit cost was $9.56 per cubic foot not including the placement of the waste. The engineered features of the trench (i.e., sidewall infiltration barrier, grout backfill and the soil beam) cost $82,600 for a unit cost of $4.08 per cubic foot of waste. This is compared to the cost of concrete cannisters used for radioactive waste disposal. On a production basis the cannisters are estimated to cost about $1,260. Depending upon the type waste, the cost of the cannisters will range from $2 to $12 per cubic foot of waste. The slightly higher cost of the concrete cannisters is offset by certain performance advantages

  14. Preliminary conceptual study of engineering-scale pyroprocess demonstration facility

    International Nuclear Information System (INIS)

    Moon, Seong-In; Chong, Won-Myung; You, Gil-Sung; Ku, Jeong-Hoe; Kim, Ho-Dong

    2013-01-01

    Highlights: ► The conceptual design of a pyroprocess demonstration facility was performed. ► The design requirements for the pyroprocess hot cell and equipment were determined. ► The maintenance concept for the pyroprocess hot cell was presented. -- Abstract: The development of an effective management technology of spent fuel is important to enhance environmental friendliness, cost viability and proliferation resistance. In Korea, pyroprocess technology has been considered as a fuel cycle option to solve the spent fuel accumulation problems. PRIDE (PyRoprocess Integrated inactive DEmonstration facility) has been developed from 2007 to 2012 in Korea as a cold test facility to support integrated pyroprocessing and an equipment demonstration, which is essential to verify the pyroprocess technology. As the next stage of PRIDE, the design requirements of an engineering-scale demonstration facility are being developed, and the preliminary conceptual design of the facility is being performed for the future. In this paper, the main design requirements for the engineering-scale pyroprocess demonstration facility were studied in the throughput of 10tHM a year. For the preliminary conceptual design of the facility, the design basis of the pyroprocess hot cell was suggested, and the main equipment, main process area, operation area, maintenance area, and so on were arranged in consideration of the effective operation of the hot cells. Also, the argon system was designed to provide and maintain a proper inert environment for the pyroprocess. The preliminary conceptual design data will be used to review the validity of the engineering-scale pyroprocess demonstration facility that enhances both safety and nonproliferation

  15. Engineering study for closure of 209E facility

    International Nuclear Information System (INIS)

    Brevick, C.H.; Heys, W.H.; Johnson, E.D.

    1997-01-01

    This document is an engineering study for evaluating alternatives to determine the most cost effective closure plan for the 209E Facility, Critical Mass Laboratory. This laboratory is located in the 200 East Area of the Hanford Site and contains a Critical Assembly Room and a Mix room were criticality experiments were once performed

  16. Engineering study for closure of 209E facility

    Energy Technology Data Exchange (ETDEWEB)

    Brevick, C.H.; Heys, W.H.; Johnson, E.D.

    1997-07-07

    This document is an engineering study for evaluating alternatives to determine the most cost effective closure plan for the 209E Facility, Critical Mass Laboratory. This laboratory is located in the 200 East Area of the Hanford Site and contains a Critical Assembly Room and a Mix room were criticality experiments were once performed.

  17. Decommissioning engineering systems for nuclear facilities and knowledge inheritance for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Tachibana, Mitsuo

    2016-01-01

    Information on construction, operation and maintenance of a nuclear facility is essential in order to plan and implement the decommissioning of the nuclear facility. A decommissioning engineering system collects these information efficiently, retrieves necessary information rapidly, and support to plan the reasonable decommissioning as well as the systematic implementation of dismantling activities. Then, knowledge of workers involved facility operation and dismantling activities is important because decommissioning of nuclear facility will be carried out for a long period. Knowledge inheritance for decommissioning has been carried out in various organizations. This report describes an outline of and experiences in applying decommissioning engineering systems in JAEA and activities related to knowledge inheritance for decommissioning in some organizations. (author)

  18. Idaho National Engineering Laboratory irradiation facilities and their applications

    International Nuclear Information System (INIS)

    Gupta, V.P.; Herring, J.S.; Korenke, R.E.; Harker, Y.D.

    1986-05-01

    Although there is a growing need for neutron and gamma irradiation by governmental and industrial organizations in the United States and in other countries, the number of facilities providing such irradiations are limited. At the Idaho National Engineering Laboratory, there are several unique irradiation facilities producing high neutron and gamma radiation environments. These facilities could be readily used for nuclear research, materials testing, radiation hardening studies on electronic components/circuitry and sensors, and production of neutron transmutation doped (NTD) silicon and special radioisotopes. In addition, a neutron radiography unit, suitable for examining irradiated materials and assemblies, is also available. This report provides a description of the irradiation facilities and the neutron radiography unit as well as examples of their unique applications

  19. Translating DWPF design criteria into an engineered facility design

    International Nuclear Information System (INIS)

    Kemp, J.B.

    1986-01-01

    The Defense Waste Processing Facility (DWPF) takes radioactive defense waste sludge and the radioactive nuclides, cesium and strontium, from the salt solution, and incorporates them in borosilicate glass in stainless steel canisters, for subsequent disposal in a deep geologic repository. The facility was designed by Bechtel National, Inc. under a subcontract from E.I. DuPont de Nemurs and Co., the prime contractor for the Department of Energy, for the design, construction and commissioning of the plant. The design criteria were specified by the DuPont Company, based upon their extensive experience as designer, and operator since the early 1950's, of the existing Savannah River Plant facilities. Some of the design criteria imposed unusual or new requirements on the detailed design of the facilities. This paper describes some of these criteria, encompassing several engineering disciplines, and discusses the solutions and designs which were developed for the DWPF

  20. Situated cognitive engineering: Developing adaptive track handling support for naval command and control centers

    NARCIS (Netherlands)

    Neerincx, M.A.; Brake, G.M. te; Ven, J.G.M. van de; Arciszewski, H.F.R.; Greef, T.E. de; Lindenberg, J.

    2008-01-01

    Dit artikel presenteert een 'situated cognitive engineering' (SCE) methode voor het verkrijgen van een theoretisch en empirisch onderbouwde Requirements Baseline, waarin operationele, human factors, en technische eisen in samenhang naar voren komen. De methode wordt toegelicht met een ontwerp van

  1. Civil Engineering for the SHiP facility

    CERN Document Server

    Osborne, John Andrew

    2015-01-01

    The enlarged scope of the recently proposed experiment to search for Heavy Neutral Leptons, SPSC-EOI-010, is a general purpose fixed target facility which in the initial phase is aimed at a general Search for Hidden Particles (SHiP) as well as tau neutrino physics. This report represents an annex to the SHiP Technical Proposal summarizing the civil engineering considerations for SHiP.

  2. Subsidence characterization and modeling for engineered facilities in Arizona, USA

    Directory of Open Access Journals (Sweden)

    M. L. Rucker

    2015-11-01

    Full Text Available Several engineered facilities located on deep alluvial basins in southern Arizona, including flood retention structures (FRS and a coal ash disposal facility, have been impacted by up to as much as 1.8 m of differential land subsidence and associated earth fissuring. Compressible basin alluvium depths are as deep as about 300 m, and historic groundwater level declines due to pumping range from 60 to more than 100 m at these facilities. Addressing earth fissure-inducing ground strain has required alluvium modulus characterization to support finite element modeling. The authors have developed Percolation Theory-based methodologies to use effective stress and generalized geo-material types to estimate alluvium modulus as a function of alluvium lithology, depth and groundwater level. Alluvial material modulus behavior may be characterized as high modulus gravel-dominated, low modulus sand-dominated, or very low modulus fines-dominated (silts and clays alluvium. Applied at specific aquifer stress points, such as significant pumping wells, this parameter characterization and quantification facilitates subsidence magnitude modeling at its' sources. Modeled subsidence is then propagated over time across the basin from the source(s using a time delay exponential decay function similar to the soil mechanics consolidation coefficient, only applied laterally. This approach has expanded subsidence modeling capabilities on scales of engineered facilities of less than 2 to more than 15 km.

  3. A Design Framework for Predictive Engine Control Un cadre de conception pour la commande prédictive de moteurs

    Directory of Open Access Journals (Sweden)

    Wang X.

    2011-09-01

    Full Text Available Model Predictive Control (MPC has been proposed several times for automotive control, with promising results, mostly based on a linear MPC approach. However, as most automotive systems are nonlinear, Nonlinear MPC (NMPC would be an interesting option. Unfortunately, an optimal control design with a generic nonlinear model usually leads to a complex, non convex problem. Against this background, this paper presents two different schemes to take into account the system nonlinearity in the control design. First, a multi-linear MPC method is shown based on the segmentation of the system and then a control system design based on a nonlinear system identification using a quasi Linear Parameter Varying (LPV structure is proposed, which is then used in a NMPC design framework. This paper presents the approaches and the application to a well studied system, the air path of a Diesel engine. La commande prédictive par modèle (Model Predictive Control; MPC a été proposée plusieurs fois dans l’automatique pour l’automobile, avec des résultats prometteurs, principalement à partir d’une approche MPC linéaire. Toutefois, comme la plupart des systèmes automobiles sont non linéaires, la commande prédictive non linéaire (Nonlinear MPC; NMPC pourrait représenter une option intéressante. Malheureusement, la conception d’une commande optimale à partir d’un modèle non linéaire générique conduit généralement à un problème non convexe complexe. Dans ce contexte, cet article présente deux schémas différents pour prendre en compte la non linéarité du système en vue de la conception de la commande. En premier lieu, une méthode MPC multilinéaire est présentée sur la base d’une segmentation du système et, en second lieu, une conception de système de commande basée sur une identification de système non linéaire utilisant une structure quasi linéaire à paramètres variants (Linear Parameter Varying; LPV est proposée; celle

  4. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant Conceptual Design Engineering Report (CDER)

    Science.gov (United States)

    1981-01-01

    The reference conceptual design of the magnetohydrodynamic (MHD) Engineering Test Facility (ETF), a prototype 200 MWe coal-fired electric generating plant designed to demonstrate the commercial feasibility of open cycle MHD, is summarized. Main elements of the design, systems, and plant facilities are illustrated. System design descriptions are included for closed cycle cooling water, industrial gas systems, fuel oil, boiler flue gas, coal management, seed management, slag management, plant industrial waste, fire service water, oxidant supply, MHD power ventilating

  5. Maintaining the U.S. Army Research, Development and Engineering Command Prototype Integration Facilities

    Science.gov (United States)

    2014-05-01

    shelters, tents and fabric covers, mechanical aerial delivery parts and components, kitchens , and combat feeding items (see Figure 4). NSRDEC’s PIF is...generic terms and refrain from revealing confidential or classified information. Research hypotheses are as follows: H1: The PIF leadership predicts

  6. An Analysis of 4D Modeling for Use by the Naval Facilities Engineering Command

    OpenAIRE

    Jors, Patrick C.

    2004-01-01

    CIVINS (Civilian Institutions) Thesis document Approved for public release ; distribution is unlimited The purpose of this paper is to explain recent research on the costs and benefits of 4D CAD technology to determine if it can benefit the U.S. Navy in management of its construction projects. The report will begin with a brief history of project management and the development of 4D computer based models. Sections 3 and 4 will discuss advantages and disadvantages of using 4D programs. A...

  7. Unliquidated Obligations for Air Force-Funded Projects Administered by The Naval Facilities Engineering Command

    National Research Council Canada - National Science Library

    2001-01-01

    ... consolidated financial statements. The Air Force Audit Agency requested us to assist in its review of the Statement of Budgetary Resources for the Air Force General Fund by reviewing unliquidated obligations for Air Force-funded...

  8. Waste Receiving and Processing (WRAP) facility engineering study

    International Nuclear Information System (INIS)

    Christie, M.A.; Cammann, J.W.; McBeath, R.S.; Rode, H.H.

    1985-01-01

    A new Hanford waste management facility, the Waste Receiving and Processing (WRAP) facility (planned to be operational by FY 1994) will receive, inspect, process, and repackage contact-handled transuranic (CH-TRU) contaminated solid wastes. The wastes will be certified according to the waste acceptance criteria for disposal at the Waste Isolation Pilot Plant (WIPP) geologic repository in southeast New Mexico. Three alternatives which could cost effectively be applied to certify Hanford CH-TRU waste to the WIPP Waste Acceptance Criteria (WIPP-WAC) have been examined in this updated engineering study. The alternatives differed primarily in the reference processing systems used to transform nonconforming waste into an acceptable, certified waste form. It is recommended to include the alternative of shredding and immobilizing nonconforming wastes in cement (shred/grout processing) in the WRAP facility. Preliminary capital costs for WRAP in mid-point-of-construction (FY 1991) dollars were estimated at $45 million for new construction and $37 million for modification and installation in an existing Hanford surplus facility (231-Z Building). Operating, shipping, and decommissioning costs in FY 1986 dollars were estimated at $126 million, based on a 23-y WRAP life cycle (1994 to 2017). During this period, the WRAP facility will receive an estimated 38,000 m 3 (1.3 million ft 3 ) of solid CH-TRU waste. The study recommends pilot-scale testing and evaluation of the processing systems planned for WRAP and advises further investigation of the 231-Z Building as an alternative to new facility construction

  9. Participation of civil engineers in designing facilities in rock salt

    International Nuclear Information System (INIS)

    Duddeck, H.; Westhaus, T.

    1990-01-01

    For the design of underground facilities in rock salt layers or domes, as caverns for repositories, the civil engineering approach may be useful. The underground openings are analysed by determining the displacements and the stresses for actual states and hypothetical situations. The paper reports on the state of art in the development of suited time dependent material laws for rock salt, on time integration methods for the analysis, and on a possible procedure for a consistent safety analysis. The examples given include caverns filled by oil, analysis of a mine with vertical excavation chambers, and dams closing mine galleries. (orig.) [de

  10. Human factors engineering report for the cold vacuum drying facility

    Energy Technology Data Exchange (ETDEWEB)

    IMKER, F.W.

    1999-06-30

    The purpose of this report is to present the results and findings of the final Human Factors Engineering (HFE) technical analysis and evaluation of the Cold Vacuum Drying Facility (CVDF). Ergonomics issues are also addressed in this report, as appropriate. This report follows up and completes the preliminary work accomplished and reported by the Preliminary HFE Analysis report (SNF-2825, Spent Nuclear Fuel Project Cold Vacuum Drying Facility Human Factors Engineering Analysis: Results and Findings). This analysis avoids redundancy of effort except for ensuring that previously recommended HFE design changes have not affected other parts of the system. Changes in one part of the system may affect other parts of the system where those changes were not applied. The final HFE analysis and evaluation of the CVDF human-machine interactions (HMI) was expanded to include: the physical work environment, human-computer interface (HCI) including workstation and software, operator tasks, tools, maintainability, communications, staffing, training, and the overall ability of humans to accomplish their responsibilities, as appropriate. Key focal areas for this report are the process bay operations, process water conditioning (PWC) skid, tank room, and Central Control Room operations. These key areas contain the system safety-class components and are the foundation for the human factors design basis of the CVDF.

  11. Design and study of Engineering Test Facility - Helium Circulator

    International Nuclear Information System (INIS)

    Jiang Huijing; Ye Ping; Zhao Gang; Geng Yinan; Wang Jie

    2015-01-01

    Helium circulator is one of the key equipment of High-temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM). In order to simulate most normal and accident operating conditions of helium circulator in HTR-PM, a full scale, rated flow rate and power, engineering test loop, which was called Engineering Test Facility - Helium Circulator (ETF-HC), was designed and established. Two prototypes of helium circulator, which was supported by Active Magnetic Bearing (AMB) or sealed by dry gas seals, would be tested on ETF-HC. Therefore, special interchangeable design was under consideration. ETF-HC was constructed compactly, which consisted of eleven sub-systems. In order to reduce the flow resistance of the circuit, special ducts, elbows, valves and flowmeters were selected. Two stages of heat exchange loops were designed and a helium - high pressure pure water heat exchanger was applied to ensure water wouldn't be vaporized while simulating accident conditions. Commissioning tests were carried out and operation results showed that ETF-HC meets the requirement of helium circulator operation. On this test facility, different kinds of experiments were supposed to be held, including mechanical and aerodynamic performance tests, durability tests and so on. These tests would provide the features and performance of helium circulator and verify its feasibility, availability and reliability. (author)

  12. Human factors engineering report for the cold vacuum drying facility

    International Nuclear Information System (INIS)

    IMKER, F.W.

    1999-01-01

    The purpose of this report is to present the results and findings of the final Human Factors Engineering (HFE) technical analysis and evaluation of the Cold Vacuum Drying Facility (CVDF). Ergonomics issues are also addressed in this report, as appropriate. This report follows up and completes the preliminary work accomplished and reported by the Preliminary HFE Analysis report (SNF-2825, Spent Nuclear Fuel Project Cold Vacuum Drying Facility Human Factors Engineering Analysis: Results and Findings). This analysis avoids redundancy of effort except for ensuring that previously recommended HFE design changes have not affected other parts of the system. Changes in one part of the system may affect other parts of the system where those changes were not applied. The final HFE analysis and evaluation of the CVDF human-machine interactions (HMI) was expanded to include: the physical work environment, human-computer interface (HCI) including workstation and software, operator tasks, tools, maintainability, communications, staffing, training, and the overall ability of humans to accomplish their responsibilities, as appropriate. Key focal areas for this report are the process bay operations, process water conditioning (PWC) skid, tank room, and Central Control Room operations. These key areas contain the system safety-class components and are the foundation for the human factors design basis of the CVDF

  13. Annual report of the CTR Blanket Engineering research facility in 1996

    International Nuclear Information System (INIS)

    1998-02-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor (CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1996. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (J.P.N.)

  14. Annual report of the CTR Blanket Engineering research facility in 1992

    International Nuclear Information System (INIS)

    1993-08-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor (CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1992. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (J.P.N.)

  15. Annual report of the CTR Blanket Engineering research facility in 1994

    International Nuclear Information System (INIS)

    1995-09-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor(CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1994. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (author)

  16. Annual report of the CTR blanket engineering research facility in 1993

    International Nuclear Information System (INIS)

    1994-08-01

    This is an annual report of the studies on Controlled Thermo-nuclear Reactor (CTR) Blanket Engineering which have been carried out in the Faculty of Engineering, the University of Tokyo, in FY 1993. This research facility on the CTR Blanket Engineering is located in the Nuclear Engineering Research Laboratory, the Tokai-mura branch of the Faculty of Engineering. (author)

  17. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 4: Supplementary engineering data

    Science.gov (United States)

    1981-01-01

    The reference conceptual design of the Magnetohydrodynamic Engineering Test Facility (ETF), a prototype 200 MWe coal-fired electric generating plant designed to demonstrate the commercial feasibility of open cycle MHD is summarized. Main elements of the design are identified and explained, and the rationale behind them is reviewed. Major systems and plant facilities are listed and discussed. Construction cost and schedule estimates, and identification of engineering issues that should be reexamined are also given. The latest (1980-1981) information from the MHD technology program are integrated with the elements of a conventional steam power electric generating plant. Supplementary Engineering Data (Issues, Background, Performance Assurance Plan, Design Details, System Design Descriptions and Related Drawings) is presented.

  18. Physics and engineering assessments of spherical torus component test facility

    International Nuclear Information System (INIS)

    Peng, Y.-K.M.; Neumeyer, C.A.; Kessel, C.; Rutherford, P.; Mikkelsen, D.; Bell, R.; Menard, J.; Gates, D.; Schmidt, J.; Synakowski, E.; Grisham, L.; Fogarty, P.J.; Strickler, D.J.; Burgess, T.W.; Tsai, J.; Nelson, B.E.; Sabbagh, S.; Mitarai, O.; Cheng, E.T.; El-Guebaly, L.

    2005-01-01

    A broadly based study of the fusion engineering and plasma science conditions of a Component Test Facility (CTF), using the Spherical Torus or Spherical Tokamak (ST) configuration, have been carried out. The chamber systems testing conditions in a CTF are characterized by high fusion neutron fluxes Γ n > 4.4x10 13 n/s/cm 2 , over size scales > 10 5 cm 2 and depth scales > 50 cm, delivering > 3 accumulated displacement per atom (dpa) per year. The desired chamber conditions can be provided by a CTF with R 0 1.2 m, A = 1.5, elongation ∼ 3.2, I p ∼ 9 MA, B T ∼ 2.5 T, producing a driven fusion burn using 36 MW of combined neutral beam and RF power. Relatively robust ST plasma conditions are adequate, which have been shown achievable [4] without active feedback manipulation of the MHD modes. The ST CTF will test the single-turn, copper alloy center leg for the toroidal field coil without an induction solenoid and neutron shielding, and require physics data on solenoid-free plasma current initiation, ramp-up, and sustainment to multiple MA level. A new systems code that combines the key required plasma and engineering science conditions of CTF has been prepared and utilized as part of this study. The results show high potential for a family of lowercost CTF devices to suit a variety of fusion engineering science test missions. (author)

  19. Command World

    National Research Council Canada - National Science Library

    Wong, Leah Y; Lange, Douglas S; Sebastyn, Jerome T; Roof, William H

    2006-01-01

    .... The Command World scenario was expressly designed as a crisis action planning exercise in order to replicate the communications, collaboration, and information requirements inherent in a military...

  20. Magnetotelluric soundings on the Idaho National Engineering Laboratory facility, Idaho

    International Nuclear Information System (INIS)

    Stanley, W.D.

    1982-01-01

    The magnetotelluric (MT) method was used as one of several geophysical tools to study part of the Idaho Engineering Laboratory (INEL) facility. The purpose of the geophysical study on INEL was to investigate the facility for a possible site to drill a geothermal exploration well. The initial interpretation of the MT sounding data was done with one-dimensional models consisting of four or five layers, the minimum number required to fit the data. After the test well (INEL-1) was completed, the electric log was used to guide an improved one-dimensional ID interpretation of the MT sounding data. Profile models derived from the well log provided good agreement with velocity models derived from refraction seismic data. A resolution study using generalized inverse techniques shows that the resolution of resistive layers in the lower part of the MT models is poor, as is the definition of a shallow, altered basalt unit. The only major structure observed on the MT data was the faulted contact between the SNRP and basin and range structures on the west. Modeling of the data near this structure with a two-dimensional computer program showed that the MT data near the fault require a model similar to the seismic refraction models and that structure on a deep crustal conductor is also required

  1. Trends of researches for fusion engineering research facility (FERF)

    International Nuclear Information System (INIS)

    Ozawa, Yasutomo; Enoto, Takeaki

    1975-01-01

    The role of a fusion neutron radiation test facility in the development of a scientific feasibility experimental reactor or demonstration fusion power reactor plant would be analogous to the role of the materials testing and experimental reactors in the development of fission power reactor. While the material testing fission reactor has been developed after successful operation of fission reactors, in the case of fusion reactor development it is desirable to realize the fusion engineering research facility (FERF) in-phase to the development of SFX and/or demonstration fusion power reactor plants. Here so called FERF in near future is the Controlled Thermonuclear Reactor which provides the high-intensity and high-energy neutron and plasma source whether the net power output is produced or not. From the point of direct attainment to SFX, we would like to emphasize that FEFE is the royal road leading to the goal of successful achievement of CTR program and could be useful for the experiment on impurity effects caused by neutron and plasma irradiations onto the wall material for SFX. Further, we rather suppose that hybrid FERF-fission assembly could be fairly and easily realizable in near future. (auth.)

  2. The FENIX [Fusion ENgineering International EXperimental] test facility

    International Nuclear Information System (INIS)

    Slack, D.S.; Patrick, R.E.; Chaplin, M.R.; Miller, J.R.; Shen, S.S.; Summers, L.T.; Kerns, J.A.

    1989-01-01

    The Fusion ENgineering International EXperimental Magnet Facility (FENIX), under construction at Lawrence Livermore National Laboratory (LLNL), is a significant step forward in meeting the testing requirements necessary for the development of superconductor for large-scale, superconducting magnets. A 14-T, transverse field over a test volume of 150 x 60 x 150 mm in length will be capable of testing conductors the size of the International Thermonuclear Experimental Reactor (ITER). Proposed conductors for ITER measure ∼35 mm on one side and will operate at currents of up to 40 kA at fields of ∼14 T. The testing of conductors and associated components, such as joints, will require large-bore, high-field magnet facilities. FENIX is being constructed using the existing A 2o and A 2i magnets from the idle MFTF. The east and west A 2 pairs will be mounted together to form a split-pair solenoid. The pairs of magnets will be installed in a 4.0-m cryostat vessel located in the HFTF building at LLNL. Each magnet is enclosed in its own cryostat, the existing 4.0-m vessel serving only as a vacuum chamber. 4 refs., 8 figs

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

    National Research Council Canada - National Science Library

    Garcia, Hector

    2000-01-01

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

  4. Knowledge Management tools integration within DLR's concurrent engineering facility

    Science.gov (United States)

    Lopez, R. P.; Soragavi, G.; Deshmukh, M.; Ludtke, D.

    The complexity of space endeavors has increased the need for Knowledge Management (KM) tools. The concept of KM involves not only the electronic storage of knowledge, but also the process of making this knowledge available, reusable and traceable. Establishing a KM concept within the Concurrent Engineering Facility (CEF) has been a research topic of the German Aerospace Centre (DLR). This paper presents the current KM tools of the CEF: the Software Platform for Organizing and Capturing Knowledge (S.P.O.C.K.), the data model Virtual Satellite (VirSat), and the Simulation Model Library (SimMoLib), and how their usage improved the Concurrent Engineering (CE) process. This paper also exposes the lessons learned from the introduction of KM practices into the CEF and elaborates a roadmap for the further development of KM in CE activities at DLR. The results of the application of the Knowledge Management tools have shown the potential of merging the three software platforms with their functionalities, as the next step towards the fully integration of KM practices into the CE process. VirSat will stay as the main software platform used within a CE study, and S.P.O.C.K. and SimMoLib will be integrated into VirSat. These tools will support the data model as a reference and documentation source, and as an access to simulation and calculation models. The use of KM tools in the CEF aims to become a basic practice during the CE process. The settlement of this practice will result in a much more extended knowledge and experience exchange within the Concurrent Engineering environment and, consequently, the outcome of the studies will comprise higher quality in the design of space systems.

  5. Physical and engineering aspects of a fusion engineering test facility based on mirror confinement

    International Nuclear Information System (INIS)

    Kawabe, T.; Hirayama, S.; Hojo, H.; Kozaki, Y.; Yoshikawa, K.

    1986-01-01

    Controlled fusion research has accomplished great progress in the field of confinement of high-density and high-temperature plasmas and breakeven experiments are expected before the end of the 1980s. Many experiments have been proposed as the next step for fusion research. Among them is the study of ignited plasmas and another is the study of fusion engineering. Some of the important studies in fusion engineering are the integrated test in a fusion reactor environment as well as tests of first-wall materials and of the reactor structures, and test for tritium breeding and blanket modules or submodules. An ideal neutron source for the study of fusion engineering is the deuterium-tritium (D-T) fusion plasma itself. A neutron facility based on a D-T-burning plasma consists of all of the components that a real fusion power reactor would have, so eventually the integrated test for fusion reactor engineering can be done as well as the tests for each engineering component

  6. High temperature engineering research facilities and experiments in Russia

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  7. The RCF [Rock Characterisation Facility]: engineering issues. Proof of evidence

    International Nuclear Information System (INIS)

    Allison, J.A.

    1996-01-01

    Proof of Evidence by an expert witness is presented in support of the case by Friends of the Earth (FOE) against the proposed construction by UK Nirex Ltd of an underground Rock Characterisation Facility (RCF) at a site in the Sellafield area. The RCF is part of an investigation by Nirex into a suitable site for an underground repository for the disposal of radioactive waste. The objections were raised at a Planning Inquiry in 1995. The evidence focuses on the engineering issues in key areas of uncertainty which Nirex claim can only be resolved through the construction of an RCF. These are: groundwater flow and radionuclide transport; natural and induced changes in the geological barrier; the design and construction of the repository. Particular attention is drawn to the uncertainties regarding the groundwater pathway due to the dominant influence of fractures and variability in the host rock. Significant uncertainties about the host rock performance will remain after the construction of the RCF and associated tests are complete. (5 figures; 28 references). (UK)

  8. Description of an engineering-scale facility for uranium fluorination studies

    International Nuclear Information System (INIS)

    Yagi, Eiji; Saito, Shinichi; Horiuchi, Masato

    1976-03-01

    In the research program of power reactor fuel reprocessing by fluoride volatility process, the engineering facility was constructed to establish the techniques of handling kilogram quantities of fluorine and uranium hexafluoride and to obtain engineering data on the uranium fluidized-bed oxidation and fluorination. This facility is designed for a capacity of 5 kg per batch. Descriptions on the facility and equipment are given, including design philosophy, safety and its analysis. (auth.)

  9. Facility Reliability and Maintainability: An Investigation of the Air Force Civil Engineering Recurring Work Program

    Science.gov (United States)

    1989-09-01

    18:2). A recent survey by the Strategic Air Command (SAC) Mechanical Fquipment Management Evaluation Team ( MEMET ) determined that equipment was...identified by MEMET included Maintenance Action Sheets (MAS) that reported work which was not completed, and other MAS which annotated recurring work...readily apparent. Problem Military. The Deputy Chief of Staff for Engineering and Services, HQ SAC, established the MEMET in 1984 in response to a

  10. Current Status and Issues of Nuclear Engineering Research and Educational Facilities in Universities

    International Nuclear Information System (INIS)

    2004-01-01

    It is important to discuss about nuclear engineering research and educational facilities in universities after new educational foundation. 12 universities investigated issues and a countermeasure of them. The results of a questionnaire survey, issues and countermeasure are shown in this paper. The questionnaire on the future nuclear researches, development of education, project, maintenance of nuclear and radioactive facilities and accelerator, control of uranium in subcritical test facilities, use of new corporation facilities, the fixed number of student, number of graduate, student experiments, themes of experiments and researches, the state of educational facilities are carried out. The results of questionnaire were summarized as followings: the fixed number of student (B/M/D) on nuclear engineering, exercise of reactor, education, themes, educational and research facilities, significance of nuclear engineering education in university and proposal. (S.Y.)

  11. 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.

  12. Model-based system-of-systems engineering for space-based command, control, communication, and information architecture design

    Science.gov (United States)

    Sindiy, Oleg V.

    This dissertation presents a model-based system-of-systems engineering (SoSE) approach as a design philosophy for architecting in system-of-systems (SoS) problems. SoS refers to a special class of systems in which numerous systems with operational and managerial independence interact to generate new capabilities that satisfy societal needs. Design decisions are more complicated in a SoS setting. A revised Process Model for SoSE is presented to support three phases in SoS architecting: defining the scope of the design problem, abstracting key descriptors and their interrelations in a conceptual model, and implementing computer-based simulations for architectural analyses. The Process Model enables improved decision support considering multiple SoS features and develops computational models capable of highlighting configurations of organizational, policy, financial, operational, and/or technical features. Further, processes for verification and validation of SoS models and simulations are also important due to potential impact on critical decision-making and, thus, are addressed. Two research questions frame the research efforts described in this dissertation. The first concerns how the four key sources of SoS complexity---heterogeneity of systems, connectivity structure, multi-layer interactions, and the evolutionary nature---influence the formulation of SoS models and simulations, trade space, and solution performance and structure evaluation metrics. The second question pertains to the implementation of SoSE architecting processes to inform decision-making for a subset of SoS problems concerning the design of information exchange services in space-based operations domain. These questions motivate and guide the dissertation's contributions. A formal methodology for drawing relationships within a multi-dimensional trade space, forming simulation case studies from applications of candidate architecture solutions to a campaign of notional mission use cases, and

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

    International Nuclear Information System (INIS)

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

    1976-08-01

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

  14. Value Engineering. "A Working Tool for Cost Control in the Design of Educational Facilities."

    Science.gov (United States)

    Lawrence, Jerry

    Value Engineering (VE) is a cost optimizing technique used to analyze design quality and cost-effectiveness. The application of VE procedures to the design and construction of school facilities has been adopted by the state of Washington. By using VE, the optimum value for every life cycle dollar spent on a facility is obtained by identifying not…

  15. Engineering design of the Nova Laser Facility for inertial-confinement fusion

    International Nuclear Information System (INIS)

    Simmons, W.W.; Godwin, R.O.; Hurley, C.A.

    1982-01-01

    The design of the Nova Laser Facility for inertial confinement fusion experiments at Lawrence Livermore National Laboratory is presented from an engineering perspective. Emphasis is placed upon design-to-performance requirements as they impact the various subsystems that comprise this complex experimental facility

  16. Engineered Barrier Testing at the INEEL Engineered Barriers Test Facility: FY-1997 and FY-1998

    International Nuclear Information System (INIS)

    Keck, K. N.; Porro, I.

    1998-01-01

    Engineered barriers of two designs are being tested at the Engineered Barriers Test Facility (EBTF) at the Idaho National Engineering and Environmental Laboratory. This report describes the test facility, barrier designs, and instruments used to monitor the test plots. Wetting tests conducted on the test plots in FY-97 are described and data collected from monitoring the test plots before, during and after the wetting tests are used to evaluate the performance of the covers during FY-97 and FY-98. Replicates of two engineered barrier designs were constructed in the EBTF cells. The first design comprises a thick, vegetated soil cover. The second design incorporates a capillary/biobarrier within the vegtated soil cover. The capillary barrier uses the textural break between an upper, fine textured soil and a lower, coarser-textured gravel layer to inhibit drainage under unsaturated conditions while increasing soil moisture storage in the root zone. Evaporation and transpiration by plants (although the test plots have not yet been vegetated) are used to recycle water stored in the soil back to the atmosphere. A geotextile fabric is used to maintain separation of the soil and gravel layers. A thick layer of cobbles beneath the gravel layer serves as a biobarrier to prevent intrusion of plant roots and burrowing animals into underlying waste (there is no waste in the test plots). Each test plot was instrumented with time domain reflectometry probes and neutron probe access tubes to measure moisture contents, tensiometers, heat dissipation sensors, and thermocouple psychrometers to measure matric potentials, thermocouples to measure soil temperature, and ion-exchange resin beads to monitor tracer movement. Each drainage sump is equipped with a tipping bucket instrument and pressure transducer to measure drainage. Precipitation is measured using a heated rain gauge located at the EBTF. Instrument calibration equation coefficients are presented, and data reduction

  17. Los Alamos Experimental Engineering Waste Burial Facility: design considerations and preliminary experimental plan

    International Nuclear Information System (INIS)

    DePoorter, G.L.

    1981-01-01

    The Experimental Engineered Waste Burial Facility is a field test site where generic experiments can be performed on several scales to get the basic information necessary to understand the processes occurring in low-level waste disposal facilities. The experiments include hydrological, chemical, mechanical, and biological factors. In order to separate these various factors in the experiments and to extrapolate the experimental results to actual facilities, experiments will be performed on several different scales

  18. UFISA: electric facility engineering for the service of emergy market

    International Nuclear Information System (INIS)

    Gutierrez Zapico, A.

    1997-01-01

    UFISA is the engineering company with the experience of UNION ELECTRICA FENOSA S.A. It activity began in 1990. This company offers to national and international markets the services for energy consumers and for the electricity costumers. (Author)

  19. Ground test facilities for evaluating nuclear thermal propulsion engines and fuel elements

    International Nuclear Information System (INIS)

    Allen, G.C.; Beck, D.F.; Harmon, C.D.; Shipers, L.R.

    1992-01-01

    Interagency panels evaluating nuclear thermal propulsion development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and design issues of a proposed ground test complex for evaluating nuclear thermal propulsion engines and fuel elements being developed for the Space Nuclear Thermal Propulsion (SNTP) program. 2 refs

  20. Engine testing the design, building, modification and use of powertrain test facilities

    CERN Document Server

    MARTYR, A J

    2012-01-01

    Engine Testing is a unique, well-organized and comprehensive collection of the different aspects of engine and vehicle testing equipment and infrastructure for anyone involved in facility design and management, physical testing and the maintenance, upgrading and trouble shooting of testing equipment. Designed so that its chapters can all stand alone to be read in sequence or out of order as needed, Engine Testing is also an ideal resource for automotive engineers required to perform testing functions whose jobs do not involve engine testing on a regular basis. This recognized standard refer

  1. Engineering study: Fast Flux Test Facility fuel reprocessing

    International Nuclear Information System (INIS)

    Beary, M.M.; Raab, G.J.; Reynolds, W.R. Jr.; Yoder, R.A.

    1974-01-01

    Several alternatives were studied for reprocessing FFTF fuels at Hanford. Alternative I would be to decontaminate and trim the fuel at T Plant and electrolytically dissolve the fuel at Purex. Alternative II would be to decontaminate and shear leach the fuels in a new facility near Purex. Alternative III would be to decontaminate and store fuel elements indefinitely at T Plant for subsequent offsite shipment. Alternative I, 8 to 10 M$ and 13 quarter-years; for Alternative II, 24 to 28 M$ and 20 quarter-years; for Alternative III, 3 to 4 M$ and 8 quarter-years. Unless there is considerable slippage in the FFTF shipping schedule, it would not be possible to build a new facility as described in Alternative II in time without building temporary storage facilities at T Plant, as described in Alternative III

  2. Science and Engineering Research Council Central Laser Facility

    International Nuclear Information System (INIS)

    1981-03-01

    This report covers the work done at, or in association with, the Central Laser Facility during the year April 1980 to March 1981. In the first chapter the major reconstruction and upgrade of the glass laser, which has been undertaken in order to increase the versatility of the facility, is described. The work of the six groups of the Glass Laser Scientific Progamme and Scheduling Committee is described in further chapters entitled; glass laser development, laser plasma interactions, transport and particle emission studies, ablative acceleration and compression studies, spectroscopy and XUV lasers, and theory and computation. Publications based on the work of the facility which have either appeared or been accepted for publication during the year are listed. (U.K.)

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  4. Command in a field hospital.

    Science.gov (United States)

    Bricknell, M C M

    2003-03-01

    This paper examines the challenges involved in commanding a field hospital. There are frequent, dynamic tensions between the military culture that is based on a task-focussed, hierarchical structure and the clinical culture that is based on flat, process-focussed, multidisciplinary teams. The paper outlines the cultural environment of the field hospital and then examines the deployment sequence whereby a functioning clinical facility may be created from a group of disparate individuals. There are a number of tools that may assist with this including the personality of the Commanding Officer, individual skills, the creation of an organizational identity and the choice of command structure.

  5. LASL experimental engineered waste burial facility: design considerations and preliminary plan

    International Nuclear Information System (INIS)

    DePoorter, G.L.

    1980-01-01

    The LASL Experimental Engineered Waste Burial Facility is a part of the National Low-Level Waste Management Program on Shallow-Land Burial Technology. It is a test facility where basic information can be obtained on the processes that occur in shallow-land burial operations and where new concepts for shallow-land burial can be tested on an accelerated basis on an appropriate scale. The purpose of this paper is to present some of the factors considered in the design of the facility and to present a preliminary description of the experiments that are initially planned. This will be done by discussing waste management philosophies, the purposes of the facility in the context of the waste management philosophy for the facility, and the design considerations, and by describing the experiments initially planned for inclusion in the facility, and the facility site

  6. French en engineering and operation rules for plutonium facilities

    International Nuclear Information System (INIS)

    Bertolotti, G.; Drain, F.; Dubois, G.; Monnatte, J.; Mathieu, P.

    1998-01-01

    COGEMA is operating large size purifying and conditioning plutonium facilities at LA HAGUE and MOX fuels fabrication plant at Marcoule. A high safety standard is recognised for these facilities. It is mainly based on : - prevention of spreading of radioactive materials to workers and environment by physical barriers ensuring static containment and by a cascade of pressure differentials ensuring dynamic containment, - radiation shielding and remote controlled processes ensuring very low dose to workers, - prevention of criticality accident by criticality control methods and double contingency principle, - prevention of fire risks by control of ignition sources, adequate management of combustible materials, physical separation between zones where there is a risk of fire and the remainder of the facility. The facilities are operated while respecting safety requirements as described in the General Operating Rules. The equipment involved in safety functions are monitored and periodically checked. Continuous improvement by incorporation of feed back of safety experience results in: - effective decrease of exposure to operating staff; - reduction of solid waste, liquid and gaseous effluents; - no significant incident recorded. (author)

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

    International Nuclear Information System (INIS)

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

    2003-09-01

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

  8. Conference on the research facilities for future nuclear power engineering

    International Nuclear Information System (INIS)

    Arkhangel'skij, N.V.

    1996-01-01

    The activity of the European nuclear society Conference (Belgium, June, 1996) is described. The main topics of 60 presented reports are the following ones: necessity of developing new experimental facilities and their parameters; financing prospects and international cooperation in this field

  9. Apollo 11 Command Service Module

    Science.gov (United States)

    1969-01-01

    A close-up view of the Apollo 11 command service module ready to be mated with the spacecraft LEM adapter of the third stage. The towering 363-foot Saturn V was a multi-stage, multi-engine launch vehicle standing taller than the Statue of Liberty. Altogether, the Saturn V engines produced as much power as 85 Hoover Dams.

  10. ARM Operations and Engineering Procedure Mobile Facility Site Startup

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, Jimmy W

    2015-05-01

    This procedure exists to define the key milestones, necessary steps, and process rules required to commission and operate an Atmospheric Radiation Measurement (ARM) Mobile Facility (AMF), with a specific focus toward on-time product delivery to the ARM Data Archive. The overall objective is to have the physical infrastructure, networking and communications, and instrument calibration, grooming, and alignment (CG&A) completed with data products available from the ARM Data Archive by the Operational Start Date milestone.

  11. Dismantling of nuclear facilities. From a structural engineering perspective

    International Nuclear Information System (INIS)

    Block, Carsten; Henkel, Fritz-Otto; Bauer, Thomas

    2014-01-01

    The paper summarizes some important aspects, requirements and technical boundary conditions that need to be considered in dismantling projects in the nuclear sector from a structural engineering perspective. Besides general requirements regarding radiation protection, occupational safety, efficiency and cost effectiveness it is important to take into account other conditions which have a direct impact on technical details and the structural assessment of the dismantling project. These are the main aspects highlighted in this paper: - The structural assessment of dismantling projects has to be based on the as-built situation. - The limitations in terms of available equipment and space have to be taken into account. - The structural assessments are often non-standardized engineering evaluations. A selection of five dismantling projects illustrates the various structural aspects. (orig.)

  12. The Battle Command Sustainment Support System: Initial Analysis Report

    Science.gov (United States)

    2016-09-01

    products including jet fuels, distillate fuels, residual fuels, automotive gasoline , specified bulk lubricating oils, aircraft engine oils, fuel...contained within this report. 15. SUBJECT TERMS Mission command Software Tactical applications (TacApps) Command post ...computing environment (CPCE) Command post client Battle command sustainment support System (BCS3) Logistics

  13. High temperature engineering research facilities and experiments in China

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  14. Remote machine engineering applications for nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    Toto, G.; Wyle, H.R.

    1983-01-01

    Decontamination and decommissioning of a nuclear facility require the application of techniques that protect the worker and the enviroment from radiological contamination and radiation. Remotely operated portable robotic arms, machines, and devices can be applied. The use of advanced systems should enhance the productivity, safety, and cost facets of the efforts; remote automatic tooling and systems may be used on any job where job hazard and other factors justify application. Many problems based on costs, enviromental impact, health, waste generation, and political issues may be mitigated by use of remotely operated machines. The work that man can not do or should not do will have to be done by machines

  15. Engineered surface barriers for waste disposal sites: lysimeter facility design and construction

    International Nuclear Information System (INIS)

    Phillips, S.J.; Ruben, M.S.; Kirkham, R.R.

    1988-01-01

    A facility to evaluate performance of engineered surface carriers for confinement of buried wastes has been designed, constructed, and operations initiated. The Field Lysimeter Test Facility is located at the US Department of Energy's Hanford Site in Richland, Washington. The facility consists of 18 one-dimensional drainage and weighing lysimeters used to evaluate 7 replicated barrier treatments. Distinct layers of natural earth materials were used to construct layered soil and rock barriers in each lysimeter. These barrier designs are capable in principal of significantly reducing or precluding infiltration of meteoric water through barriers into underlying contaminated zones. This paper summarizes salient facility design and construction features used in testing of the Hanford Site's engineered surface barriers

  16. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 2: Engineering. Volume 3: Costs and schedules

    Science.gov (United States)

    1981-01-01

    Engineering design details for the principal systems, system operating modes, site facilities, and structures of an engineering test facility (ETF) of a 200 MWE power plant are presented. The ETF resembles a coal-fired steam power plant in many ways. It is analogous to a conventional plant which has had the coal combustor replaced with the MHD power train. Most of the ETF components are conventional. They can, however, be sized or configured differently or perform additional functions from those in a conventional coal power plant. The boiler not only generates steam, but also performs the functions of heating the MHD oxidant, recovering seed, and controlling emissions.

  17. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 2: Engineering. Volume 3: Costs and schedules. Final Report

    International Nuclear Information System (INIS)

    1981-09-01

    Engineering design details for the principal systems, system operating modes, site facilities, and structures of an engineering test facility (ETF) of a 200 MWE power plant are presented. The ETF resembles a coal-fired steam power plant in many ways. It is analogous to a conventional plant which has had the coal combustor replaced with the MHD power train. Most of the ETF components are conventional. They can, however, be sized or configured differently or perform additional functions from those in a conventional coal power plant. The boiler not only generates steam, but also performs the functions of heating the MHD oxidant, recovering seed, and controlling emissions

  18. Temporary septic holding tank at the 100-D remedial action support facility -- Engineering report. Revision 1

    International Nuclear Information System (INIS)

    Kelty, G.G.

    1996-09-01

    This document provides an engineering evaluation for the temporary septic holding tank that will be installed at the 100-D Remedial Action Support Facility at the 100-DR-1 Operable Unit in the Hanford Site. This support facility will be installed at the 100-DR-1 Operable Unit to provide office and work space for the workers involved in remediation activities of the various waste sites located at the Hanford Site

  19. Conceptual design of a mirror reactor for a fusion engineering research facility (FERF)

    International Nuclear Information System (INIS)

    Batzer, T.H.; Burleigh, R.C.; Carlson, G.A.; Dexter, W.L.; Hamilton, G.W.; Harvey, A.R.; Hickman, R.G.; Hoffman, M.A.; Hooper, E.B. Jr.; Moir, R.W.; Nelson, R.L.; Pittenger, L.C.; Smith, B.H.; Taylor, C.E.; Werner, R.W.; Wilcox, T.P.

    1975-01-01

    A conceptual design is presented for a small mirror fusion reactor for a Fusion Engineering Research Facility (FERF). The reactor produces 3.4 MW of fusion power and a useful neutron flux of about 10 14 n.cm -2 .s -1 . Superconducting ''yin-yang'' coils are used, and the plasma is sustained by injection of energetic neutral D 0 and T 0 . Conceptual layouts are given for the reactor, its major components, and supporting facilities. (author)

  20. Human engineering considerations in the design of New Virginia Power Radwaste facilities

    International Nuclear Information System (INIS)

    Bankley, A.V.; Morris, L.L.; Lippard, D.W.

    1988-01-01

    Human engineering principles were considered by Virginia Power in the recent design of new radwaste facilities (NRFs) for both the Surry and North Anna power stations. Virginia Power recognized that the rigorous application of human engineering principles to the NRF design was essential to the ultimate success or failure of the facilities. Success of the NRF should not only be measured in the volume of radwaste processed but also by other factors such as (a) availability and maintainability of preferred equipment, (b) as-low-as-reasonably-achievable considerations, (c) actual release rates versus achievable release rates, and (d) flexibility to deal with varying circumstances. Each of these success criteria would suffer as the result of operator/human inefficiencies or error. Therefore, human engineering should be applied to the maximum practical extent to minimize such inefficiencies or errors. No method is ever going to ensure a perfectly human-engineered facility design. Virginia Power believes, however, that significant strides have been made in efforts to design and construct a successful radwaste processing facility, a facility where operating success rests with the ability of the human operators to perform their jobs in an efficient and reliable fashion

  1. F/H Effluent Treatment Facility. Preliminary engineering report

    International Nuclear Information System (INIS)

    1985-01-01

    The Department of Energy is currently proposing to construct the F/H ETF to process wastewater from the Separations Areas and replace the existing seepage basins. Reasons for seepage basin closure are two-fold. First, nonradioactive hazardous materials routinely discharged to the seepage basins may have adversely impacted the quality of the groundwater in the vicinity of the basins. Second, amendments to the Resource Conservation and Recovery Act (RCRA) were approved in 1984, prohibiting the discharge of hazardous wastes to unlined seepage basins after November, 1988. The F/H ETF will consist of wastewater storage facilities and a treatment plant discharging treated effluent to Upper Three Runs Creek. Seepage basin use in F and H Areas wil be discontinued after startup, allowing timely closure of these basins. 3 refs

  2. Engineering evaluation/cost analysis for the 105-DR and 105-F Reactor facilities and ancillary facilities

    International Nuclear Information System (INIS)

    Coenenberg, E.T.

    1998-01-01

    This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives to address final disposition of the 105-DR and 105-F Reactor Buildings (subsequently referred to as facilities), including the fuel storage basins (FSB) and below-grade portions of the reactors, excluding the reactor blocks. The reactor blocks will remain in a safe storage mode for up to 75 years as identified in the Record the Decision (ROD) (58 FR 48509) for the Environmental Impact Statement (EIS), Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington (DOE 1992a). This EE/CA also addresses final disposition of four ancillary facilities: 116-D and 116-DR Exhaust Air Stacks, 117-DR Exhaust Filter Building, and 119-DR Exhaust Air Sample Building. The 105-DR and 105-F facilities are located in the 100-D and 100-F Areas of the Hanford Site. In November 1989, the 100 Area of the Hanford Site was placed on the U.S. Environmental Protection Agency's (EPA) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The 100 Area NPL includes the 100-D Area (which includes the 100-DR site) and the 100-F Area, which are in various stages of the remediation process. It has been determined by DOE that hazardous substances in the 105-DR, 105-F, and the four ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, DOE, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the 105-DR and 105-F facilities and the four ancillary facilities. The 116-DR and 117-DR facilities are located within the boundaries of the 105-DR Large Sodium Fire Facility Treatment, Storage, and Disposal (TSD) unit, which is

  3. Risk assessment for civil engineering facilities: critical overview and discussion

    International Nuclear Information System (INIS)

    Faber, M.H.; Stewart, M.G.

    2003-01-01

    The present paper should be seen as a basis for discussion of important aspects of risk analysis and assessment, as well as attempting to describe risk assessment in accordance with the present state of the art. Risk assessment is thus presented in an overview form from the viewpoint of being a means for decision-making and thus within the formal framework of decision theory. First the motivation for risk analysis is given and the theoretical basis together with the practical aspects, methodologies and techniques for the implementation of risk assessment in civil engineering applications are explained and discussed. The paper furthermore addresses the problems associated with risk acceptance criteria, risk aversion and value of human life and attempts to provide suggestions for the rational treatment of these aspects. Finally a number of problem areas are highlighted and the needs for further education, research and dissemination are stressed

  4. Command History, 1993.

    Science.gov (United States)

    1994-04-01

    his space capsule. The ()CUILAR COtJNTI:,RROI,.L I)FVICI" was built by the Naval Air Rework Facility, NAS Pensacola. tfor NAMRI, in the early 1960s...Dunwoody, GA Kevin G. Singleton, ENS USNR Naval Aviation Schools Command Kyle W M. Taylor, ENS USNR U.S. Naval Academy Jason A. Temple, ENS USNR Auburn...Pensacola, 13-15 Oct 93. Pokorski, T.L., LICDR MSC USN, attended Aircrew Modified IEquipment for Ladies in Aviation (AMELIA) Fri -service Long-range Planning

  5. Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase

    Energy Technology Data Exchange (ETDEWEB)

    Bargalló, Enric, E-mail: enric.bargallo@esss.se [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Arroyo, Jose Manuel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain); Abal, Javier; Dies, Javier; De Blas, Alfredo; Tapia, Carlos [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Moya, Joaquin; Ibarra, Angel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain)

    2015-10-15

    Highlights: • RAMI methodology used for IFMIF accelerator facility is presented. • Availability analyses and results are shown. • Main accelerator design changes are proposed. • Consequences and conclusions of the RAMI analyses are described. - Abstract: This paper presents a summary of the RAMI (Reliability Availability Maintainability Inspectability) analyses done for the IFMIF (International Fusion Materials Irradiation Facility) Accelerator facility in the Engineering Design Phase. The methodology followed, the analyses performed, the results obtained and the conclusions drawn are described. Moreover, the consequences of the incorporation of the RAMI studies in the IFMIF design are presented and the main outcomes of these analyses are shown.

  6. Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase

    International Nuclear Information System (INIS)

    Bargalló, Enric; Arroyo, Jose Manuel; Abal, Javier; Dies, Javier; De Blas, Alfredo; Tapia, Carlos; Moya, Joaquin; Ibarra, Angel

    2015-01-01

    Highlights: • RAMI methodology used for IFMIF accelerator facility is presented. • Availability analyses and results are shown. • Main accelerator design changes are proposed. • Consequences and conclusions of the RAMI analyses are described. - Abstract: This paper presents a summary of the RAMI (Reliability Availability Maintainability Inspectability) analyses done for the IFMIF (International Fusion Materials Irradiation Facility) Accelerator facility in the Engineering Design Phase. The methodology followed, the analyses performed, the results obtained and the conclusions drawn are described. Moreover, the consequences of the incorporation of the RAMI studies in the IFMIF design are presented and the main outcomes of these analyses are shown.

  7. A study on the direct use of spent PWR fuel in CANDU reactors. DUPIC facility engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Soo; Lee, Jae Sul; Choi, Jong Won [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    This report summarizes the second year progress of phase II of DUPIC program which aims to verify experimentally the feasibility of direct use of spent PWR fuel in CANDU reactors. The project is to provide the experimental facilities and technologies that are required to perform the DUPIC experiment. As an early part of the project, engineering analysis of those facilities and construction of mock-up facility are described. Another scope of the project is to assess the DUPIC fuel cycle system and facilitate international cooperation. The progresses in this scope of work made during the fiscal year are also summarized in the report. 38 figs, 44 tabs, 8 refs. (Author).

  8. Tissue Engineering of Cartilage on Ground-Based Facilities

    Science.gov (United States)

    Aleshcheva, Ganna; Bauer, Johann; Hemmersbach, Ruth; Egli, Marcel; Wehland, Markus; Grimm, Daniela

    2016-06-01

    Investigations under simulated microgravity offer the opportunity for a better understanding of the influence of altered gravity on cells and the scaffold-free three-dimensional (3D) tissue formation. To investigate the short-term influence, human chondrocytes were cultivated for 2 h, 4 h, 16 h, and 24 h on a 2D Fast-Rotating Clinostat (FRC) in DMEM/F-12 medium supplemented with 10 % FCS. We detected holes in the vimentin network, perinuclear accumulations of vimentin after 2 h, and changes in the chondrocytes shape visualised by F-actin staining after 4 h of FRC-exposure. Scaffold-free cultivation of chondrocytes for 7 d on the Random Positioning Machine (RPM), the FRC and the Rotating Wall Vessel (RWV) resulted in spheroid formation, a phenomenon already known from spaceflight experiments with chondrocytes (MIR Space Station) and thyroid cancer cells (SimBox/Shenzhou-8 space mission). The experiments enabled by the ESA-CORA-GBF programme gave us an optimal opportunity to study gravity-related cellular processes, validate ground-based facilities for our chosen cell system, and prepare long-term experiments under real microgravity conditions in space

  9. Environmental monitoring for EG and G Idaho facilities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Tkachyk, J.W.; Wright, K.C.; Wilhelmsen, R.N.

    1990-08-01

    This report describes the 1989 environmental-monitoring activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G-operated facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Additional monitoring activities performed by Environmental Monitoring are also discussed, including drinking-water monitoring and nonradiological liquid-effluent monitoring, as well as data management. The primary purposes of monitoring are to evaluate environmental conditions and to provide and interpret data, in compliance with applicable regulations, to ensure protection of human health and the environment. This report compares 1989 environmental-monitoring data with derived concentration guides and with data from previous years. This report also presents results of sampling performed by the Radiological and Environmental Sciences Laboratory and by the United States Geological Survey. 17 refs., 49 figs., 11 tabs

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

    International Nuclear Information System (INIS)

    Liverman, J.L.

    1977-09-01

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

  11. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 1: Executive summary

    Science.gov (United States)

    1981-01-01

    Main elements of the design are identified and explained, and the rationale behind them was reviewed. Major systems and plant facilities are listed and discussed. Construction cost and schedule estimates are presented, and the engineering issues that should be reexamined are identified. The latest (1980-1981) information from the MHD technology program is integrated with the elements of a conventional steam power electric generating plant.

  12. Evaluating physical protection systems of licensed nuclear facilities using systems engineered inspection guidance

    International Nuclear Information System (INIS)

    Bradley, R.T.; Olson, A.W.; Rogue, F.; Scala, S.; Richard, E.W.

    1980-01-01

    The Lawrence Livermore National Laboratory (LLNL) and the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) have applied a systems engineering approach to provide the NRC Office of Inspection and Enforcement (IE) with improved methods and guidance for evaluating the physical protection systems of licensed nuclear facilities

  13. State-of-the-art WEB -technologies and ecological safety of nuclear power engineering facilities

    International Nuclear Information System (INIS)

    Batij, V.G.; Batij, E.V.; Rud'ko, V.M.; Kotlyarov, V.T.

    2004-01-01

    Prospects of web-technologies using in the field of improvement radiation safety level of nuclear power engineering facilities is seen. It is shown that application of such technologies will enable entirely using the data of all information systems of radiation control

  14. Design of an engineered safeguards system for a mixed-oxide fuel fabrication facility

    International Nuclear Information System (INIS)

    Winblad, A.E.; McKnight, R.P.; Fienning, W.C.; Fenchel, B.R.

    1977-06-01

    Several Engineered Safeguards System concepts and designs are described that provide increased protection against a wide spectrum of adversary threats. An adversary sequence diagram that outlines all possible adversary paths through the safeguards elements in a mixed-oxide fuel fabrication facility is shown. An example of a critical adversary path is given

  15. Commanders' Survey: School for Command Preparation Feedback

    National Research Council Canada - National Science Library

    Frame, Adela

    1997-01-01

    .... All command designees attend the PreCommand Course (PCC). PCC provides common understanding of current doctrine, and up-to-date information on Army-wide policy, programs and special items of interest...

  16. Pollution provoquée par le moteur Diesel. Niveaux d'émission. Comparaison avec le moteur à allumage commandé Pollution Caused by Diesel Engines. Emission Levels. Comparison with Spark-Ignition Engines

    Directory of Open Access Journals (Sweden)

    Degobert P.

    2006-11-01

    Full Text Available A partir de l'analyse des différences de modes de combustion allumage commandé et Diesel , cet article compare et explique la nature et les niveaux des différents polluants émis en fonction de leurs mécanismes de formation. Les facteurs d'action au niveau moteur sont examinés, ainsi que l'influence du carburant utilisé. Based on an analysis of the difference between spark-ignition and diesel combustion modes, this article compares and explains the nature and levels of different pollutants emitted as a function of their formation mechanisms. The action factors at the engine> level are examined together with the influence of the fuel used.

  17. Yearbook facility engineering 2009. Facility engineering for electric power grids; Jahrbuch Anlagentechnik 2009. Anlagentechnik fuer elektrische Verteilungsnetze

    Energy Technology Data Exchange (ETDEWEB)

    Cichowski, Rolf Ruediger (ed.)

    2009-07-01

    The strong changes in the energy market - e.g. deregulation, the influence of the Bundesnetzagentur, globalisation of new technologies, constant issueing and adaptation of standards, require more and deeper knowledge than ever before. Issues like energy efficiency and utilisation of renewable energy sources not only govern public discussions but have also created new, variable professions which challenge experts of energy engineering. The yearbook provides an insight into specific issues, e.g. a calendar of events, trade fairs, product recommendations, services, and further hints for practicians. (orig.) [German] Durch die starken Veraenderungen im Energiemarkt, wie die Liberalisierung, die Einflussnahme auf die Gestaltung der Energieversorgung durch die Bundesnetzagentur, die Globalisierung, die neuen Techniken und damit staendige Anpassungen der Normen bzw. Bewaeltigung neuer Normen durch die Fachleute, nimmt die Vielfalt und der Umfang an notwendigen Kenntnissen staendig zu. Themen wie Energieeffizienz und Nutzung regenerativer Energien bestimmen nicht nur die oeffentliche Diskussion, sondern schlagen sich auch in neuen und sich aendernden beruflichen Taetigkeiten nieder. Dadurch sind die Fachleute der Energietechnik ausserordentlich herausgefordert. Zusaetzlich bietet das Jahrbuch spezifische Themen zu den jeweiligen Jahren, wie Kalendarium, Veranstaltungshinweise, Messen, Produktempfehlungen, Dienstleistungen und weitere Tipps fuer Praktiker. (orig.)

  18. A human factors engineering evaluation of the Multi-Function Waste Tank Facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Donohoo, D.T. [Pacific Northwest Lab., Richland, WA (United States); Sarver, T.L. [ARES Corp., San Francisco, CA (United States)

    1995-06-05

    This report documents the methods and results of a human factors engineering (HFE) review conducted on the Multi-Function Waste Tank Facility (MWTF), Westinghouse Hanford Company (WHC) Project 236A, to be constructed at the U.S. Department of Energy (DOE) facility at Hanford, Washington. This HFE analysis of the MWTF was initiated by WHC to assess how well the current facility and equipment design satisfies the needs of its operations and maintenance staff and other potential occupants, and to identify areas of the design that could benefit from improving the human interfaces at the facility. Safe and effective operations, including maintenance, is a primary goal for the MWTF. Realization of this goal requires that the MWTF facility, equipment, and operations be designed in a manner that is consistent with the abilities and limitations of its operating personnel. As a consequence, HFE principles should be applied to the MWTF design, construction, its operating procedures, and its training. The HFE review was focused on the 200-West Area facility as the design is further along than that of the 200-East Area. The review captured, to the greatest extent feasible at this stage of design, all aspects of the facility activities and included the major topics generally associated with HFE (e.g., communication, working environment). Lessons learned from the review of the 200 West facility will be extrapolated to the 200-East Area, as well as generalized to the Hanford Site.

  19. A human factors engineering evaluation of the Multi-Function Waste Tank Facility. Final report

    International Nuclear Information System (INIS)

    Donohoo, D.T.; Sarver, T.L.

    1995-01-01

    This report documents the methods and results of a human factors engineering (HFE) review conducted on the Multi-Function Waste Tank Facility (MWTF), Westinghouse Hanford Company (WHC) Project 236A, to be constructed at the U.S. Department of Energy (DOE) facility at Hanford, Washington. This HFE analysis of the MWTF was initiated by WHC to assess how well the current facility and equipment design satisfies the needs of its operations and maintenance staff and other potential occupants, and to identify areas of the design that could benefit from improving the human interfaces at the facility. Safe and effective operations, including maintenance, is a primary goal for the MWTF. Realization of this goal requires that the MWTF facility, equipment, and operations be designed in a manner that is consistent with the abilities and limitations of its operating personnel. As a consequence, HFE principles should be applied to the MWTF design, construction, its operating procedures, and its training. The HFE review was focused on the 200-West Area facility as the design is further along than that of the 200-East Area. The review captured, to the greatest extent feasible at this stage of design, all aspects of the facility activities and included the major topics generally associated with HFE (e.g., communication, working environment). Lessons learned from the review of the 200 West facility will be extrapolated to the 200-East Area, as well as generalized to the Hanford Site

  20. Engineering evaluation/cost analysis for the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    Rugg, J.E.

    1996-08-01

    The 100, 200, 300 and 1100 Areas of the Hanford Site were placed on the U. S. Environmental Protection Agency's National Priorities List in November 1989 under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Located in the 200 Area is the deactivated 233-S Plutonium Concentration Facility (used in the REDOX process). The facility has undergone severe degradation due to exposure to extreme weather conditions. An expedited response is proposed to ensure protection of human health and the environment. The Department of Energy, Richland Operations Office (RL) in cooperation with the Washington State Department of Ecology, has prepared this Engineering Evaluation/Cost Analysis pursuant to CERCLA. Based on the evaluation, RL has determined that hazardous substances in the 233-S Facility may present a potential threat to human health or the environment, and that an expedited removal action is warranted for decommissioning of the facility

  1. Temporary septic holding tank at the 300-FF-1 remedial action central support facility -- Engineering report

    International Nuclear Information System (INIS)

    Jackson, G.J.

    1996-09-01

    The 300-FF-1 Remedial Action Support Facility will be required in the 300 Area (at the Hanford Site in Richland, Washington) to support the remedial actions planned for the 300-FF-1 Operable Unit. In conjunction with this project, soils laden with radiological contamination will be excavated, removed, and transported to a permitted disposal facility, if required based upon characterization. This facility will be a temporary, modular building sized to provide office and work space for the supervisors, engineers, and technicians assigned to the project and engaged in the associated field work. Electrical and potable water service to the 300-FF-1 Support Facility will be provided via permanent connections to existing systems. A temporary septic system is desired as opposed to connecting to the existing sewer system due to regulatory issues. The paper describes the project location, geology and flooding potential, design criteria, operations, and maintenance

  2. Engineering Task Plan for the Integrity Assessment Examination of Double-Contained Receiver Tanks (DCRT), Catch Tanks and Ancillary facilities

    International Nuclear Information System (INIS)

    BECKER, D.L.

    2000-01-01

    This Engineering Task Plan (ETP) presents the integrity assessment examination of three DCRTs, seven catch tanks, and two ancillary facilities located in the 200 East and West Areas of the Hanford Site. The integrity assessment examinations, as described in this ETP, will provide the necessary information to enable the independently qualified registered professional engineer (IQRPE) to assess the condition and integrity of these facilities. The plan is consistent with the Double-Shell Tank Waste Transfer Facilities Integrity Assessment Plan

  3. Engineering evaluation/cost analysis for the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    1997-01-01

    The deactivated 233-S Plutonium Concentration Facility (233-S Facility) is located in the 200 Area. The facility has undergone severe degradation due to exposure to extreme weather conditions. A rapid freeze and thaw cycle occurred at the Hanford Site during February 1996, which caused cracking to occur on portions of the building's roof. This has resulted in significantly infiltration of water into the facility, which provides a pathway for potential release of radioactive material into the environment (air and/or ground). The weather caused several existing cracks in the concrete portions of the structure to lengthen, increasing the potential for failed confinement of the radioactive material in the building. Differential settlement has also occurred, causing portions of the facility to separate from the main building structure thus creating a potential for release of radioactive material t the environment. An expedited removal action is proposed to ensure that a release from the 233-S Facility does not occur. The US Department of Energy (DOE), Richland Operations Office (RL), in cooperation with the EPA, has prepared this Engineering Evaluation/Cost Analysis (EE/CA) pursuant to CERCLA. Based on the evaluation, RL has determined that hazardous substances in the 233-S Facility may present a potential threat to human health and/or the environment, and that an expedited removal action is warranted. The purpose of the EE/CA is to provide the framework for the evaluation and selection of a technology from a viable set of alternatives for a removal action

  4. Temporary septic holding tank at the 100-C remedial action restroom facility -- Engineering report

    International Nuclear Information System (INIS)

    Jackson, G.J.

    1996-10-01

    The primary mission of the Hanford Site from 1943 to 1990 was to produce nuclear materials for national defense. Waste disposal activities associated with this mission resulted in the creation of more than 1,000 waste sites contaminated with radioactive and chemically hazardous constituents. Investigation and remediation of these waste sites is governed by the Tri-Party Agreement. The agreement grouped the waste sites into 78 operable units, each of which was to be investigated and remediated separately. The 100-C Remedial Action Restroom Trailer Facility will be required near the 105-C Reactor to support the 105-C Interim Storage Project. This project is part of the decommissioning of the eight surplus reactor buildings along the Columbia River in the 100 Area. This facility will be a temporary, modular building sized to provide restroom facilities for the supervisors, engineers, technicians, and craft personnel assigned to the project and engaged in the associated field work. This facility will be a temporary, modular building sized to provide restroom facilities for the supervisors, engineers, technicians, and raft personnel assigned to the project and engaged in the associated field work. The paper describes the project location, geology and flooding potential, design criteria, and operations and maintenance

  5. Systems engineering applied to integrated safety management for high consequence facilities

    International Nuclear Information System (INIS)

    Barter, R; Morais, B.

    1998-01-01

    Integrated Safety Management is a concept that is being actively promoted by the U.S. Department of Energy as a means of assuring safe operation of its facilities. The concept involves the integration of safety precepts into work planning rather than adjusting for safe operations after defining the work activity. The system engineering techniques used to design an integrated safety management system for a high consequence research facility are described. An example is given to show how the concepts evolved with the system design

  6. Lawrence Berkeley laboratory neutral-beam engineering test facility power-supply system

    International Nuclear Information System (INIS)

    Lutz, I.C.; Arthur, C.A.; deVries, G.J.; Owren, H.M.

    1981-10-01

    The Lawrence Berkeley Laboratory is upgrading the neutral beam source test facility (NBSTF) into a neutral beam engineering test facility (NBETF) with increased capabilities for the development of neutral beam systems. The NBETF will have an accel power supply capable of 170 kV, 70 A, 30 sec pulse length, 10% duty cycle; and the auxiliary power supplies required for the sources. This paper describes the major components, their ratings and capabilities, and the flexibility designed to accomodate the needs of source development

  7. Energy use and engineering audits at state-owned facilities in Minnesota

    Energy Technology Data Exchange (ETDEWEB)

    Hirst, E.

    1980-01-01

    The contents and results of two large computerized data bases maintained by the Minnesota Department of Administration are described and analyzed. One contains information on monthly fuel use from 1972 through 1978 for 42 large state facilities: community colleges, state universities, hospitals, prisons, and office buildings. The second contains the results of detailed engineering audits performed at 41 such institutions. The audits cover 270 buildings and include 2010 individual energy conservation recommendations. Several data base management issues are discussed. These include errors and their identification, development of simple and consistent definitions for key terms, and collection of information on the major determinants of energy use and conservation potentials at these facilities.

  8. Facility ''Bench of Stationary Engines for Study of Emissions (E65-PO) CIEMAT''

    International Nuclear Information System (INIS)

    Rojas Garcia, E.; Rodriguez Maroto, J.J.

    2007-01-01

    The Project of Technology of Aerosols in Generation of Energy, of the Department of Fossil Fuels of the CIEMAT, began in the year 2004, a research activity line, based on the study of the emissions coming from internal combustion engines, particularly of Diesel technology. Activity was continued by the Polluting Emissions Group of the Department of Environment, when becoming the original Project in this Group. From the concession to the Group, of the project GR/AMB/0119/2004 Evaluation of the Emissions of Biodiesel supported by the Autonomous Community of Madrid together with the European Regional Development Fund (ERDF), this activity was encourage, with the design, assembly and to get ready of the facility Bench of stationary engines for study of emissions, located in the building 65 at CIEMAT, Madrid. The present report constitutes a detailed technical description of each one of the elements that the installation Bench of stationary engines for study of emissions it integrated within the framework of the referred project (GR/AMB/0119/2004) and whose capacity includes studies of the effects of the engine, fuel, operation conditions, and methodology of sampling and measurement of emissions (gases and particles). The fundamental parts of facility describes in the present report are: engine test cell (cabin of sound insulation , ventilation and refrigeration system, anti vibrations mounting, engine, dynamometric brake), lines of preconditioning of particles and gases emissions (exhaust line, primary and secondary dilution lines, gases cleaning system...), other general parts of facility (sampling and measurement station, service lines...). The present report not only reflects the characteristics of the systems involved, but rather also in certain cases specified the procedure and reason for their choice. (Author) 10 refs

  9. Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

    1994-10-01

    This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

  10. Construction and operational experiences of engineered barrier test facility for near surface disposal of LILW

    International Nuclear Information System (INIS)

    Park, Jin Beak; Park, Se Moon; Kim, Chang Lak

    2003-01-01

    Engineered barrier test facility is specially designed to demonstrate the performance of engineered barrier system for the near-surface disposal facility under the domestic environmental conditions. Comprehensive measurement systems are installed within each test cell. Long-and short-term monitoring of the multi-layered cover system can be implemented according to different rainfall scenarios with artificial rainfall system. Monitoring data on the water content, temperature, matric potential, lateral drainage and percolation of cover-layer system can be systematically managed by automatic data acquisition system. The periodic measurement data are collected and will be analyzed by a dedicated database management system, and provide a basis for performance verification of the disposal cover design

  11. Waste Receiving and Processing Facility, Module 1: Volume 5, Engineering studies

    International Nuclear Information System (INIS)

    1992-03-01

    The WRAP facility at Hanford will retrieve, process, certify transuranic, mixed, and low level radioactive wastes for disposal/either on-site or at the WIPP. The Conceptual Design Report for the Waste Receiving And Processing Facility, Module 1 (WRAP 1), established the technical benchmark. The UE ampersand C Engineering Proposal/Work Plan proposed twenty Evaluation/Optimization Engineering Studies to evaluate design alternatives and critically examine functional performance requirements prior to commencement of Preliminary Design. Of these twenty studies, one has been eliminated as unnecessary (The Use of Scintered Metal Filters) due mainly to the lack of National Standards and to the fact that standard HEPA type filters are totally adequate for WRAP application. This report presents an executive summary of the remaining nineteen studies

  12. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Design Requirements Document (DRD)

    Science.gov (United States)

    Rigo, H. S.; Bercaw, R. W.; Burkhart, J. A.; Mroz, T. S.; Bents, D. J.; Hatch, A. M.

    1981-01-01

    A description and the design requirements for the 200 MWe (nominal) net output MHD Engineering Test Facility (ETF) Conceptual Design, are presented. Performance requirements for the plant are identified and process conditions are indicated at interface stations between the major systems comprising the plant. Also included are the description, functions, interfaces and requirements for each of these major systems. The lastest information (1980-1981) from the MHD technology program are integrated with elements of a conventional steam electric power generating plant.

  13. Design of a Facility to Test the Advanced Stirling Radioisotope Generator Engineering Unit

    Science.gov (United States)

    Lewandowski, Edward J.; Schreiber, Jeffrey G.; Oriti, Salvatore M.; Meer, David W.; Brace, Michael H.; Dugala, Gina

    2009-01-01

    The Advanced Stirling Radioisotope Generator (ASRG) is being considered to power deep space missions. An engineering unit, the ASRG-EU, was designed and fabricated by Lockheed Martin under contract to the Department of Energy. This unit is currently on an extended operation test at NASA Glenn Research Center to generate performance data and validate the life and reliability predictions for the generator and the Stirling convertors. A special test facility was designed and built for testing the ASRG-EU. Details of the test facility design are discussed. The facility can operate the convertors under AC bus control or with the ASRG-EU controller. It can regulate input thermal power in either a fixed temperature or fixed power mode. An enclosure circulates cooled air around the ASRG-EU to remove heat rejected from the ASRG-EU by convection. A custom monitoring and data acquisition system supports the test. Various safety features, which allow 2417 unattended operation, are discussed.

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

    Science.gov (United States)

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

    1992-01-01

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

  15. Team engineering for successful reuse and mission enhancement of a former DOE Weapons Material Production Facility

    International Nuclear Information System (INIS)

    Blackford, L.T.; Mizner, J.H. Jr.

    1994-11-01

    This paper describes the team engineering approach used to resolve issues associated with converting a 50-year-old fuel processing facility into a decontamination facility. In only nine months, the multi-disciplinary team formed for this task has made significant progress toward both long-term and short-term goals, including conceptual design of two decontamination modules. The team's accomplishments are even more notable in light of frequent changes in scope and mission. Today, the team serves as a venue for troubleshooting operational issues, sharing vendor information, developing long-range strategies, and addressing integration issues within the facility's organizational structure. The team's approach could serve as a useful model to address the many issues surrounding the transition of the U.S. Department of Energy (DOE) and commercial complexes from a production and supply role to one of cleanup and environmental remediation

  16. Demountable toroidal fusion core facility for physics optimization and fusion engineering

    International Nuclear Information System (INIS)

    Bogart, S.L.; Wagner, C.E.; Krall, N.A.; Dalessandro, J.A.; Weggel, C.F.; Lund, K.O.; Sedehi, S.

    1986-01-01

    Following a successful compact ignition tokamak (CIT) experiment, a fusion facility will be required for physics optimization (POF) and fusion engineering research (FERF). The POF will address issues such as high-beta operation, current drive, impurity control, and will test geometric and configurational variations such as the spherical torus or the reversed-field pinch (RFP). The FERF will be designed to accumulate rapidly a large neutron dose in prototypical fusion subsystems exposed to radiation. Both facilities will require low-cost replacement cores and rapid replacement times. The Demountable Toroidal Fusion Core (DTFC) facility is designed to fulfill these requirements. It would be a cost-effective stepping stone between the CIT and a demonstration fusion reactor

  17. Temporary septic holding tank at the 100-C remedial action restroom facility -- Engineering report. Revision 1

    International Nuclear Information System (INIS)

    Jackson, G.J.

    1996-10-01

    The primary mission of the Hanford Site from 1943 to 1990 was to produce nuclear materials for national defense. Waste disposal activities associated with this mission resulted in the creation of more than 1,000 waste sites contaminated with radioactive and chemically hazardous constituents. Investigation and remediation of these waste sites is governed by the Tri-Party Agreement. The 100-C Remedial Action Restroom Trailer Facility will be required near the 105-C Reactor to support the 105-C Interim Storage Project. This project is part of the decommissioning of the eight surplus reactor buildings along the Columbia River in the 100 Area. This facility will be a temporary, modular building sized to provide restroom facilities for the supervisors, engineers, technicians, and raft personnel assigned to the project and engaged in the associated field work. This paper describes the geology and flooding potential, design criteria, operations, and maintenance

  18. Considerations for closure of low-level radioactive waste engineered disposal facilities

    International Nuclear Information System (INIS)

    1992-01-01

    Proper stabilization and closure of low-level radioactive waste disposal facilities require detailed planning during the early stages of facility development. This report provides considerations for host States, compact regions, and unaffiliated States on stabilization and closure of engineered low-level radioactive waste and mixed waste disposal facilities. A time line for planning closure activities, which identifies closure considerations to be addressed during various stages of a facility's development, is presented. Current Federal regulatory requirements and guidance for closure and post-closure are outlined. Significant differences between host State and Federal closure requirements are identified. Design features used as stabilization measures that support closure, such as waste forms and containers, backfill materials, engineered barrier systems, and site drainage systems, are described. These design features are identified and evaluated in terms of how they promote long-term site stability by minimizing water infiltration, controlling subsidence and surface erosion, and deterring intrusion. Design and construction features critical to successful closure are presented for covers and site drainage. General considerations for stabilization and closure operations are introduced. The role of performance and environmental monitoring during closure is described

  19. Scope and status of the USA Engineering Test Facility including relevant TFTR research and development

    International Nuclear Information System (INIS)

    Becraft, W.R.; Reardon, P.J.

    1980-01-01

    The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The progress toward the design and construction of the ETF will reflect the significant achievements of past, present, and future experimental tokamak devices. Some of the features of this foundation of experimental results and relevant engineering designs and operation will derive from the Tokamak Fusion Test Reactor (TFTR) Project, now nearing the completion of its construction phase. The ETF would provide a test-bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy (OFE) established the ETF Design Center activity to prepare the design of the ETF. This paper describes the design status of the ETF and discusses some highlights of the TFTR R and D work

  20. Scope and status of the USA Engineering Test Facility including relevant TFTR research and development

    International Nuclear Information System (INIS)

    Becraft, W.R.; Reardon, P.J.

    1981-01-01

    The vehicle by which the fusion programme would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The progress toward the design and construction of the ETF will reflect the significant achievements of past, present, and future experimental tokamak devices. Some of the features of this foundation of experimental results and relevant engineering designs and operation will derive from the Tokamak Fusion Test Reactor (TFTR) Project, now nearing the completion of its construction phase. The ETF would provide a test-bed for reactor components in the fusion environment. To initiate preliminary planning for the ETF decision, the Office of Fusion Energy (OFE) established the ETF Design Center activity to prepare the design of the ETF. This paper describes the design status of the ETF and discusses some highlights of the TFTR R and D work. (author)

  1. Systems Engineering and Safety Issues in Scientific Facilities Subject to Ionizing Radiations

    Directory of Open Access Journals (Sweden)

    Pierre Bonnal

    2013-10-01

    Full Text Available The conception and development of large-scale scientific facilities emitting ionizing radiations rely more on project management practices in use in the process industry than on systems engineering practices. This paper aims to highlight possible reasons for this present situation and to propose some ways to enhance systems engineering so that the specific radiation safety requirements are considered and integrated in the approach. To do so, we have reviewed lessons learned from the management of large-scale scientific projects and more specifically that of the Large Hadron Collider project at CERN. It is shown that project management and systems engineering practices are complementary and can beneficially be assembled in an integrated and lean managerial framework that grants the appropriate amount of focus to safety and radiation safety aspects.

  2. Overview of the main challenges for the engineering design of the test facilities system of IFMIF

    International Nuclear Information System (INIS)

    Molla, J.; Nakamura, K.

    2009-01-01

    High intense radiation fields were demanded to IFMIF to address the lack of information on effects in materials due to radiation fields with fusion reactor features. Such intense radiation fields will also produce a number of unwanted effects in exposed materials and components. The main difficulties to achieve a reliable engineering design of the Test Facilities System during the Engineering Validation and the Engineering Design phase of IFMIF now under development are reviewed in this paper. The most challenging activities will be the design of the high flux test module, the creep fatigue test module, the test cell and the remote handling system. The intense radiation fields in the irradiation area and the high availability required for IFMIF (70%) are the main reasons for these difficulties.

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

    International Nuclear Information System (INIS)

    1977-01-01

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

  4. Engineered safeguards system activities at Sandia Laboratories for back-end fuel cycle facilities

    International Nuclear Information System (INIS)

    Sellers, T.A.; Fienning, W.C.; Winblad, A.E.

    1978-01-01

    Sandia Laboratories have been developing concepts for safeguards systems to protect facilities in the back-end of the nuclear fuel cycle against potential threats of sabotage and theft of special nuclear material (SNM). Conceptual designs for Engineered Safeguards Systems (ESSs) have been developed for a Fuel Reprocessing Facility (including chemical separations, plutonium conversion, and waste solidification), a Mixed-Oxide Fuel Fabrication Facility, and a Plutonium Transport Vehicle. Performance criteria for the various elements of these systems and a candidate systematic design approach have been defined. In addition, a conceptual layout for a large-scale Fuel-Cycle Plutonium Storage Facility has been completed. Work is continuing to develop safeguards systems for spent fuel facilities, light-water reactors, alternative fuel cycles, and improved transportation systems. Additional emphasis will be placed on the problems associated with national diversion of special nuclear material. The impact on safeguards element performance criteria for surveillance and containment to protect against national diversion in various alternative fuel cycle complexes is also being investigated

  5. Environmental assessment: Closure of the Waste Calcining Facility (CPP-633), Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1996-07-01

    The U.S. Department of Energy (DOE) proposes to close the Waste Calcining Facility (WCF). The WCF is a surplus DOE facility located at the Idaho Chemical Processing Plant (ICPP) on the Idaho National Engineering Laboratory (INEL). Six facility components in the WCF have been identified as Resource Conservation and Recovery Ace (RCRA)-units in the INEL RCRA Part A application. The WCF is an interim status facility. Consequently, the proposed WCF closure must comply with Idaho Rules and Standards for Hazardous Waste contained in the Idaho Administrative Procedures Act (IDAPA) Section 16.01.05. These state regulations, in addition to prescribing other requirements, incorporate by reference the federal regulations, found at 40 CFR Part 265, that prescribe the requirements for facilities granted interim status pursuant to the RCRA. The purpose of the proposed action is to reduce the risk of radioactive exposure and release of hazardous constituents and eliminate the need for extensive long-term surveillance and maintenance. DOE has determined that the closure is needed to reduce potential risks to human health and the environment, and to comply with the Idaho Hazardous Waste Management Act (HWMA) requirements

  6. Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

    1994-09-01

    The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria.

  7. Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

    1994-09-01

    The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria

  8. Proposal of experimental facilities for studies of nuclear data and radiation engineering in the Intense Proton Accelerator Project

    CERN Document Server

    Baba, M; Nagai, Y; Ishibashi, K

    2003-01-01

    A proposal is given on the facilities and experiments in the Intense Proton Accelerator Project (J-PARC) relevant to the nuclear data and radiation engineering, nuclear astrophysics, nuclear transmutation, accelerator technology and space technology and so on. (3 refs).

  9. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: vasconv@cdtn.br, e-mail: silvaem@cdtn.br, e-mail: aclc@cdtn.br, e-mail: reissc@cdtn.br

    2009-07-01

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  10. Experimental facility and methodology for systematic studies of cold startability in direct injection Diesel engines

    Science.gov (United States)

    Pastor, J. V.; García-Oliver, J. M.; Pastor, J. M.; Ramírez-Hernández, J. G.

    2009-09-01

    Cold start at low temperatures in current direct injection (DI) Diesel engines is a problem which has not yet been properly solved and it becomes particularly critical with the current trend to reduce the engine compression ratio. Although it is clear that there are some key factors whose control leads to a proper cold start process, their individual relevance and relationships are not clearly understood. Thus, efforts on optimization of the cold start process are mainly based on a trial-and-error procedure in climatic chambers at low ambient temperature, with serious limitations in terms of measurement reliability during such a transient process, low repeatability and experimental cost. This paper presents a novel approach for an experimental facility capable of simulating real engine cold start, at room temperature and under well-controlled low speed and low temperature conditions. It is based on an optical single cylinder engine adapted to reproduce in-cylinder conditions representative of those of a real engine during start at cold ambient temperatures (of the order of -20 °C). Such conditions must be realistic, controlled and repeatable in order to perform systematic studies in the borderline between ignition success and misfiring. An analysis methodology, combining optical techniques and heat release analysis of individual cycles, has been applied.

  11. Experimental facility and methodology for systematic studies of cold startability in direct injection Diesel engines

    International Nuclear Information System (INIS)

    Pastor, J V; García-Oliver, J M; Pastor, J M; Ramírez-Hernández, J G

    2009-01-01

    Cold start at low temperatures in current direct injection (DI) Diesel engines is a problem which has not yet been properly solved and it becomes particularly critical with the current trend to reduce the engine compression ratio. Although it is clear that there are some key factors whose control leads to a proper cold start process, their individual relevance and relationships are not clearly understood. Thus, efforts on optimization of the cold start process are mainly based on a trial-and-error procedure in climatic chambers at low ambient temperature, with serious limitations in terms of measurement reliability during such a transient process, low repeatability and experimental cost. This paper presents a novel approach for an experimental facility capable of simulating real engine cold start, at room temperature and under well-controlled low speed and low temperature conditions. It is based on an optical single cylinder engine adapted to reproduce in-cylinder conditions representative of those of a real engine during start at cold ambient temperatures (of the order of −20 °C). Such conditions must be realistic, controlled and repeatable in order to perform systematic studies in the borderline between ignition success and misfiring. An analysis methodology, combining optical techniques and heat release analysis of individual cycles, has been applied

  12. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    International Nuclear Information System (INIS)

    Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos

    2009-01-01

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  13. Development of lithium target system in engineering validation and engineering design activity of the international fusion materials irradiation facility (IFMIF/EVEDA)

    International Nuclear Information System (INIS)

    Wakai, Eiichi; Kondo, Hiroo; Sugimoto, Masayoshi; Ida, Mizuho; Kanemura, Takuji; Watanabe, Kazuyoshi; Fujishiro, Kouji; Edao, Yuuki; Niitsuma, Shigeto; Kimura, Haruyuki; Fukada, Satoshi; Hiromoto, Tetsushi; Shigeharu, Satoshi; Yagi, Jyuro; Furukawa, Tomohiro; Hirakawa, Yasushi; Suzuki, Akihiro; Terai, Takayuki; Horiike, Hiroshi; Hoashi, Eiji; Suzuki, Sachiko; Yamaoka, Nobuo; Serizawa, Hisashi; Kawahito, Yosuke; Tsuji, Yoshiyuki; Furuya, Kazuyuki; Takeo, Fumio

    2012-01-01

    Engineering validation and engineering design activity (EVEDA) for the international fusion materials irradiation facility (IFMIF) has been conducted since 2007. Research and development of the Lithium target facility is an important part of this activity. We constructed a world largest liquid Lithium test loop with a capacity of 5000 L in 2010 and successfully completed the first stage validation tests (functional tests of components and Lithium flow test (flow velocity 15 m/s at the target). In the present article, recent results of the EVEDA activity for the Lithium target facility and related technologies on liquid Lithium are reviewed. (author)

  14. Assessment of activity-based pyroprocess costs for an engineering-scale facility in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Ki; Ko, Won Il [Nuclear Fuel Cycle Analysis Department, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Bang, Sung Sig [Dept. of Business and Technology Management, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2015-12-15

    This study set the pyroprocess facility at an engineering scale as a cost object, and presented the cost consumed during the unit processes of the pyroprocess. For the cost calculation, the activity based costing (ABC) method was used instead of the engineering cost estimation method, which calculates the cost based on the conceptual design of the pyroprocess facility. The calculation results demonstrate that the pyroprocess facility's unit process cost is $194/kgHM for pretreatment, $298/kgHM for electrochemical reduction, $226/kgHM for electrorefining, and $299/kgHM for electrowinning. An analysis demonstrated that the share of each unit process cost among the total pyroprocess cost is as follows: 19% for pretreatment, 29% for electrochemical reduction, 22% for electrorefining, and 30% for electrowinning. The total unit cost of the pyroprocess was calculated at $1,017/kgHM. In the end, electrochemical reduction and the electrowinning process took up most of the cost, and the individual costs for these two processes was found to be similar. This is because significant raw material cost is required for the electrochemical reduction process, which uses platinum as an anode electrode. In addition, significant raw material costs are required, such as for Li3PO4, which is used a lot during the salt purification process.

  15. Engineering validation for lithium target facility of the IFMIF under IFMIF/EVEDA project

    Directory of Open Access Journals (Sweden)

    E. Wakai

    2016-12-01

    Full Text Available The International Fusion Materials Irradiation Facility (IFMIF, presently in the Engineering Validation and Engineering Design Activities (EVEDA phase was started from 2007 under the frame of the Broader Approach (BA agreement. In the activities, a prototype Li loop with the world's highest flow rate of 3000L/min was constructed in 2010, and it succeeded in generating a 100mm wide and 25mm thick with a free-surface lithium flow along a concave back plate steadily at a high-speed of 15m/s at 250°C for 1300h. In the demonstration operation it was needed to develop the Li flowing measurement system with precious resolution less than 0.1mm, and a new wave height measuring method which is laser-probe method was developed for measurements of the 3D geometry of the liquid Li target surface. Using the device, the stability of the variation in the Li flowing thickness which is required in the IFMIF specification was ±1mm or less as the liquid Li target, and the result was satisfied with it and the feasibility of the long-term stable liquid Li flow was also verified. The results of the other engineering validation tests such as lithium purification tests of lithium target facility have also been evaluated and summarized.

  16. Engineering Evaluation/Cost Analysis for the 100-N Area Ancillary Facilities and Integration Plan

    International Nuclear Information System (INIS)

    Mukherjee, B.

    1997-09-01

    This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives for addressing final disposition of contaminated buildings and structures in the 100-N Area of the Hanford Site. The Hanford Site is located in southeastern Washington State and is owned by the U.S. Government and operated by the U.S. Department of Energy, Richland Operations Office (RL). In November 1989, the 100 Area of the Hanford Site (as well as the 200, 300, and 1100 Areas) was placed on the U.S. Environmental Protection Agency's National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980. The 100 Area NPL includes the 100-N Area, which is in various stages of the remediation process. It has been determined by RL that hazardous substances in the 100-N Area ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, RL, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the inactive contaminated ancillary facilities in the 100-N Area, the facilities residing in the buffer zone, and the Hanford Generating Plant (HGP) and the solid waste management units (SWMUs) inside HGP support facilities. The 105-N Reactor and 109-N Heat Exchange facilities are excluded from this EE/CA evaluation

  17. Description and Operational Experiences of the Engineering Test Facility - Helium Technology (ETF-HT)

    International Nuclear Information System (INIS)

    Zhang Zuoyi; Yang Mingde; Bo Hanliang; Duan Riqqiang; Zhu Hongye

    2014-01-01

    This paper presents the configuration of the Engineering Test Facility - Helium Technology (ETF-HT) and the information of its key components and subsystems, which is located in the Changping campus of Tsinghua University. The ETF-HT facility began to be constructed in Jan. 2009. The main objective of the facility is to test and verify the thermo-hydraulic performance of one full-sized modular unit of HTR-PM helically coiled SG assembly. In the ETF-HT facility, electricity energy is used to heat the loop helium, centrifugal blower is used to circulate the helium medium, and the heat sink is one would-tested SG module. Up to now, except for the tested SG module, preheater and hot gas duct under way of construction, the other components has been installed in situ. Via the temporary connection of the installed components, the preliminary operation of the loop has been carried out to test its performances as can be done, which include the loop leak tightness, blower pneumatic performance and electrical heater at partial thermal load. (author)

  18. The disposal of Canada's nuclear fuel waste: engineering for a disposal facility

    International Nuclear Information System (INIS)

    Simmons, G.R.; Baumgartner, P.

    1994-01-01

    This report presents some general considerations for engineering a nuclear fuel waste disposal facility, alternative disposal-vault concepts and arrangements, and a conceptual design of a used-fuel disposal centre that was used to assess the technical feasibility, costs and potential effects of disposal. The general considerations and alternative disposal-vault arrangements are presented to show that options are available to allow the design to be adapted to actual site conditions. The conceptual design for a used-fuel disposal centre includes descriptions of the two major components of the disposal facility, the Used-Fuel Packaging Plant and the disposal vault; the ancillary facilities and services needed to carry out the operations are also identified. The development of the disposal facility, its operation, its decommissioning, and the reclamation of the site are discussed. The costs, labour requirements and schedules used to assess socioeconomic effects and that may be used to assess the cost burden of waste disposal to the consumer of nuclear energy are estimated. The Canadian Nuclear Fuel Waste Management Program is funded jointly by AECL and Ontario Hydro under the auspices of the CANDU Owners Group. (author)

  19. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Bryant, J.W.; Nenni, J.A.

    2003-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  20. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Jeffrey Bryant

    2008-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  1. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ansley, Shannon Leigh

    2002-02-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  2. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility; TOPICAL

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

  3. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Wastewater Discharge Facility

    International Nuclear Information System (INIS)

    Ansley, Shannon L.

    2002-01-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist

  4. SECONDARY WASTE/ETF (EFFLUENT TREATMENT FACILITY) PRELIMINARY PRE-CONCEPTUAL ENGINEERING STUDY

    International Nuclear Information System (INIS)

    May, T.H.; Gehner, P.D.; Stegen, Gary; Hymas, Jay; Pajunen, A.L.; Sexton, Rich; Ramsey, Amy

    2009-01-01

    This pre-conceptual engineering study is intended to assist in supporting the critical decision (CD) 0 milestone by providing a basis for the justification of mission need (JMN) for the handling and disposal of liquid effluents. The ETF baseline strategy, to accommodate (WTP) requirements, calls for a solidification treatment unit (STU) to be added to the ETF to provide the needed additional processing capability. This STU is to process the ETF evaporator concentrate into a cement-based waste form. The cementitious waste will be cast into blocks for curing, storage, and disposal. Tis pre-conceptual engineering study explores this baseline strategy, in addition to other potential alternatives, for meeting the ETF future mission needs. Within each reviewed case study, a technical and facility description is outlined, along with a preliminary cost analysis and the associated risks and benefits.

  5. Engineering program in order to increase the irradiated fuel storage capacity in pool facilities of Juragua

    International Nuclear Information System (INIS)

    Rodriguez R, J.

    1996-01-01

    In 1993, a technical program in the spent fuel storage area of Nuclear Plant Juragua was launched. Such a program tries to carry out an engineering assessment of the possibility of increasing the spent fuel storage capacity in pool storage facilities by using high density racks (re-racking) instead of the original (non-compact) ones. The purpose of the above-mentioned program is to evaluate possible solutions that can be applied to the construction works prior to plant operation. The first stage of the program for the 1994-95 period is an ongoing Engineering-Economic Feasibility Study (EEFS), which endeavors to examine the capabilities of the reloading pool in Unit-1 Reactor building and long-term storage pool in auxiliary building in high density storage conditions. Technical details of the EEFS and reached results and difficulties are described. (author). 5 refs., 2 figs

  6. 76 FR 55933 - Federal Property Suitable as Facilities To Assist the Homeless

    Science.gov (United States)

    2011-09-09

    ... written expression of interest to HHS, addressed to Theresa Ritta, Division of Property Management... Management Division, Naval Facilities Engineering Command, Washington Navy Yard, 1330 Patterson Ave., SW... Area Ohio Facility 30089 5490 Pearson Wright Patterson AFB OH 45433 Landholding Agency: Air Force...

  7. US command improvements and command vulnerability

    International Nuclear Information System (INIS)

    Ball, D.; Bethe, H.A.; Blair, B.G.; Bracken, P.; Carter, A.B.; Dickinson, H.; Garwin, R.L.; Holloway, D.; Kendall, H.W.

    1988-01-01

    In essence, the United States still relies on the strategic command system erected during the 1960s and 1970s, but as we have seen, this system suffers from a number of serious weaknesses. Among these the authors emphasized the vulnerability of vital communications even before any warheads impact directly on U.S. targets, as well as the systems; heavy reliance on a relatively small number of limited-endurance aircraft as command posts and radio relays. This paper focuses on the committed improvement program, assess its impact on command vulnerability, and offer suggestions for further command improvements designed to enhance crisis stability and to facilitate ware termination should deterrence fail. The reader should note that this chapter is rather more technical than the remainder of this book

  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. Facile construction of a random protein domain insertion library using an engineered transposon.

    Science.gov (United States)

    Shah, Vandan; Pierre, Brennal; Kim, Jin Ryoun

    2013-01-15

    Insertional fusion between multiple protein domains represents a novel means of creating integrated functionalities. Currently, there is no robust guideline for selection of insertion sites ensuring the desired functional outcome of insertional fusion. Therefore, construction and testing of random domain insertion libraries, in which a host protein domain is randomly inserted into a guest protein domain, significantly benefit extensive exploration of sequence spaces for insertion sites. Short peptide residues are usually introduced between protein domains to alleviate structural conflicts, and the interdomain linker residues may affect the functional outcome of protein insertion complexes. Unfortunately, optimal control of interdomain linker residues is not always available in conventional methods used to construct random domain insertion libraries. Moreover, most conventional methods employ blunt-end rather than sticky-end ligation between host and guest DNA fragments, thus lowering library construction efficiency. Here, we report the facile construction of random domain insertion libraries using an engineered transposon. We show that random domain insertion with optimal control of interdomain linker residues was possible with our engineered transposon-based method. In addition, our method employs sticky-end rather than blunt-end ligation between host and guest DNA fragments, thus allowing for facile construction of relatively large sized libraries. Copyright © 2012 Elsevier Inc. All rights reserved.

  10. Spent nuclear fuel project, Cold Vacuum Drying Facility human factors engineering (HFE) analysis: Results and findings

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1998-01-01

    This report presents the background, methodology, and findings of a human factors engineering (HFE) analysis performed in May, 1998, of the Spent Nuclear Fuels (SNF) Project Cold Vacuum Drying Facility (CVDF), to support its Preliminary Safety Analysis Report (PSAR), in responding to the requirements of Department of Energy (DOE) Order 5480.23 (DOE 1992a) and drafted to DOE-STD-3009-94 format. This HFE analysis focused on general environment, physical and computer workstations, and handling devices involved in or directly supporting the technical operations of the facility. This report makes no attempt to interpret or evaluate the safety significance of the HFE analysis findings. The HFE findings presented in this report, along with the results of the CVDF PSAR Chapter 3, Hazards and Accident Analyses, provide the technical basis for preparing the CVDF PSAR Chapter 13, Human Factors Engineering, including interpretation and disposition of findings. The findings presented in this report allow the PSAR Chapter 13 to fully respond to HFE requirements established in DOE Order 5480.23. DOE 5480.23, Nuclear Safety Analysis Reports, Section 8b(3)(n) and Attachment 1, Section-M, require that HFE be analyzed in the PSAR for the adequacy of the current design and planned construction for internal and external communications, operational aids, instrumentation and controls, environmental factors such as heat, light, and noise and that an assessment of human performance under abnormal and emergency conditions be performed (DOE 1992a)

  11. Use of engineered soils beneath low-level radioactive waste disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sandford, T.C.; Humphrey, D.N.; DeMascio, F.A. [Univ. of Maine, Orono, ME (United States). Dept. of Civil Engineering

    1993-03-01

    Current regulations are oriented toward locating low-level radioactive waste disposal facilities on sites that have a substantial natural soil barrier and are above the groundwater table. In some of the northern states, like Maine, the overburden soils are glacially derived and in most places provide a thin cover over bedrock with a high groundwater table. Thus, the orientation of current regulations can severely limit the availability of suitable sites. A common characteristic of many locations in glaciated regions is the rapid change of soil types that may occur and the heterogeneity within a given soil type. In addition, the bedrock may be fractured, providing avenues for water movement. A reliable characterization of these sites can be difficult, even with a detailed subsurface exploration program. Moreover, fluctuating groundwater and frost as well as the natural deposition processes have introduced macro features such as cracks, fissures, sand and silt seams, and root holes. The significant effect that these macro features have on the permeability and adsorptive capacity of a large mass is often ignored or poorly accounted for in the analyses. This paper will examine an alternate approach, which is to use engineered soils as a substitute for some or all of the natural soil and to treat the fractures in the underlying bedrock. The site selection would no longer be primarily determined by the natural soil and rock and could even be placed in locations with no existing soils. Engineered soils can be used for below- or aboveground facilities.

  12. Schema for Spacecraft-Command Dictionary

    Science.gov (United States)

    Laubach, Sharon; Garcia, Celina; Maxwell, Scott; Wright, Jesse

    2008-01-01

    An Extensible Markup Language (XML) schema was developed as a means of defining and describing a structure for capturing spacecraft command- definition and tracking information in a single location in a form readable by both engineers and software used to generate software for flight and ground systems. A structure defined within this schema is then used as the basis for creating an XML file that contains command definitions.

  13. Use of reliability engineering tools in safety and risk assessment of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Raso, Amanda Laureano; Vasconcelos, Vanderley de; Marques, Raíssa Oliveira; Soares, Wellington Antonio; Mesquita, Amir Zacarias, E-mail: amandaraso@hotmail.com, E-mail: vasconv@cdtn.br, E-mail: raissaomarques@gmail.com, E-mail: soaresw@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil). Serviço de Tecnologia de Reatores

    2017-07-01

    Safety, reliability and availability are fundamental criteria in design, construction and operation of nuclear facilities, as nuclear power plants. Deterministic and probabilistic risk assessments of such facilities are required by regulatory authorities in order to meet licensing regulations, contributing to assure safety, as well as reduce costs and environmental impacts. Probabilistic Risk Assessment has become an important part of licensing requirements of the nuclear power plants in Brazil and in the world. Risk can be defined as a qualitative and/or quantitative assessment of accident sequence frequencies (or probabilities) and their consequences. Risk management is a systematic application of management policies, procedures and practices to identify, analyze, plan, implement, control, communicate and document risks. Several tools and computer codes must be combined, in order to estimate both probabilities and consequences of accidents. Event Tree Analysis (ETA), Fault Tree Analysis (FTA), Reliability Block Diagrams (RBD), and Markov models are examples of evaluation tools that can support the safety and risk assessment for analyzing process systems, identifying potential accidents, and estimating consequences. Because of complexity of such analyzes, specialized computer codes are required, such as the reliability engineering software develop by Reliasoft® Corporation. BlockSim (FTA, RBD and Markov models), RENO (ETA and consequence assessment), Weibull++ (life data and uncertainty analysis), and Xfmea (qualitative risk assessment) are some codes that can be highlighted. This work describes an integrated approach using these tools and software to carry out reliability, safety, and risk assessment of nuclear facilities, as well as, and application example. (author)

  14. Temporary septic holding tank at the 100-D remedial action support facility -- Engineering report. Revision 2

    International Nuclear Information System (INIS)

    Kelty, G.G.

    1996-10-01

    The primary mission of the Hanford Site from 1943 to 1990 was to produce nuclear materials for the national defense. Waste disposal activities associated with this mission resulted in the creation of more than 1,000 waste sites contaminated with radioactive and chemical constituents. Investigation and remediation of the wastes sites is governed by the Tri-Party Agreement. This agreement grouped the waste sites into 78 operable units, each of which was to be investigated and remediated separately. Once actual remediation activities begin at the waste sites, a central support facility will be required at each of the reactor areas (100-B/C, 100-D, and 100-H). These facilities will provide office and work space for the supervisors, engineers, and technicians engaged in the field work. The central facilities will be temporary, modular buildings sized to accommodate the anticipated staff, which in turn is determined by the scope of the planned remediation activities. The paper describes the project location, geology and flooding potential, design criteria, operation, and maintenance

  15. Design, fabrication and operation of the mechanical systems for the Neutral Beam Engineering Test Facility

    International Nuclear Information System (INIS)

    Paterson, J.A.; Biagi, L.A.; Fong, M.; Koehler, G.W.; Low, W.; Purgalis, P.; Wells, R.P.

    1983-12-01

    The Neutral Beam Engineering Test Facility (NBETF) at Lawrence Berkeley Laboratory (LBL) is a National Test Facility used to develop long pulse Neutral Beam Sources. The Facility will test sources up to 120 keV, 50 A, with 30 s beam-on times with a 10% duty factor. For this application, an actively cooled beam dump is required and one has been constructed capable of dissipating a wide range of power density profiles. The flexibility of the design is achieved by utilizing a standard modular panel design which is incorporated into a moveable support structure comprised of eight separately controllable manipulator assemblies. A unique neutralizer design has been installed into the NBETF beamline. This is a gun-drilled moveable brazed assembly which provides continuous armoring of the beamline near the source. The unit penetrates the source mounting valve during operation and retracts to permit the valve to close as needed. The beamline is also equpped with many beam scraper plates of differing detail design and dissipation capabilities

  16. Use of reliability engineering tools in safety and risk assessment of nuclear facilities

    International Nuclear Information System (INIS)

    Raso, Amanda Laureano; Vasconcelos, Vanderley de; Marques, Raíssa Oliveira; Soares, Wellington Antonio; Mesquita, Amir Zacarias

    2017-01-01

    Safety, reliability and availability are fundamental criteria in design, construction and operation of nuclear facilities, as nuclear power plants. Deterministic and probabilistic risk assessments of such facilities are required by regulatory authorities in order to meet licensing regulations, contributing to assure safety, as well as reduce costs and environmental impacts. Probabilistic Risk Assessment has become an important part of licensing requirements of the nuclear power plants in Brazil and in the world. Risk can be defined as a qualitative and/or quantitative assessment of accident sequence frequencies (or probabilities) and their consequences. Risk management is a systematic application of management policies, procedures and practices to identify, analyze, plan, implement, control, communicate and document risks. Several tools and computer codes must be combined, in order to estimate both probabilities and consequences of accidents. Event Tree Analysis (ETA), Fault Tree Analysis (FTA), Reliability Block Diagrams (RBD), and Markov models are examples of evaluation tools that can support the safety and risk assessment for analyzing process systems, identifying potential accidents, and estimating consequences. Because of complexity of such analyzes, specialized computer codes are required, such as the reliability engineering software develop by Reliasoft® Corporation. BlockSim (FTA, RBD and Markov models), RENO (ETA and consequence assessment), Weibull++ (life data and uncertainty analysis), and Xfmea (qualitative risk assessment) are some codes that can be highlighted. This work describes an integrated approach using these tools and software to carry out reliability, safety, and risk assessment of nuclear facilities, as well as, and application example. (author)

  17. Decontamination and decommissioning of the initial engine test facility and the IET two-inch hot-waste line

    International Nuclear Information System (INIS)

    Stoll, F.E.

    1987-04-01

    The Initial Engine Test Decommissioning Project is described in this report. The Initial Engine Test facility was constructed and operated at the National Reactor Testing Station, now known as the Idaho National Engineering Laboratory, to support the Aircraft Nuclear Propulsion Program and the Systems for Nuclear Auxiliary Power Transient test program, circa 1950 through 1960s. Due to the severe nature of these nuclear test programs, a significant amount of radioactive contamination was deposited in various portions of the Initial Engine Test Facility. Characterizations, decision analyses, and plans for decontamination and decommissioning were prepared from 1982 through 1985. Decontamination and decommissioning activities were performed in such a way that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory remains. These decontamination and decommissioning activities began in 1985 and were completed in 1987. 13 figs

  18. Initial closed operation of the CELSS Test Facility Engineering Development Unit

    Science.gov (United States)

    Kliss, M.; Blackwell, C.; Zografos, A.; Drews, M.; MacElroy, R.; McKenna, R.; Heyenga, A. G.

    2003-01-01

    As part of the NASA Advanced Life Support Flight Program, a Controlled Ecological Life Support System (CELSS) Test Facility Engineering Development Unit has been constructed and is undergoing initial operational testing at NASA Ames Research Center. The Engineering Development Unit (EDU) is a tightly closed, stringently controlled, ground-based testbed which provides a broad range of environmental conditions under which a variety of CELSS higher plant crops can be grown. Although the EDU was developed primarily to provide near-term engineering data and a realistic determination of the subsystem and system requirements necessary for the fabrication of a comparable flight unit, the EDU has also provided a means to evaluate plant crop productivity and physiology under controlled conditions. This paper describes the initial closed operational testing of the EDU, with emphasis on the hardware performance capabilities. Measured performance data during a 28-day closed operation period are compared with the specified functional requirements, and an example of inferring crop growth parameters from the test data is presented. Plans for future science and technology testing are also discussed. Published by Elsevier Science Ltd on behalf of COSPAR.

  19. The design status of the liquid lithium target facility of IFMIF at the end of the engineering design activities

    Energy Technology Data Exchange (ETDEWEB)

    Nitti, F.S., E-mail: francesco.nitti@enea.it [IFMIF/EVEDA Project Team, Rokkasho Japan (Japan); Ibarra, A. [CIEMAT, Madrid (Spain); Ida, M. [IHI Corporation, Tokyo (Japan); Favuzza, P. [ENEA Research Center Firenze (Italy); Furukawa, T. [JAEA Research Center, Tokai-mura, Ibaraki (Japan); Groeschel, F. [KIT Research Center, Karlsruhe (Germany); Heidinger, R. [F4E Research Center, Garching (Germany); Kanemura, T. [JAEA Research Center, Tokai-mura, Ibaraki (Japan); Knaster, J. [IFMIF/EVEDA Project Team, Rokkasho Japan (Japan); Kondo, H. [JAEA Research Center, Tokai-mura, Ibaraki (Japan); Micchiche, G. [ENEA Research Center, Brasimone (Italy); Sugimoto, M. [JAEA Research Center, Rokkasho Japan (Japan); Wakai, E. [JAEA Research Center, Tokai-mura, Ibaraki (Japan)

    2015-11-15

    Highlights: • Results of validation and design activity for the Li loop facility of IFMIF. • Demonstration of Li target stability, with surface disturbance <1 mm. • Demonstration of start-up and shut down procedures of Li loop. • Complete design of the heat removal system and C and O purification system. • Conceptual design of N and H isotopes purification systems. - Abstract: The International Fusion Material Irradiation Facility (IFMIF) is an experimental facility conceived for qualifying and characterizing structural materials for nuclear fusion applications. The Engineering Validation and Engineering Design Activity (EVEDA) is a fundamental step towards the final design. It presented two mandates: the Engineering Validation Activities (EVA), still on-going, and the Engineering Design Activities (EDA) accomplished on schedule in June 2013. Five main facilities are identified in IFMIF, among which the Lithium Target Facility constituted a technological challenge overcome thanks to the success of the main validation challenges impacting the design. The design of the liquid Lithium Target Facility at the end of the EDA phase is here detailed.

  20. The design status of the liquid lithium target facility of IFMIF at the end of the engineering design activities

    International Nuclear Information System (INIS)

    Nitti, F.S.; Ibarra, A.; Ida, M.; Favuzza, P.; Furukawa, T.; Groeschel, F.; Heidinger, R.; Kanemura, T.; Knaster, J.; Kondo, H.; Micchiche, G.; Sugimoto, M.; Wakai, E.

    2015-01-01

    Highlights: • Results of validation and design activity for the Li loop facility of IFMIF. • Demonstration of Li target stability, with surface disturbance <1 mm. • Demonstration of start-up and shut down procedures of Li loop. • Complete design of the heat removal system and C and O purification system. • Conceptual design of N and H isotopes purification systems. - Abstract: The International Fusion Material Irradiation Facility (IFMIF) is an experimental facility conceived for qualifying and characterizing structural materials for nuclear fusion applications. The Engineering Validation and Engineering Design Activity (EVEDA) is a fundamental step towards the final design. It presented two mandates: the Engineering Validation Activities (EVA), still on-going, and the Engineering Design Activities (EDA) accomplished on schedule in June 2013. Five main facilities are identified in IFMIF, among which the Lithium Target Facility constituted a technological challenge overcome thanks to the success of the main validation challenges impacting the design. The design of the liquid Lithium Target Facility at the end of the EDA phase is here detailed.

  1. Modelling of a Spark Ignition Engine for Power-Heat Production Optimization Modèle de moteur à allumage commandé en vue de l’optimisation de la production chaleur-force

    Directory of Open Access Journals (Sweden)

    Descieux D.

    2011-09-01

    Full Text Available Spark ignition gas engine is more and more used in order to produce electricity and heat simultaneously. The engine crankshaft drives a synchronous electric generator. The thermal power output is recovered from the engine coolant system and exhaust gas, and is used to produce generally hot water for heating system. In order to have a better adequacy between supply (production of the engine and user demand, good knowledge of the engine and implemented phenomena are necessary. A generic methodology is proposed to simulate the stationary state response of a SI engine. The engine simulation is based on a one zone thermodynamic model, which characterizes each phase of the engine cycle to predict energy performances: exergy efficiency as high as 0.70 is attainable. Le moteur a allumage commande alimente en gaz est un moteur de plus en plus utilise pour la production simultanee d’electricite et de chaleur. Classiquement le moteur entraine sur l’arbre une generatrice electrique. Le flux thermique est recupere principalement sur le systeme de refroidissement du moteur ainsi que sur les fumees chaudes et il est generalement utilise pour produire de la chaleur pour les systemes de chauffage. Pour avoir une meilleure adaptation entre la production du moteur et la demande de l’usager, une bonne connaissance des evolutions dans le moteur et des phenomenes correspondants est necessaire. Une methode thermodynamique generale est proposee pour simulation du fonctionnement dynamique stationnaire d’un MACI. Le modele utilise une analyse monozone et les caracteristiques de chaque transformation du cycle pour etudier les performances energetiques : rendement exergetique de l’ordre de 0,70.

  2. Physics goals for the planned next linear collider engineering test facility

    International Nuclear Information System (INIS)

    Bohn, C.; Michelotti, L.; Ostiguy, J.-F.; Syphers, M.; Bluem, H.; Todd, A.; Gai, W.; Power, J.; Simpson, J.; Raubenheimer, T.

    2001-01-01

    The Next Linear Collider (NLC) Collaboration is planning to construct an Engineering Test Facility (ETF) at Fermilab. As presently envisioned, the ETF would comprise a fundamental unit of the NLC main linac to include X-band klystrons and modulators, a delay-line power-distribution system (DLDS), and NLC accelerating structures that serve as loads. The principal purpose of the ETF is to validate stable operation of the power-distribution system, first without beam, then with a beam having the NLC pulse structure. This paper concerns the possibility of configuring and using the ETF to accelerate beam with an NLC pulse structure, as well as of doing experiments to measure beam-induced wakefields in the rf structures and their influence back on the beam

  3. Physics Goals for the Planned Next Linear Collider Engineering Test Facility

    International Nuclear Information System (INIS)

    Raubenheimer, Tor O

    2001-01-01

    The Next Linear Collider (NLC) Collaboration is planning to construct an Engineering Test Facility (ETF) at Fermilab. As presently envisioned, the ETF would comprise a fundamental unit of the NLC main linac to include X-band klystrons and modulators, a delay-line power-distribution system (DLDS), and NLC accelerating structures that serve as loads. The principal purpose of the ETF is to validate stable operation of the power distribution system, first without beam, then with a beam having the NLC pulse structure. This paper concerns the possibility of configuring and using the ETF to accelerate beam with an NLC pulse structure, as well as of doing experiments to measure beam-induced wakefields in the rf structures and their influence back on the beam

  4. Seismic engineering for an expanded tritium facility at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Volkman, D.E.; Olive, W.B.; Endebrocid, E.E.; Khan, P.K.; Rebillet, W.R.

    1997-10-01

    An existing complex of three single story concrete and masonry shear wall buildings will be integrated into an expanded tritium facility for neutron tube target loading. Known as the NTTL Project, the expanded plant is a major element of the Department of Energy's tritium program at the Los Alamos National Laboratory. This paper describes seismic evaluation and upgrade modifications for the 1950's concrete shear wall building; drift analyses of two 1980's CMU [concrete masonry unit] shear wall buildings; design of a new CMU shear wall building linking existing structures and providing personnel change room services; and design of a new steel frame building housing HVAC and electrical power and communication equipment for the complex. All buildings are closely adjacent and drift analysis to establish separation to prevent pounding is a major seismic engineering concern for the project

  5. Safety analysis report for the mixed waste storage facility and portable storage units at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Peatross, R.

    1997-01-01

    The Mixed Waste Storage Facility (MWSF) including the Portable Storage Units (PSUs) is a government-owned contractor-operated facility located at the Idaho National Engineering Laboratory (INEL). Lockheed Martin Idaho Technologies Company (LMITCO) is the current operating contractor and facility Architect/Engineer as of September 1996. The operating contractor is referred to as open-quotes the Companyclose quotes or open-quotes Companyclose quotes throughout this document. Oversight of MWSF is provided by the Department of Energy Idaho Operations Office (DOE-ID). The MWSF is located in the Power Burst Facility (PBF) Waste Reduction Operations Complex (WROC) Area, approximately 10.6 km (6.6 mi) from the southern INEL boundary and 4 km (2.5 mi) from U.S. Highway 20

  6. Preliminary Results From a Heavily Instrumented Engine Ice Crystal Icing Test in a Ground Based Altitude Test Facility

    Science.gov (United States)

    Flegel, Ashlie B.; Oliver, Michael J.

    2016-01-01

    Preliminary results from the heavily instrumented ALF502R-5 engine test conducted in the NASA Glenn Research Center Propulsion Systems Laboratory are discussed. The effects of ice crystal icing on a full scale engine is examined and documented. This same model engine, serial number LF01, was used during the inaugural icing test in the Propulsion Systems Laboratory facility. The uncommanded reduction of thrust (rollback) events experienced by this engine in flight were simulated in the facility. Limited instrumentation was used to detect icing on the LF01 engine. Metal temperatures on the exit guide vanes and outer shroud and the load measurement were the only indicators of ice formation. The current study features a similar engine, serial number LF11, which is instrumented to characterize the cloud entering the engine, detect/characterize ice accretion, and visualize the ice accretion in the region of interest. Data were acquired at key LF01 test points and additional points that explored: icing threshold regions, low altitude, high altitude, spinner heat effects, and the influence of varying the facility and engine parameters. For each condition of interest, data were obtained from some selected variations of ice particle median volumetric diameter, total water content, fan speed, and ambient temperature. For several cases the NASA in-house engine icing risk assessment code was used to find conditions that would lead to a rollback event. This study further helped NASA develop necessary icing diagnostic instrumentation, expand the capabilities of the Propulsion Systems Laboratory, and generate a dataset that will be used to develop and validate in-house icing prediction and risk mitigation computational tools. The ice accretion on the outer shroud region was acquired by internal video cameras. The heavily instrumented engine showed good repeatability of icing responses when compared to the key LF01 test points and during day-to-day operation. Other noticeable

  7. ALARA engineering at Department of Energy facilities: Bibliography of selected readings in radiation protection and ALARA

    International Nuclear Information System (INIS)

    Dionne, B.J.; Khan, T.A.; Lane, S.G.; Baum, J.W.

    1991-03-01

    This report is the second in the series of bibliographies supporting the efforts at the Brookhaven National Laboratory ALARA Center on dose reduction at US Department of Energy (DOE) facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the US Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE's Office of Environment, Safety and Health to include DOE nuclear facilities. Abstracts for this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy Data Base, and reprints of published articles provided by the authors. Information that the reader feels should be included in the next volume of this bibliography may be submitted to the BNL ALARA Center. These abstracts, which have a bearing on dose reduction, consolidates information from publications pertinent to Radiological Engineers and Operational Health Physicists. Volume 2 contains 127 abstracts numbered from 69 through 195 as well as author and subject indices. The subject index contains the abstract numbers from both the previous volume and the current volume, the latter being indicated in boldface

  8. Temporary septic holding tank at the 100-C remedial action support facility -- Engineering report

    International Nuclear Information System (INIS)

    Jackson, G.J.

    1996-08-01

    The primary mission of the Hanford Site from 1943 to 1990 was to produce nuclear materials for national defense. Waste disposal activities associated with this mission resulted in the creation of more than 1,000 waste sites contaminated with radioactive and chemically hazardous constituents. Investigation and remediation of these waste sites is governed by the Tri-Party Agreement. The agreement grouped the waste sites into 78 operable units, each of which was to be investigated and remediated separately. The 100 C Remedial Action Support Facility will be required near the 105-C Reactor to support the 105-C Interim Storage Project. This project is part of the decommissioning of the eight surplus reactor buildings along the Columbia River in the 100 Area. This facility, will be a temporary, modular building sized to provide office and work space for the supervisors, engineers, and technicians assigned to the project and engaged in the associated field work. This report describes the project location, geology and potential flooding, design criteria, operations, and maintenance

  9. Summary of facility and operating experience on helium engineering demonstration loop (HENDEL)

    Energy Technology Data Exchange (ETDEWEB)

    Ouchi, Yoshihiro; Fujisaki, Katsuo; Kobayashi, Toshiaki; Kato, Michio; Ota, Yukimaru; Watanabe, Syuji; Kobayashi, Hideki; Mogi, Haruyoshi [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    1996-07-01

    The HENDEL is a test facility to perform full scale demonstration tests on the core internals and high temperature components for the High Temperature Engineering Test Reactor(HTTR). The main systems consist of Mother(M) and Adapter(A), fuel stack Test(T{sub 1}) and in-core structure Test(T{sub 2}) sections. The (M+A) section can supply high temperature helium gas to the test section. The M+A section completed in March 1982 has been operated for about 22900 hours till February 1995. The T{sub 1} and T{sub 2} sections, completed in March 1983 and June 1986, have been operated for about 19400 and 16700 hours, respectively. In this period, a large number of tests have been conducted to verify the performance and safety features of the HTTR components. The results obtained from these tests have been effectively applied to the detailed design, licensing procedures and construction of the HTTR. The operating experience of the HENDEL for more than 10 years also brought us establishment of the technique of operation of a large scale helium gas loop, handling of helium gas and maintenance of high temperature facilities. The technique will be available for the operation of the HTTR. This paper mainly describes the summary of plant facirities, operating experience and maintenance on the HENDEL. (author)

  10. The design, fabrication and operation of the mechanical systems for the Neutral Beam Engineering Test Facility

    International Nuclear Information System (INIS)

    Patterson, J.A.; Fong, M.; Koehler, G.W.; Low, W.; Purgalis, P.; Wells, R.P.

    1983-01-01

    The Neutral Beam Engineering Test Facility (NBETF) at the Lawrence Berkeley Laboratory (LBL) is a National Test Facility used to develop long pulse Neutral Beam Sources. The Facility will test sources up to 120 keV, 50 A, with 30 s beam-on times with a 10% duty factor. For this application, an actively cooled beam dump is required and one has been constructed capable of dissipating a wide range of power density profiles. The flexibility of the design is achieved by utilizing a standard modular panel design which is incorporated into a moveable support structure comprised of eight separately controllable manipulator assemblies. The thermal hydraulic design of the panels permits the dissipation of 2 kW/cm 2 anywhere on the panel surface. The cooling water requirements of the actively cooled dump system are provided by the closed loop Primary High Pressure Cooling Water System. To minimize the operating costs of continuously running this high power system, a variable speed hydraulic drive is used for the main pump. During beam pulses, the pump rotates at high speed, then cycles to low speed upon completion of the beam shot. A unique neutralizer design has been installed into the NBETF beamline. This is a gun-drilled moveable brazed assembly which provides continuous armoring of the beamline near the source. The unit penetrates the source mounting valve during operation and retracts to permit the valve to close as needed. The beamline also has an inertially cooled duct calorimeter assembly. This assembly is a moveable hinged matrix of copper plates that can be used as a beam stop up to pulse lengths of 50 ms. The beamline is also equipped with many beam scraper plates of differing detail design and dissipation capabilities

  11. 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

  12. Engineering design of a fusion test reactor (FTR) and fusion engineering research facility (FERF) based on a toroidal theta pinch

    International Nuclear Information System (INIS)

    Abdou, M.; Burke, R.J.; Dauzvardis, P.V.; Foss, M.; Gerstl, S.A.W.; Maroni, V.A.; Pierce, A.W.; Turner, A.F.; Krakowski, R.A.; Linford, R.K.; Oliphant, T.A.; Ribe, F.L.; Thomassen, K.I.

    1975-01-01

    This paper describes two advanced toroidal theta-pinch devices which are being proposed for future construction. The Fusion Test Reactor (FTR) is being designed to produce thermonuclear energy (at 20 MeV/neutron) equal to the maximum plasma energy (Q=1) and to demonstrate α-particle heating. The Fusion Engineering and Research Facility (FERF) is being designed to test materials in a fusion environment where the average 14-MeV neutron flux from the plasma is greater than or of the order of 5.10 13 n/cm 2 .s over large surface areas. These devices employ the staged theta-pinch principle where the heating is accomplished by rapid (about 0.1 μs) implosion and expansion followed by a slow compression of the plasma. The rapid implosion injects as much heat as possible at as large a plasma radious as possible so that the plasma remains stable even after further compression. The final compression to ignition requires the transfer of a large amount of magnetic energy which implies a long transfer time (about 1 ms) for realistic voltages in the driving circuit. Throughout the heating and burn cycle the plasma must remain in equilibrium and stable to the dominant MHD-modes. A sufficiently large plasma radius guarantees stability against the m = 1 modes. These equilibrium and stability conditions and the requirements on thermonuclear burn determine the design parameters for either machine. The design parameters must also be consistent with economic limitations and technological feasibility of components. In addition to these requirements, the FERF must provide a steady and reliable source of fusion neutrons. (author)

  13. Environmental surveillance for EG ampersand G Idaho Waste Management facilities at the Idaho National Engineering Laboratory. 1993 annual report

    International Nuclear Information System (INIS)

    Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.; Borsella, B.W.

    1994-08-01

    This report describes calendar year 1993 environmental surveillance activities of Environmental Monitoring of EG ampersand G Idaho, Inc., performed at EG ampersand G Idaho operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1993 environmental surveillance data with US Department of Energy derived concentration guides and with data from previous years

  14. Annual report -- 1992: Environmental surveillance for EG ampersand G Idaho Waste Management Facilities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.

    1993-08-01

    This report describes the 1992 environmental surveillance activities of the Environmental Monitoring Unit of EG ampersand G Idaho, Inc., at EG ampersand G Idaho-operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are some results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1992 environmental surveillance data with DOE derived concentration guides, and with data from previous years

  15. Comprenhensive Program of Engineering and Geologic Surveys for Designing and Constructing Radioactive Waste Storage Facilities in Hard Rock Massifs

    International Nuclear Information System (INIS)

    Gupalo, T.; Milovidov, V.; Prokopoca, O.; Jardine, L.

    2002-01-01

    Geological, geophysical, and engineering-geological research conducted at the 'Yeniseisky' site obtained data on climatic, geomorphologic, geological conditions, structure and properties of composing rock, and conditions of underground water recharge and discharge. These results provide suficient information to make an estimate of the suitability of locating a radioactive waste (RW) underground isolation facility at the Nizhnekansky granitoid massif.

  16. Photovoltaic Engineering Testbed: A Facility for Space Calibration and Measurement of Solar Cells on the International Space Station

    Science.gov (United States)

    Landis, Geoffrey A.; Bailey, Sheila G.; Jenkins, Phillip; Sexton, J. Andrew; Scheiman, David; Christie, Robert; Charpie, James; Gerber, Scott S.; Johnson, D. Bruce

    2001-01-01

    The Photovoltaic Engineering Testbed ("PET") is a facility to be flown on the International Space Station to perform calibration, measurement, and qualification of solar cells in the space environment and then returning the cells to Earth for laboratory use. PET will allow rapid turnaround testing of new photovoltaic technology under AM0 conditions.

  17. Robot Task Commander with Extensible Programming Environment

    Science.gov (United States)

    Hart, Stephen W (Inventor); Yamokoski, John D. (Inventor); Wightman, Brian J (Inventor); Dinh, Duy Paul (Inventor); Gooding, Dustin R (Inventor)

    2014-01-01

    A system for developing distributed robot application-level software includes a robot having an associated control module which controls motion of the robot in response to a commanded task, and a robot task commander (RTC) in networked communication with the control module over a network transport layer (NTL). The RTC includes a script engine(s) and a GUI, with a processor and a centralized library of library blocks constructed from an interpretive computer programming code and having input and output connections. The GUI provides access to a Visual Programming Language (VPL) environment and a text editor. In executing a method, the VPL is opened, a task for the robot is built from the code library blocks, and data is assigned to input and output connections identifying input and output data for each block. A task sequence(s) is sent to the control module(s) over the NTL to command execution of the task.

  18. Army Aviation and the Mission Command Warfighting Function

    Science.gov (United States)

    2017-06-09

    information systems , processes and procedures, optimize facilities and equipment, and build understanding of the networks that link the headquarters...however further publication or sale of copyrighted images is not permissible. ii REPORT DOCUMENTATION PAGE Form Approved OMB No. 0704-0188...Command System , Mission Command Information Systems , Training, Mission Training Complex 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT

  19. Commander manipulator scoops prestigious mulit-million pound BNFL contract

    International Nuclear Information System (INIS)

    Bailey, Andrew.

    1997-01-01

    Twenty-one Commander robotic arms are on order from INBIS (formerly Ricardo Hitec) and BNFL Engineering Limited (''BEL'', the engineering arm of parent company BNFL). The multi-million pound contract was won amid fierce competition from other well-known names in robotic engineering. The specially designed Commander manipulators will be engaged in remotely handling Intermediate Level Waste (ILW) in a suite of four BNFL ILW plants, which are currently either under construction or planned at Sellafield. The first Commander will delivered to BNFL's Sellafield Silo Emptying Project in January 1998. (Author)

  20. Testing of the Engineering Model Electrical Power Control Unit for the Fluids and Combustion Facility

    Science.gov (United States)

    Kimnach, Greg L.; Lebron, Ramon C.; Fox, David A.

    1999-01-01

    The John H. Glenn Research Center at Lewis Field (GRC) in Cleveland, OH and the Sundstrand Corporation in Rockford, IL have designed and developed an Engineering Model (EM) Electrical Power Control Unit (EPCU) for the Fluids Combustion Facility, (FCF) experiments to be flown on the International Space Station (ISS). The EPCU will be used as the power interface to the ISS power distribution system for the FCF's space experiments'test and telemetry hardware. Furthermore. it is proposed to be the common power interface for all experiments. The EPCU is a three kilowatt 12OVdc-to-28Vdc converter utilizing three independent Power Converter Units (PCUs), each rated at 1kWe (36Adc @ 28Vdc) which are paralleled and synchronized. Each converter may be fed from one of two ISS power channels. The 28Vdc loads are connected to the EPCU output via 48 solid-state and current-limiting switches, rated at 4Adc each. These switches may be paralleled to supply any given load up to the 108Adc normal operational limit of the paralleled converters. The EPCU was designed in this manner to maximize allocated-power utilization. to shed loads autonomously, to provide fault tolerance. and to provide a flexible power converter and control module to meet various ISS load demands. Tests of the EPCU in the Power Systems Facility testbed at GRC reveal that the overall converted-power efficiency, is approximately 89% with a nominal-input voltage of 12OVdc and a total load in the range of 4O% to 110% rated 28Vdc load. (The PCUs alone have an efficiency of approximately 94.5%). Furthermore, the EM unit passed all flight-qualification level (and beyond) vibration tests, passed ISS EMI (conducted, radiated. and susceptibility) requirements. successfully operated for extended periods in a thermal/vacuum chamber, was integrated with a proto-flight experiment and passed all stability and functional requirements.

  1. Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de, E-mail: flavia.biaty@usp.br, E-mail: msrocha@ipen.br, E-mail: otavioluis@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

  2. Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

    International Nuclear Information System (INIS)

    Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de

    2017-01-01

    The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

  3. Strategic Global Climate Command?

    Science.gov (United States)

    Long, J. C. S.

    2016-12-01

    Researchers have been exploring geoengineering because Anthropogenic GHG emissions could drive the globe towards unihabitability for people, wildlife and vegetation. Potential global deployment of these technologies is inherently strategic. For example, solar radiation management to reflect more sunlight might be strategically useful during a period of time where the population completes an effort to cease emissions and carbon removal technologies might then be strategically deployed to move the atmospheric concentrations back to a safer level. Consequently, deployment of these global technologies requires the ability to think and act strategically on the part of the planet's governments. Such capacity most definitely does not exist today but it behooves scientists and engineers to be involved in thinking through how global command might develop because the way they do the research could support the development of a capacity to deploy intervention rationally -- or irrationally. Internationalizing research would get countries used to working together. Organizing the research in a step-wise manner where at each step scientists become skilled at explaining what they have learned, the quality of the information they have, what they don't know and what more they can do to reduce or handle uncertainty, etc. Such a process can increase societal confidence in being able to make wise decisions about deployment. Global capacity will also be enhanced if the sceintific establishment reinvents misssion driven research so that the programs will identify the systemic issues invovled in any proposed technology and systematically address them with research while still encouraging individual creativity. Geoengineering will diverge from climate science in that geoengineering research needs to design interventions for some publically desirable goal and investigates whether a proposed intervention will acheive desired outcomes. The effort must be a systems-engineering design problem

  4. Application of the finite element groundwater model FEWA to the engineered test facility

    International Nuclear Information System (INIS)

    Craig, P.M.; Davis, E.C.

    1985-09-01

    A finite element model for water transport through porous media (FEWA) has been applied to the unconfined aquifer at the Oak Ridge National Laboratory Solid Waste Storage Area 6 Engineered Test Facility (ETF). The model was developed in 1983 as part of the Shallow Land Burial Technology - Humid Task (ONL-WL14) and was previously verified using several general hydrologic problems for which an analytic solution exists. Model application and calibration, as described in this report, consisted of modeling the ETF water table for three specialized cases: a one-dimensional steady-state simulation, a one-dimensional transient simulation, and a two-dimensional transient simulation. In the one-dimensional steady-state simulation, the FEWA output accurately predicted the water table during a long period in which there were no man-induced or natural perturbations to the system. The input parameters of most importance for this case were hydraulic conductivity and aquifer bottom elevation. In the two transient cases, the FEWA output has matched observed water table responses to a single rainfall event occurring in February 1983, yielding a calibrated finite element model that is useful for further study of additional precipitation events as well as contaminant transport at the experimental site

  5. Engineering judgement and bridging the fire safety gap in existing nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Qamheiah, G.; Wu, Y., E-mail: gqamheiah@plcfire.com, E-mail: dwu@plcfire.com [PLC Fire Safety Solutions, Mississauga, ON (Canada)

    2014-07-01

    Canadian nuclear power plants were constructed in the 1960's through the 1980's. Fire safety considerations were largely based on guidance from general building and fire codes in effect at the time. Since then, nuclear specific fire safety standards have been developed and adopted by the Regulator, increasing the expected level of fire safety in the process. Application of the standards to existing plants was largely limited to operational requirements viewed as retroactive. However, as existing facilities undergo modifications or refurbishment for the purpose of life extension, the expectation is that the design requirements of these fire safety standards also be satisfied. This creates considerable challenges for existing nuclear power plants as fire safety requirements such as those intended to assure means for safe egress, prevention of fire spread and protection of redundancy rely upon fire protection features that are inherent in the physical infrastructural design. This paper focuses on the methodology for conducting fire safety gap analyses on existing plants, and the integral role that engineering judgement plays in the development of viable and cost effective solutions to achieve the objectives of the current fire safety standards. (author)

  6. Final report for the Idaho National Engineering Laboratory Central Facilities Area Landfill 2

    International Nuclear Information System (INIS)

    Doornbos, M.H.; Morgan, M.E.; Hubbell, J.M.

    1991-04-01

    This report summarize activities completed during FY-88 through FY-91 for the US Department of Energy's (DOE's) Hazardous Waste Remedial Actions Program (HAZWRAP) at the Idaho National Engineering Laboratory (INEL) Central Facilities Area (CFA) Landfill 2. The objectives of this program are to demonstrate new technologies or innovative uses of existing technologies for the identification and remediation of hazardous wastes within a municipal-type landfill. The site was chosen as a candidate site because it represents a problem typical of both DOE and public landfills. The HAZWRAP Technology Demonstration Project began at the INEL CFA Landfill 2 in 1987. During characterization and identification activities, several organic ''hotspots'' or anomalies were identified. Proposals were then solicited from the private sector for innovative technologies to remediate the isolated areas. Remediation was planned to be implemented using horizontal wells installed underneath a portion of the landfill. These innovative technologies and the well installation were planned to support the current goals of the DOE and the Environmental Protection Agency to treat hazardous waste in place. 2 refs., 2 figs., 2 tabs

  7. 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.

  8. Preliminary siting criteria for the proposed mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Jorgenson-Waters, M.

    1992-09-01

    The Mixed and Low-Level Waste Treatment Facility project was established in 1991 by the US Department of Energy Idaho Field Office. This facility will provide treatment capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This report identifies the siting requirements imposed on facilities that treat and store these waste types by Federal and State regulatory agencies and the US Department of Energy. Site selection criteria based on cost, environmental, health and safety, archeological, geological and service, and support requirements are presented. These criteria will be used to recommend alternative sites for the new facility. The National Environmental Policy Act process will then be invoked to evaluate the alternatives and the alternative sites and make a final site determination

  9. Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns.

  10. Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

    International Nuclear Information System (INIS)

    1997-01-01

    This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns

  11. AFRICOM: Combatant Command for the 21st Century

    National Research Council Canada - National Science Library

    Juergens, Jr., Richard A

    2008-01-01

    ...: European Command, Southern Command, Northern Command, Central Command, and Pacific Command, as the Department of Defense's unified command structure responsible for specific geographical regions of the world...

  12. Implementing UPDM to develop command and control systems

    CSIR Research Space (South Africa)

    Oosthuizen, R

    2016-09-01

    Full Text Available Systems engineering is an established approach to develop systems, including complex sociotechnical systems such as Command and Control (C2) Systems. These systems often occur through introduction of a new technology into an existing system...

  13. Linde FUSRAP Site Remediation: Engineering Challenges and Solutions of Remedial Activities on an Active Industrial Facility - 13506

    International Nuclear Information System (INIS)

    Beres, Christopher M.; Fort, E. Joseph; Boyle, James D.

    2013-01-01

    The Linde FUSRAP Site (Linde) is located in Tonawanda, New York at a major research and development facility for Praxair, Inc. (Praxair). Successful remediation activities at Linde combines meeting cleanup objectives of radiological contamination while minimizing impacts to Praxair business operations. The unique use of Praxair's property coupled with an array of active and abandoned utilities poses many engineering and operational challenges; each of which has been overcome during the remedial action at Linde. The U.S. Army Corps of Engineers - Buffalo District (USACE) and CABRERA SERVICES, INC. (CABRERA) have successfully faced engineering challenges such as relocation of an aboveground structure, structural protection of an active water line, and installation of active mechanical, electrical, and communication utilities to perform remediation. As remediation nears completion, continued success of engineering challenges is critical as remaining activities exist in the vicinity of infrastructure essential to business operations; an electrical substation and duct bank providing power throughout the Praxair facility. Emphasis on engineering and operations through final remediation and into site restoration will allow for the safe and successful completion of the project. (authors)

  14. Linde FUSRAP Site Remediation: Engineering Challenges and Solutions of Remedial Activities on an Active Industrial Facility - 13506

    Energy Technology Data Exchange (ETDEWEB)

    Beres, Christopher M.; Fort, E. Joseph [Cabrera Services, Inc., 473 Silver Lane, East Hartford, CT 06118 (United States); Boyle, James D. [United States Army Corps of Engineers - Buffalo, 1776 Niagara Street, Buffalo, NY 14207 (United States)

    2013-07-01

    The Linde FUSRAP Site (Linde) is located in Tonawanda, New York at a major research and development facility for Praxair, Inc. (Praxair). Successful remediation activities at Linde combines meeting cleanup objectives of radiological contamination while minimizing impacts to Praxair business operations. The unique use of Praxair's property coupled with an array of active and abandoned utilities poses many engineering and operational challenges; each of which has been overcome during the remedial action at Linde. The U.S. Army Corps of Engineers - Buffalo District (USACE) and CABRERA SERVICES, INC. (CABRERA) have successfully faced engineering challenges such as relocation of an aboveground structure, structural protection of an active water line, and installation of active mechanical, electrical, and communication utilities to perform remediation. As remediation nears completion, continued success of engineering challenges is critical as remaining activities exist in the vicinity of infrastructure essential to business operations; an electrical substation and duct bank providing power throughout the Praxair facility. Emphasis on engineering and operations through final remediation and into site restoration will allow for the safe and successful completion of the project. (authors)

  15. Engineering Evaluation/Cost Analysis for Power Burst Facility (PER-620) Final End State and PBF Vessel Disposal

    Energy Technology Data Exchange (ETDEWEB)

    B. C. Culp

    2007-05-01

    Preparation of this engineering evaluation/cost analysis is consistent with the joint U.S. Department of Energy and U.S. Environmental Protection Agency Policy on Decommissioning of Department of Energy Facilities Under the Comprehensive Environmental Response, Compensation, and Liability Act, (DOE and EPA 1995) which establishes the Comprehensive Environmental, Response, Compensation, and Liability Act non-time critical removal action process as an approach for decommissioning. The scope of this engineering evaluation/cost analysis is to evaluate alternatives and recommend a preferred alternative for the final end state of the PBF and the final disposal location for the PBF vessel.

  16. A Review on the Regulatory Strategy of Human Factors Engineering Consideration in Pakistan Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sohail, Sabir [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Choi, Seong Nam [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    In this paper, the legal and regulatory infrastructure available in Pakistan for HFE requirements is assessed, and the methodology for strengthening of legal infrastructure is presented. The regulatory strategy on evaluation of HFE consideration should provide reviewers with guidance on review process. Therefore, the suggested methodology is based on preparation of guidance documents such as checklist, working procedures, S and Gs etc.; incorporation of PRM elements in regulatory system; and finally the development of PRM implementation criteria. Altogether, the scheme provide the enhancement in regulatory infrastructure and also the effective and efficient review process. The Three Mile Island (TMI) accident brought the general consensus among the nuclear community on the integration of human factors engineering (HFE) principles in all phases of nuclear power. This notion has further strengthened after the recent Fukushima nuclear accident. Much effort has been put over to incorporate the lesson learned and continuous technical evolution on HFE to device different standards. The total of 174 ergonomics standards are alone identified by Dul et al. (2004) published by International Organization for Standardization (ISO) and the European Committee for Standardization (CEN) and number of standards and HFE guidelines (S and Gs) are also published by organizations like Institute for Electrical and Electronics Engineering (IEEE), International Electrotechnical Commission (IEC), International Atomic Energy Agency (IAEA), United States Nuclear Regulatory Commission (USNRC), etc. The ambition of effective review on HFE integration in nuclear facility might be accomplished through the development of methodology for systematic implementation of S and Gs. Such kind of methodology would also be beneficial for strengthening the regulatory framework and practices for countries new in the nuclear arena and with small scale nuclear program. The objective of paper is to review the

  17. Quality assurance during construction of civil engineering structures important to safety of nuclear facilities

    International Nuclear Information System (INIS)

    2011-11-01

    The present manual is developed to deal with quality assurance aspect of civil engineering structures in a greater detail. This manual gives detail to develop QA plans specific to multifarious activities of civil engineering construction

  18. Fault detection and protection system for neutral beam generators on the Neutral Beam Engineering Test Facility (NBETF)

    International Nuclear Information System (INIS)

    deVries, G.J.; Chesley, K.L.; Owren, H.M.

    1983-12-01

    Neutral beam sources, their power supplies and instrumentation can be damaged from high voltage sparkdown or from overheating due to excessive currents. The Neutral Beam Engineering Test Facility (NBETF) in Berkeley has protective electronic hardware that senses a condition outside a safe operating range and generates a response to terminate such a fault condition. A description of this system is presented in this paper. 8 references, 2 figures, 2 tables

  19. 78 FR 67180 - Federal Property Suitable as Facilities To Assist the Homeless

    Science.gov (United States)

    2013-11-08

    ... Navy, Asset Management Division, Naval Facilities Engineering Command, Washington Navy Yard, 1330...: Landholding Agency- US Forest Service Disposal Agency- GSA Comments: 53.6 acres; agricultural/research...- GSA Comments: 54.8 acres; agricultural/research; Sec. 106 Nat'l Historic review required to transfer...

  20. SOA approach to battle command: simulation interoperability

    Science.gov (United States)

    Mayott, Gregory; Self, Mid; Miller, Gordon J.; McDonnell, Joseph S.

    2010-04-01

    NVESD is developing a Sensor Data and Management Services (SDMS) Service Oriented Architecture (SOA) that provides an innovative approach to achieve seamless application functionality across simulation and battle command systems. In 2010, CERDEC will conduct a SDMS Battle Command demonstration that will highlight the SDMS SOA capability to couple simulation applications to existing Battle Command systems. The demonstration will leverage RDECOM MATREX simulation tools and TRADOC Maneuver Support Battle Laboratory Virtual Base Defense Operations Center facilities. The battle command systems are those specific to the operation of a base defense operations center in support of force protection missions. The SDMS SOA consists of four components that will be discussed. An Asset Management Service (AMS) will automatically discover the existence, state, and interface definition required to interact with a named asset (sensor or a sensor platform, a process such as level-1 fusion, or an interface to a sensor or other network endpoint). A Streaming Video Service (SVS) will automatically discover the existence, state, and interfaces required to interact with a named video stream, and abstract the consumers of the video stream from the originating device. A Task Manager Service (TMS) will be used to automatically discover the existence of a named mission task, and will interpret, translate and transmit a mission command for the blue force unit(s) described in a mission order. JC3IEDM data objects, and software development kit (SDK), will be utilized as the basic data object definition for implemented web services.

  1. Monitored retrievable storage (MRS) facility and salt repository integration: Engineering study report

    International Nuclear Information System (INIS)

    1987-07-01

    This MRS Facility and Salt Repository Integration Study evaluates the impacts of an integrated MRS/Salt Repository Waste Management System on the Salt Repository Surface facilities' design, operations, cost, and schedule. Eight separate cases were studied ranging from a two phase repository design with no MRS facility to a design in which the repository only received package waste from the MRS facility for emplacement. The addition of the MRS facility to the Waste Management System significantly reduced the capital cost of the salt repository. All but one of the cases studied were capable of meeting the waste acceptance data. The reduction in the size and complexity of the Salt Repository waste handling building with the integration of the MRS facility reduces the design and operating staff requirements. 7 refs., 35 figs., 43 tabs

  2. Command History for 1990

    Science.gov (United States)

    1991-05-01

    Marine Corps Tiaining Systems (CBESS) memorization training Inteligence Center, Dam Neck Threat memorization training Commander Tactical Wings, Atlantic...News Shipbuilding Technical training AEGIS Training Center, Dare Artificial Intelligence (Al) Tools Computerized firm-end analysis tools NETSCPAC...Technology Department and provides computational and electronic mail support for research in areas of artificial intelligence, computer-assisted instruction

  3. Command Home Page

    Science.gov (United States)

    Inclusion And Diversity Navy Standard Integrated Personnel System (NSIPS) My Navy Portal Board of One Source USA.gov U.S. Office of Special Counsel Social Media Directory and Policy US Navy App Locker Navy Personnel Command (NPC) Navy SAPR Navy EEO Inclusion And Diversity Navy Standard Integrated

  4. Command and Control Software Development

    Science.gov (United States)

    Wallace, Michael

    2018-01-01

    The future of the National Aeronautics and Space Administration (NASA) depends on its innovation and efficiency in the coming years. With ambitious goals to reach Mars and explore the vast universe, correct steps must be taken to ensure our space program reaches its destination safely. The interns in the Exploration Systems and Operations Division at the Kennedy Space Center (KSC) have been tasked with building command line tools to ease the process of managing and testing the data being produced by the ground control systems while its recording system is not in use. While working alongside full-time engineers, we were able to create multiple programs that reduce the cost and time it takes to test the subsystems that launch rockets to outer space.

  5. Factors Affecting Navy Working Capital Funding (NWCF) Net Operating Result: A Case Study of Naval Facilities Engineering Command Washington, Washington D.C.

    Science.gov (United States)

    2009-12-01

    44 Figure 17. Average Retail Price of Electricity Sold by Sector, 1960–2007 (From: http://www.eia.doe.gov/ bookshelf /brochures/epa...Sold by Sector, 1960–2007 (From: http://www.eia.doe.gov/ bookshelf /brochures/epa/epa.html) All three illustrations, with the exception of the sharp... bookshelf /brochures/epa/epa.html 72 Fawls, C. (2006). Issues and unexplored opportunities within the navy working capital fund. Defense AT&L, 35(3), 38

  6. Integrated Human Test Facilities at NASA and the Role of Human Engineering

    Science.gov (United States)

    Tri, Terry O.

    2002-01-01

    Integrated human test facilities are a key component of NASA's Advanced Life Support Program (ALSP). Over the past several years, the ALSP has been developing such facilities to serve as a large-scale advanced life support and habitability test bed capable of supporting long-duration evaluations of integrated bioregenerative life support systems with human test crews. These facilities-targeted for evaluation of hypogravity compatible life support and habitability systems to be developed for use on planetary surfaces-are currently in the development stage at the Johnson Space Center. These major test facilities are comprised of a set of interconnected chambers with a sealed internal environment, which will be outfitted with systems capable of supporting test crews of four individuals for periods exceeding one year. The advanced technology systems to be tested will consist of both biological and physicochemical components and will perform all required crew life support and habitability functions. This presentation provides a description of the proposed test "missions" to be supported by these integrated human test facilities, the overall system architecture of the facilities, the current development status of the facilities, and the role that human design has played in the development of the facilities.

  7. 32 CFR 724.406 - Commander, Naval Medical Command.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 5 2010-07-01 2010-07-01 false Commander, Naval Medical Command. 724.406 Section 724.406 National Defense Department of Defense (Continued) DEPARTMENT OF THE NAVY PERSONNEL NAVAL DISCHARGE REVIEW BOARD Principal Elements of the Navy Department Discharge Review System § 724.406 Commander...

  8. Weapons Engineering Tritium Facility, Building 205, Technical Area 16: Los Alamos National Laboratory, Los Alamos, New Mexico

    International Nuclear Information System (INIS)

    1991-04-01

    The Weapons Engineering Tritium Facility (WETF) was planned by the US Department of Energy (DOE) to retain at Los Alamos National Laboratory the capability of repackaging small quantities of tritium to exacting specifications. Small quantities of tritium are required for energy research and development activities and for research on nuclear weapons test devices carried out as part of the laboratory mission. The WETF is an improved design proposed to replace an aging Los Alamos facility where tritium has been repackaged for many years. This Environmental Assessment evaluates the environmental consequences to be expected from operating the new facility, for which construction was completed in 1984, compared with those from continuing to operate the old facility. The document was prepared for compliance with NEPA. In operation, the WETF will incorporate state-of-the-art systems for containing tritium in glove boxes and capturing any tritium released into the glove box exhaust system and the laboratory atmosphere. Liquid discharges from the WETF would contain less than 1% of the tritium found in effluents from the present facility. Effluent streams would be surface discharges and would not enter the aquifer from which municipal water supplies are drawn. The quantity of solid radioactive waste generated at the WETF would be approximately the same as that generated at the present facility. The risk to the public from normal tritium-packaging operations would be significantly less from the WETF than from the present facility. The proposed action will reduce the adverse environmental impacts caused by tritium repackaging by substantially reducing the amount of tritium that escapes to the environment. 35 refs., 3 figs., 21 tabs

  9. Combatant Commanders Informational Series, USEUCOM

    National Research Council Canada - National Science Library

    Burton, Steven

    1996-01-01

    ...) and the diverse challenges it faces require it to maintain one of the highest operational and personnel tempos of the combatant command, are limited in the opportunity of personnel new to the command...

  10. Field test facility for monitoring water/radionuclide transport through partially saturated geologic media: design, construction, and preliminary description. Appendix I. Engineering drawings

    International Nuclear Information System (INIS)

    Phillips, S.J.; Campbell, A.C.; Campbell, M.D.; Gee, G.W.; Hoober, H.H.; Schwarzmiller, K.O.

    1979-11-01

    The engineering plans for a test facility to monitor radionuclide transport in water through partially saturated geological media are included. Drawings for the experimental set-up excavation plan and details, lysimeter, pad, access caisson, and caisson details are presented

  11. Problems of development and putting into education process an electronic textbook on special discipline 'General theory and construction of heat-and-power engineering facilities'

    International Nuclear Information System (INIS)

    Karitskaya, S.G.; Ruzanov, K.A.; Davletov, V.S.

    2005-01-01

    The results of work of making the electronic textbook of special discipline ('General theory and construction of heat-and-power engineering facilities' are brought. The principles and requirements, presented towards literature of such type, are outlined. (author)

  12. Thermal performance analysis of Brayton cycle with waste heat recovery boiler for diesel engines of offshore oil production facilities

    International Nuclear Information System (INIS)

    Liu, Xianglong; Gong, Guangcai; Wu, Yi; Li, Hangxin

    2016-01-01

    Highlights: • Comparison of Brayton cycle with WHRB adopted in diesel engines with and without fans by thermal performance. • Waste heat recovery technology for FPSO. • The thermoeconomic analysis for the heat recovery for FPSO. - Abstract: This paper presents the theoretical analysis and on-site testing on the thermal performance of the waste heat recovery system for offshore oil production facilities, including the components of diesel engines, thermal boilers and waste heat boilers. We use the ideal air standard Brayton cycle to analyse the thermal performance. In comparison with the traditional design, the fans at the engine outlet of the waste heat recovery boiler is removed due to the limited space of the offshore platform. The cases with fan and without fan are compared in terms of thermal dynamics performance, energy efficiency and thermo-economic index of the system. The results show that the application of the WHRB increases the energy efficiency of the whole system, but increases the flow resistance in the duct. It is proved that as the waste heat recovery boiler takes the place of the thermal boiler, the energy efficiency of whole system without fan is slightly reduced but heat recovery efficiency is improved. This research provides an important guidance to improve the waste heat recovery for offshore oil production facilities.

  13. Command and motivation

    DEFF Research Database (Denmark)

    Jacobsen, Christian Bøtcher; Hvidtved, Johan; Andersen, Lotte Bøgh

    2014-01-01

    Motivated employees are crucial to organizations, but external interventions such as command systems and financial incentives may decrease motivation. If these external interventions are perceived to be controlling, they are expected to crowd out intrinsic motivation, and this may also apply...... to other types of autonomous motivation such as public service motivation. The perception of external interventions is thus expected to be vital. This article investigates how the perception of a specific command system (obligatory student plans) is associated with intrinsic motivation and public service...... motivation. Using a dataset with 3,230 school teachers in Denmark, a structural equation model shows that the perception of obligatory student plans as controlling is negatively associated with all of the investigated types of employee motivation, supporting that motivation crowding can occur....

  14. Joint Mission Command Implementation

    Science.gov (United States)

    2016-01-22

    choose. The paper finds that trust is strongly influenced by the subconscious brain and treating it like a tool ignores biology and results in... bias for action and empowerment.14 Since then, the services have evaluated their own concepts of command assessing them against Dempsey’s vision. Lt...understanding, intent, and trust, only trust is strongly influenced by the subconscious brain. Treating trust like it can be taught, or a behavior that

  15. Site selection and design basis of the National Disposal Facility for LILW. Geological and engineering barriers

    International Nuclear Information System (INIS)

    Boyanov, S.

    2010-01-01

    Content of the presentation: Site selection; Characteristics of the “Radiana” site (location, geological structure, physical and mechanical properties, hydro-geological conditions); Design basis of the Disposal Facility; Migration analysis; Safety assessment approach

  16. Engineering report for interim solids removal modifications of the Steam Plant Wastewater Treatment Facility

    International Nuclear Information System (INIS)

    1995-04-01

    The Steam Plant Wastewater Treatment Facility (SPWTF) treats wastewater from the Y-12 Plant coal yard, steam plant, and water demineralizer facility. The facility is required to comply with National Pollutant Discharge Elimination System (NPDES) standards prior to discharge to East Fork Poplar Creek (EFPC). The existing facility was designed to meet Best Available Technology (BAT) standards and has been in operation since 1988. The SPWTF has had intermittent violations of the NPDES permit primarily due to difficulties in complying with the limit for total iron of 1.0 ppM. A FY-1997 Line Item project, SPWTF Upgrades, is planned to improve the capabilities of the SPWTF to eliminate non-compliances with the permit limits. The intent of the Interim Solids Removal Modification project is to improve the SPWTF effluent quality and to provide pilot treatment data to assist in the design and implementation of the SPWTF Upgrades Line Item Project

  17. Engineering and technology in the deconstruction of nuclear materials production facilities

    International Nuclear Information System (INIS)

    Kingsley, R.S.; Reynolds, W.E.; Heffner, D.C.

    1996-01-01

    Technology and equipment exist to support nuclear facility deactivation, decontamination, and decommissioning. In reality, this statement is not surprising because the nuclear industry has been decontaminating and decommissioning production plants for decades as new generations of production technology were introduced. Since the 1950s, the Babcock and Wilcox Company (B ampersand W) has operated a number of nuclear materials processing facilities to manufacture nuclear fuel for the commercial power industry and the U.S. Navy. These manufacturing facilities included a mixed oxide (PuO 2 -UO 2 ) nuclear fuel manufacturing plant, low- and high-enriched uranium (HEU/LEU) chemical and fuel plants, and fuel assembly plants. In addition, B ampersand W designed and build a major nuclear research center in Lynchburg, Virginia, to support these nuclear fuel manufacturing activities and to conduct nuclear power research. These nuclear research facilities included two research reactors, a hot-cell complex for nuclear materials research, four critical experiment facilities, and a plutonium fuels research and development facility. This article describes the B ampersand W deactivation, decomtanimation, and decommisioning program

  18. Tank Closure Progress at the Department of Energy's Idaho National Engineering Laboratory Tank Farm Facility

    International Nuclear Information System (INIS)

    Butterworth, St.W.; Shaw, M.R.

    2009-01-01

    Significant progress continued at the U.S. Department of Energy (DOE) Idaho National Laboratory (INL) with the completion of the closure process to empty, clean and close radioactive liquid waste storage tanks at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF). The TFF includes eleven 1,135.6-kL (300,000-gal) underground stainless steel storage tanks and four smaller, 113.5-kL (30,000-gal) stainless steel tanks, along with tank vaults, interconnecting piping, and ancillary equipment. The TFF tanks had historically been used to store a variety of radioactive liquid waste, including wastes associated with past spent nuclear fuel reprocessing. Four of the large storage tanks remain in use for waste storage while the other seven 1,135.6-kL (300,000-gal) tanks and the four 113.5-kL (30,000-gal) tanks have been emptied of waste, cleaned and filled with grout. Recent issuance of an Amended Record of Decision (ROD) in accordance with the National Environmental Policy Act, and a Waste Determination complying with Section 3116 of the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, allowed commencement of grouting activities on the cleaned tanks. The first three 113.5-kL (30,000-gal) tanks were grouted in the Fall of 2006 and the fourth tank and the seven 1,135.6-kL (300,000-gal) tanks were filled with grout in 2007 to provide long-term stability. During 2008 over seven miles of underground process piping along with associated tank valve boxes and secondary containment systems was stabilized with grout. Lessons learned were compiled and implemented during the closure process and will be utilized on the remaining four 1,135.6-kL (300,000-gal) underground stainless steel storage tanks. Significant progress has been made to clean and close emptied tanks at the INTEC TFF. Between 2002 and 2005, seven of the eleven 1,135.6-kL (300,000-gal) tanks and all four 113.5-kL (30,000-gal) tanks were cleaned and prepared

  19. The estimation of the amount of radioactive waste from decommissioning of the nuclear facilities in Oarai Engineering Center

    International Nuclear Information System (INIS)

    Tanimoto, Kenichi; Aihara, Nagafumi; Imai, Katutomo; Tobita, Kazunori; Nemoto, Masaaki; Imahori, Shinji; Noguchi, Kouichi; Hasegawa, Makoto

    1998-11-01

    The estimation of the amount of radioactive waste produced from nuclear facilities in Oarai Engineering Center was performed for the purpose of using it for countermeasure of decommissioning planning. The conditions and the result of the estimation are as follows; (1) The total amount of occurrence of radioactive waste is 18,820 tons. As the items of the amount in radioactive level, the amount of 1 GBq/t and over is 820 tons and that of under 1 GBq/t is 18,000 tons. (2) The amount of metal waste is 5,820 tons and the amount of concrete is 13,000 tons. (3) Above calculation was based on related specifications, complete drawings, and visual observation. (4) To dismantle facilities, if must exfoliate the surface of wall. As for the polluted zone and the zone with possibility of pollution, it decided to exfoliate 5 cm in thickness from the surface of the wall. And, as for the zone that fundamentally pollution was not there, it decided to exfoliate surface 1 cm in thickness from the surface of the wall. (5) Using the suitable decontamination technology and exfoliation technology can reduce the amount of radioactive waste. (6) In the facilities dealing with sealed source judging from the past record of operation, there is no contact with the radioactive material, etc. Therefore, it can be disposed of all the waste that comes out from the facilities as non-radioactive waste. (author)

  20. Engineering evaluation cost analysis for the 100-B/C area ancillary facilities at the 108-F Building

    International Nuclear Information System (INIS)

    1996-10-01

    In 1995, the US Department of Energy (DOE), Richland Operations Office (RL) conducted a removal site evaluation of selected facilities in the 100 Area of the Hanford Site in accordance with CERCLA and 40 Code of Federal Regulations (CFR) 300.410. The scope of the evaluation included the aboveground portions of the 108-F Biology Laboratory in the 100-F Area and all inactive ancillary buildings and structures in the 100-B/C Area, excluding the reactor building and the river outfall. Based on the evaluation, RL determined that hazardous substances in the 108-F Biology Laboratory and five of the 100-B/C Area facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. This determination was documented in an engineering evaluation/cost analysis (EE/CA) approval memorandum. The EE/CA approval memorandum is the basis on which to proceed with the performance of an EE/CA to determine the appropriate removal action. This report presents the results of the EE/CA for removal alternatives for final disposition of these six facilities. The EE/CA was conducted pursuant to the requirements of CERCLA and 40 CFR 300.415 and is intended to aid RL and the EPA in selecting a preferred removal action

  1. Testing of a Liquid Oxygen/Liquid Methane Reaction Control Thruster in a New Altitude Rocket Engine Test Facility

    Science.gov (United States)

    Meyer, Michael L.; Arrington, Lynn A.; Kleinhenz, Julie E.; Marshall, William M.

    2012-01-01

    A relocated rocket engine test facility, the Altitude Combustion Stand (ACS), was activated in 2009 at the NASA Glenn Research Center. This facility has the capability to test with a variety of propellants and up to a thrust level of 2000 lbf (8.9 kN) with precise measurement of propellant conditions, propellant flow rates, thrust and altitude conditions. These measurements enable accurate determination of a thruster and/or nozzle s altitude performance for both technology development and flight qualification purposes. In addition the facility was designed to enable efficient test operations to control costs for technology and advanced development projects. A liquid oxygen-liquid methane technology development test program was conducted in the ACS from the fall of 2009 to the fall of 2010. Three test phases were conducted investigating different operational modes and in addition, the project required the complexity of controlling propellant inlet temperatures over an extremely wide range. Despite the challenges of a unique propellant (liquid methane) and wide operating conditions, the facility performed well and delivered up to 24 hot fire tests in a single test day. The resulting data validated the feasibility of utilizing this propellant combination for future deep space applications.

  2. Fonctionnement transitoire et controle de la richesse des moteurs à allumage commandé à injection multipoint Transient Operation and Air-Fuel Ratio Control of Spark-Ignition Port-Injected Engines

    Directory of Open Access Journals (Sweden)

    Le Moyne L.

    2006-12-01

    Full Text Available Sur les moteurs à allumage commandé à injection multipoint on observe des désadaptations de richesse lors de fonctionnement transitoire. Ces désadaptations sont dues au dépôt, sous forme de film liquide, du carburant injecté dans le collecteur. Elles peuvent être compensées par une gestion adéquate de la masse injectée. Ainsi, afin d'obtenir la masse de carburant qui maintient la richesse constante, nous avons développé un modèle bidimensionnel des écoulements dans le collecteur au cours du cycle moteur. Ce modèle décrit l'écoulement des gaz frais, des gouttes injectées, des gaz brûlés refoulés vers l'admission et du film sur les parois, sur le principe de la séparation des phases. Nous montrons que le modèle reproduit correctement le signal de richesse et comment il permet de supprimer les désadaptations. La mesure de richesse est faite à l'échappement avec une sonde à oxygène dont nous validons le fonctionnement en transitoire avec une corrélation à la pression maximale du cycle dans le cylindre. Air-fuel ratio excursions are observed on port-injected spark ignition engines during transients. This excursions result from the liquid fuel film deposited on intake port. They can be compensated by controlling the injected fuel mass. In order to have the amount of fuel that keeps air-fuel ratio constant, we have developed a 2D model of flows in the intake port during engine cycle. This separate phases model describes the flow of fresh gases, injected droplets, hot burned gases and film on port walls. We show that the model effectively predicts the equivalence ratio and how it allows to eliminate excursions. Equivalence ratio measures are made with an oxygen sensor which functioning is validated during transients by correlating it to maximal pressure during engine cycle.

  3. Design and utilization of a Flight Test Engineering Database Management System at the NASA Dryden Flight Research Facility

    Science.gov (United States)

    Knighton, Donna L.

    1992-01-01

    A Flight Test Engineering Database Management System (FTE DBMS) was designed and implemented at the NASA Dryden Flight Research Facility. The X-29 Forward Swept Wing Advanced Technology Demonstrator flight research program was chosen for the initial system development and implementation. The FTE DBMS greatly assisted in planning and 'mass production' card preparation for an accelerated X-29 research program. Improved Test Plan tracking and maneuver management for a high flight-rate program were proven, and flight rates of up to three flights per day, two times per week were maintained.

  4. ENGINEERING STUDY FOR THE 200 AREA EFFLUENT TREATMENT FACILITY (ETF) SECONDARY WASTE TREATMENT OF PROJECTED FUTURE WASTE FEEDS

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2004-01-01

    This report documents an engineering study conducted to evaluate alternatives for treating secondary waste in the secondary treatment train (STT) of the Hanford Site 200 Area Effluent Treatment Facility (ETF). The study evaluates ETF STT treatment alternatives and recommends preferred alternatives for meeting the projected future missions of the ETF. The preferred alternative(s) will process projected future ETF influents to produce a solid waste acceptable for final disposal on the Hanford Site. The main text of this report summarizes the ETF past and projected operations, lists the assumptions about projected operations that provide the basis for the engineering evaluation, and summarizes the evaluation process. The evaluation process includes identification of available modifications to the current ETF process, screens those modifications for technical viability, evaluates the technically viable alternatives, and provides conclusions and recommendations based on that evaluation

  5. Magnetohydrodynamics MHD Engineering Test Facility ETF 200 MWe power plant. Conceptual Design Engineering Report CDER. Volume 3: Costs and schedules

    Science.gov (United States)

    1981-01-01

    The estimated plant capital cost for a coal fired 200 MWE electric generating plant with open cycle magnetohydrodynamics is divided into principal accounts based on Federal Energy Regulatory Commision account structure. Each principal account is defined and its estimated cost subdivided into identifiable and major equipment systems. The cost data sources for compiling the estimates, cost parameters, allotments, assumptions, and contingencies, are discussed. Uncertainties associated with developing the costs are quantified to show the confidence level acquired. Guidelines established in preparing the estimated costs are included. Based on an overall milestone schedule related to conventional power plant scheduling experience and starting procurement of MHD components during the preliminary design phase there is a 6 1/2-year construction period. The duration of the project from start to commercial operation is 79 months. The engineering phase of the project is 4 1/2 years; the construction duration following the start of the man power block is 37 months.

  6. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER) supplement. Magnet system special investigations

    Science.gov (United States)

    1981-01-01

    The results of magnet system special investigations listed below are summarized: 4 Tesla Magnet Alternate Design Study; 6 Tesla Magnet Manufacturability Study. The conceptual design for a 4 Tesla superconducting magnet system for use with an alternate (supersonic) ETF power train is described, and estimated schedule and cost are identified. The magnet design is scaled from the ETF 6 T Tesla design. Results of a manufacturability study and a revised schedule and cost estimate for the ETF 6 T magnet are reported. Both investigations are extensions of the conceptual design of a 6 T magnet system performed earlier as a part of the overall MED-ETF conceptual design described in Conceptual Design Engineering Report (CDER) Vol. V, System Design Description (SDD) 503 dated September, 1981, DOE/NASA/0224-1; NASA CR-165/52.

  7. NASA's Suborbital Missions Teach Engineering and Technology: Goddard Space Flight Center's Wallops Flight Facility

    Science.gov (United States)

    Winterton, Joyce L.

    2016-01-01

    A 50 minute-workshop based on NASA publicly available information will be conducted at the International Technology and Engineering Educator Association annual conference. Attendees will include middle and high school teachers and university teacher educators. Engineering and technology are essential to NASA's suborbital missions including sounding rockets, scientific balloon and airborne science. The attendees will learn how to include NASA information on these missions in their teaching.

  8. Force Protection and Command Relationships: Who's Responsible

    National Research Council Canada - National Science Library

    Moller, James

    1998-01-01

    .... This monograph analyzes the joint force protection program by investigating the terms: command, chain of command, command relationship, and how these terms authorize and empower a commander to implement this program across the joint force...

  9. Spaceport Command and Control System Automation Testing

    Science.gov (United States)

    Hwang, Andrew

    2017-01-01

    The Spaceport Command and Control System (SCCS) is the National Aeronautics and Space Administrations (NASA) launch control system for the Orion capsule and Space Launch System, the next generation manned rocket currently in development. This large system requires high quality testing that will properly measure the capabilities of the system. Automating the test procedures would save the project time and money. Therefore, the Electrical Engineering Division at Kennedy Space Center (KSC) has recruited interns for the past two years to work alongside full-time engineers to develop these automated tests, as well as innovate upon the current automation process.

  10. Spaceport Command and Control System Automated Testing

    Science.gov (United States)

    Stein, Meriel

    2017-01-01

    The Spaceport Command and Control System (SCCS) is the National Aeronautics and Space Administrations (NASA) launch control system for the Orion capsule and Space Launch System, the next generation manned rocket currently in development. This large system requires high quality testing that will properly measure the capabilities of the system. Automating the test procedures would save the project time and money. Therefore, the Electrical Engineering Division at Kennedy Space Center (KSC) has recruited interns for the past two years to work alongside full-time engineers to develop these automated tests, as well as innovate upon the current automation process.

  11. Waste Receiving and Processing Facility, Module 1: Volume 6, Engineering assessments

    International Nuclear Information System (INIS)

    1992-03-01

    This report evaluates the ability of the WRAP Module 1 Facility to achieve the required material throughput by developing a time and motion simulation model of the facility using the WITNESS Simulation Program. Analysis of the simulation model indicated that the required throughput of 6825 drums per year based on working 5.5 hours in the Shipping ampersand Receiving and Waste Process areas and 7 hours in the NDA/NDE area for 175 days a year, as stated in the Functional Design Criteria (FDC) Rev. 1 and Supplemental Design Requirements Document (SDRD) Rev. 1, can be achieved

  12. Structural health monitoring and lifecycle-management for civil engineering constructions in power plants and industrial facilities; Zustandsueberwachung und Lebensdauermanagement von baulichen Einrichtungen in Kraftwerken und Industrieanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Lehnen, Dieter; Demmer, Martin; Pfister, Tobias [ZERNA Planen und Pruefen GmbH, Bochum (Germany)

    2013-09-01

    In contrast to other fields of engineering, structural health monitoring and lifecycle management for civil engineering constructions in power plants and industrial facilities have to be developed yet. The necessity of this development immediately arises from the building regulations law with its extensive set of regulations as well as from economic constraints. Approaches and methods of structural health monitoring and lifecycle management for civil engineering constructions in power plants and industrial facilities could be improved intensively during recent years. The paper focuses on practical examples that show the necessity of comprehensive and strategic structural health monitoring in conjunction with lifecycle management for civil engineering constructions in power plants and industrial facilities unambiguously und clear. (orig.)

  13. Performance of engineered barrier materials in near surface disposal facilities for radioactive waste. Results of a co-ordinated research project

    International Nuclear Information System (INIS)

    2001-11-01

    The primary objectives of the CRP were to: promote the sharing of experiences of the Member States in their application of engineered barrier materials for near surface disposal facilities; help enhance their use of engineered barriers by improving techniques and methods for selecting, planning and testing performance of various types of barrier materials for near surface disposal facilities. The objective of this publication is to provide and overview of technical issues related to the engineered barrier systems and a summary of the major findings of each individual research project that was carried out within the framework of the CRP. This publication deals with a general overview of engineered barriers in near surface disposal facilities, key technical information obtained within the CRP and overall conclusions and recommendations for future research and development activities. Appendices presenting individual research accomplishments are also provided. Each of the 13 appendices was indexed separately

  14. ALARA engineering at Department of Energy facilities: Bibliography of selected readings in radiation protection and ALARA

    International Nuclear Information System (INIS)

    Dionne, B.J.; Khan, T.A.; Lane, S.G.; Baum, J.W.

    1991-05-01

    Promoting the exchange of information related to implementation of the As Low As Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report, prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health, is the second in a series of bibliographies on dose reduction at DOE facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose reduction activities, with a specific focus towards DOE facilities. Facility types and activities covered in the scope of this report include: radioactive waste; uranium enrichment; fuel fabrication, storage, and reprocessing; facility decommissioning; hot laboratories; tritium production; research, test and production reactors; weapons fabrication and testing; and accelerators. Material on improved shielding design, decontamination, containments, robotics, job planning, improved operational techniques, and other topics has also been included. This volume (Volume 2 of the series) contains 127 abstracts numbered from 69 through 195, as well as author and subject indices. The subject index contains the abstract numbers from both the previous volume and the current volume, the latter being indicated in boldface. Information that the reader feels should be included in the next volume of this bibliography should be submitted to the BNL ALARA Center

  15. Reports and operational engineering: An independent safety assessment of Department of Energy nuclear reactor facilities

    International Nuclear Information System (INIS)

    Rochman, A.; Washburn, B.W.

    1981-02-01

    The Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee, established via an October 24, 1979 memorandum from the Department of Energy (DOE) Under Secretary, was instructed to review the ''Kemeny Commission'' recommendations and to identify possible implications for DOE's nuclear facilities. As a result of this review, the Committee recommended that DOE carry out assessments in seven categories. The assessments would address specific topics identified for each category as delineated in the NFPQT ''Guidelines for Assessing the Safe Operation of DOE-Owned Reactors,'' dated May 7, 1980. The Committee recognized that similar assessments had been ongoing in the DOE program and safety overview organizations since the Three Mile Island nuclear accident and it was the Committee's intent to use the results of those ongoing assessments as an input to their evaluations. This information would be supplemented by additional studies consisting of the subject-related documents used at each reactor facility studied, and an on-site review of these reactor facilities by professional personnel within the Department of Energy, its operating contractors and independent consultants. 1 tab

  16. A Global Survey and Interactive Map Suite of Deep Underground Facilities; Examples of Geotechnical and Engineering Capabilities, Achievements, Challenges: (Mines, Shafts, Tunnels, Boreholes, Sites and Underground Facilities for Nuclear Waste and Physics R&D)

    Science.gov (United States)

    Tynan, M. C.; Russell, G. P.; Perry, F.; Kelley, R.; Champenois, S. T.

    2017-12-01

    This global survey presents a synthesis of some notable geotechnical and engineering information reflected in four interactive layer maps for selected: 1) deep mines and shafts; 2) existing, considered or planned radioactive waste management deep underground studies, sites, or disposal facilities; 3) deep large diameter boreholes, and 4) physics underground laboratories and facilities from around the world. These data are intended to facilitate user access to basic information and references regarding deep underground "facilities", history, activities, and plans. In general, the interactive maps and database [http://gis.inl.gov/globalsites/] provide each facility's approximate site location, geology, and engineered features (e.g.: access, geometry, depth, diameter, year of operations, groundwater, lithology, host unit name and age, basin; operator, management organization, geographic data, nearby cultural features, other). Although the survey is not all encompassing, it is a comprehensive review of many of the significant existing and historical underground facilities discussed in the literature addressing radioactive waste management and deep mined geologic disposal safety systems. The global survey is intended to support and to inform: 1) interested parties and decision makers; 2) radioactive waste disposal and siting option evaluations, and 3) safety case development as a communication tool applicable to any mined geologic disposal facility as a demonstration of historical and current engineering and geotechnical capabilities available for use in deep underground facility siting, planning, construction, operations and monitoring.

  17. ARAC: A unique command and control resource

    International Nuclear Information System (INIS)

    Bradley, M.M.; Baskett, R.L.; Ellis, J.S.

    1996-04-01

    The Atmospheric Release Advisory Capability (ARAC) at Lawrence Livermore National Laboratory (LLNL) is a centralized federal facility designed to provide real-time, world-wide support to military and civilian command and control centers by predicting the impacts of inadvertent or intentional releases of nuclear, biological, or chemical materials into the atmosphere. ARAC is a complete response system consisting of highly trained and experienced personnel, continually updated computer models, redundant data collection systems, and centralized and remote computer systems. With over 20 years of experience responding to domestic and international incidents, strong linkages with the Department of Defense, and the ability to conduct classified operations, ARAC is a unique command and control resource

  18. ARAC: A unique command and control resource

    Energy Technology Data Exchange (ETDEWEB)

    Bradley, M.M.; Baskett, R.L.; Ellis, J.S. [and others

    1996-04-01

    The Atmospheric Release Advisory Capability (ARAC) at Lawrence Livermore National Laboratory (LLNL) is a centralized federal facility designed to provide real-time, world-wide support to military and civilian command and control centers by predicting the impacts of inadvertent or intentional releases of nuclear, biological, or chemical materials into the atmosphere. ARAC is a complete response system consisting of highly trained and experienced personnel, continually updated computer models, redundant data collection systems, and centralized and remote computer systems. With over 20 years of experience responding to domestic and international incidents, strong linkages with the Department of Defense, and the ability to conduct classified operations, ARAC is a unique command and control resource.

  19. Engineering activities for the preparation of systems and facilities in the dismantling of Jose Cabrera NPP

    International Nuclear Information System (INIS)

    Gomez Rodriguez, C. A.; Martin Palomo, N.

    2012-01-01

    This paper presents the previous work of analysis of management systems and facilities, modifications to systems plans and the final implementation carried out on the site. The final result of the development of these plans, obtained after two years of intense work and in particular the result of the evolution of the turbine (now EAD) building, converted into the central infrastructure for the dismantling of the rest of the installation plans will be presented.

  20. Engineering study for a melting, casting, rolling and fabrication facility for recycled contaminated stainless steel

    International Nuclear Information System (INIS)

    1994-01-01

    This Preliminary Report is prepared to study the facilities required for recycling contaminated stainless steel scrap into plate which will be fabricated into boxes suitable for the storage of contaminated wastes and rubble. The study is based upon the underlying premise that the most cost effective way to produce stainless steel is to use the same processes employed by companies now in production of high quality stainless steel. Therefore, the method selected for this study for the production of stainless steel plate from scrap is conventional process using an Electric Arc Furnace for meltdown to hot metal, a Continuous Caster for production of cast slabs, and a Reversing Hot Mill for rolling the slabs into plate. The fabrication of boxes from the plate utilizes standard Shears, Punch Presses and welding equipment with Robotic Manipulators. This Study presumes that all process fumes, building dusts and vapors will be cycled through a baghouse and a nuclear grade HEPA filter facility prior to discharge. Also, all process waste water will be evaporated into the hot flue gas stream from the furnace utilizing a quench tank; so there will be no liquid discharges from the facility and all vapors will be processed through a HEPA filter. Even though HEPA filters are used today in controlling radioactive contamination from nuclear facilities there is a sparsity of data concerning radioactivity levels and composition of waste that may be collected from contaminated scrap steel processing. This report suggests some solutions to these problems but it is recommended that additional study must be given to these environmental problems

  1. Automated constraint checking of spacecraft command sequences

    Science.gov (United States)

    Horvath, Joan C.; Alkalaj, Leon J.; Schneider, Karl M.; Spitale, Joseph M.; Le, Dang

    1995-01-01

    Robotic spacecraft are controlled by onboard sets of commands called "sequences." Determining that sequences will have the desired effect on the spacecraft can be expensive in terms of both labor and computer coding time, with different particular costs for different types of spacecraft. Specification languages and appropriate user interface to the languages can be used to make the most effective use of engineering validation time. This paper describes one specification and verification environment ("SAVE") designed for validating that command sequences have not violated any flight rules. This SAVE system was subsequently adapted for flight use on the TOPEX/Poseidon spacecraft. The relationship of this work to rule-based artificial intelligence and to other specification techniques is discussed, as well as the issues that arise in the transfer of technology from a research prototype to a full flight system.

  2. A preliminary study for an engineering assessment of a shallow land burial facility in clay

    International Nuclear Information System (INIS)

    Fitzpatrick, J.; Murray, N.

    1987-02-01

    This study characterises a notional low-level waste repository site within the Oxford clay belt, provides a conceptual design for a shallow, engineered repository at the site, and presents a rationale of the multiple-barrier design basis in sufficient detail to enable BRE to rehearse an engineering assessment. Parameters are identified which describe the repository's structural integrity, permeability and effectiveness in physical and chemical containment of nuclides by resistance to diffusive and advective transport. Such parameters may be used by the DoE as input for the mathematical modelling of the repository's post-closure performance under various release scenarios, as part of a full radiological assessment. Limitations in the analytical methods and experience base available for such assessments are identified and suggestions are made for future research activities. (author)

  3. Development of an engineering design process and associated systems and procedures for a UK geological disposal facility - 59160

    International Nuclear Information System (INIS)

    Rendell, Philip; Breen, Brendan; Clark, Alastair; Reece, Steve; O'Grady, Henry

    2012-01-01

    In the United Kingdom the Nuclear Decommissioning Authority (NDA) has been charged with implementing Government policy for the long-term management of higher activity radioactive waste. The UK Government is leading a site selection process based on voluntarism and partnership with local communities interested in hosting such a facility and as set out in the 'Managing Radioactive Waste Safely' White Paper (2008). The NDA has set up the Radioactive Waste Management Directorate (RWMD) as the body responsible for planning, building and operating a geological disposal facility (GDF). RWMD will develop into a separately regulated Site Licence Company (SLC) responsible for the construction, operation and closure of the facility. RWMD will be the Design Authority for the GDF; requiring a formal process to ensure that the knowledge and integrity of the design is maintained. In 2010 RWMD published 'Geological Disposal - Steps towards implementation' which described the preparatory work that it is undertaking in planning the future work programme, and the phases of work needed to deliver the programme. RWMD has now developed a process for the design of the GDF to support this work. The engineering design process follows a staged approach, encompassing options development, requirements definition, and conceptual and detailed designs. Each stage finishes with a 'stage gate' comprising a technical review and a specific set of engineering deliverables. The process is intended to facilitate the development of the most appropriate design of GDF, and to support the higher level needs of both the project and the community engagement programmes. The process incorporates elements of good practices derived from other work programmes; including process mapping, issues and requirements management, and progressive design assurance. A set of design principles have been established, and supporting design guidance notes are being produced. In addition a requirements management system is being

  4. Engineering for a disposal facility using the in-room emplacement method

    Energy Technology Data Exchange (ETDEWEB)

    Baumgartner, P; Bilinsky, D M; Ates, Y; Read, R S; Crosthwaite, J L; Dixon, D A

    1996-06-01

    This report describes three nuclear fuel waste disposal vaults using the in-room emplacement method. First, a generic disposal vault design is provided which is suitable for a depth range of 500 m to 1000 m in highly stressed, sparsely fractured rock. The design process is described for all components of the system. The generic design is then applied to two different disposal vaults, one at a depth of 750 m in a low hydraulically conductive, sparsely fractured rock mass and another at a depth of 500 m in a higher conductivity, moderately fractured rock mass. In the in-room emplacement method, the disposal containers with used-fuel bundles are emplaced within the confines of the excavated rooms of a disposal vault. The discussion of the disposal-facility design process begins with a detailed description of a copper-shell, packed-particulate disposal container and the factors that influenced its design. The disposal-room generic design is presented including the detailed specifications, the scoping and numerical thermal and thermal mechanical analyses, the backfilling and sealing materials, and the operational processes. One room design is provided that meets all the requirements for a vault depth range of 500 to 1000 m. A disposal-vault layout and the factors that influenced its design are also presented, including materials handling, general logistics, and separation of radiological and nonradiological operations. Modifications to the used-fuel packaging plant for the filling and sealing of the copper-shell, packed-particulate disposal containers and a brief description of the common surface facilities needed by the disposal vault and the packaging plant are provided. The implementation of the disposal facility is outlined, describing the project stages and activities and itemizing a specific plan for each of the project stages: siting, construction, operation; decommissioning; and closure. (author). 72 refs., 15 tabs., 63 figs.

  5. Engineering for a disposal facility using the in-room emplacement method

    International Nuclear Information System (INIS)

    Baumgartner, P.; Bilinsky, D.M.; Ates, Y.; Read, R.S.; Crosthwaite, J.L.; Dixon, D.A.

    1996-06-01

    This report describes three nuclear fuel waste disposal vaults using the in-room emplacement method. First, a generic disposal vault design is provided which is suitable for a depth range of 500 m to 1000 m in highly stressed, sparsely fractured rock. The design process is described for all components of the system. The generic design is then applied to two different disposal vaults, one at a depth of 750 m in a low hydraulically conductive, sparsely fractured rock mass and another at a depth of 500 m in a higher conductivity, moderately fractured rock mass. In the in-room emplacement method, the disposal containers with used-fuel bundles are emplaced within the confines of the excavated rooms of a disposal vault. The discussion of the disposal-facility design process begins with a detailed description of a copper-shell, packed-particulate disposal container and the factors that influenced its design. The disposal-room generic design is presented including the detailed specifications, the scoping and numerical thermal and thermal mechanical analyses, the backfilling and sealing materials, and the operational processes. One room design is provided that meets all the requirements for a vault depth range of 500 to 1000 m. A disposal-vault layout and the factors that influenced its design are also presented, including materials handling, general logistics, and separation of radiological and nonradiological operations. Modifications to the used-fuel packaging plant for the filling and sealing of the copper-shell, packed-particulate disposal containers and a brief description of the common surface facilities needed by the disposal vault and the packaging plant are provided. The implementation of the disposal facility is outlined, describing the project stages and activities and itemizing a specific plan for each of the project stages: siting, construction, operation; decommissioning; and closure. (author)

  6. Hydrodynamic instability experiments on the HIPER laser facility at the Institute of Laser Engineering, Osaka University

    International Nuclear Information System (INIS)

    Shigemori, K.; Azechi, H.; Fujioka, S.

    2003-01-01

    We present recent results on the hydrodynamic instability experiments on the HIPER (High Intensity Plasma Experimental Research) laser facility at ILE, Osaka University. We measured the Rayleigh-Taylor growth rate on the HIPER laser. Also measured were all parameters that determine the RT growth rate. We focused on the measurements of the ablation density of laser-irradiated targets, which had not been experimentally measured. The experimental results were compared with calculations with one dimensional simulation coupled with Fokker-Planck equation for electron transport. (author)

  7. Engineering study of generic site criteria for selected DOE plutonium facilities

    International Nuclear Information System (INIS)

    Kingsbury, R.J.; Greenwood, J.M.; Sandoval, M.D.

    1980-09-01

    The objectives of this study were to identify criteria that would be applied to selection of a site for plutonium facilities such as those at the Rocky Flats Plant, to establish the relative importance of these criteria, and to identify suitable areas within the United States for location of plutonium facilities with respect to these criteria. Sources of the site criteria identified include federal laws, federal agency regulations, state laws and regulations, and requirements associated with operations to be performed at the site. The criteria identified during the study were organized into 14 major categories. The relative importnace of each category and each criterion within the categories were established using group decision-making techniques. The major criteria categories, their assigned weight on a scale of 1 to 10, and their relative priority ranks are as follows: geology/seismicity; public safety; environmental impact; meteorology; hydrology; topography; transportation; utilities; personnel; safeguards/security; land area and availability; land use compatibility; and, public acceptance. A suitability analysis of the continental United States was performed using only those criteria that could be mapped at a national scale. Suitability was assessed with respect to each of these criteria, and individual suitability maps were prepared. A composite suitability map was generated using computerized overlay techniques. This map provides a starting point for identifying specific candidate sites if an actual site selection were to be conducted

  8. [Engineering aspects of seismic behavior of health-care facilities: lessons from California earthquakes].

    Science.gov (United States)

    Rutenberg, A

    1995-03-15

    The construction of health-care facilities is similar to that of other buildings. Yet the need to function immediately after an earthquake, the helplessness of the many patients and the high and continuous occupancy of these buildings, require that special attention be paid to their seismic performance. Here the lessons from the California experience are invaluable. In this paper the behavior of California hospitals during destructive earthquakes is briefly described. Adequate structural design and execution, and securing of nonstructural elements are required to ensure both safety of occupants, and practically uninterrupted functioning of equipment, mechanical and electrical services and other vital systems. Criteria for post-earthquake functioning are listed. In view of the hazards to Israeli hospitals, in particular those located along the Jordan Valley and the Arava, a program for the seismic evaluation of medical facilities should be initiated. This evaluation should consider the hazards from nonstructural elements, the safety of equipment and systems, and their ability to function after a severe earthquake. It should not merely concentrate on safety-related structural behavior.

  9. Seismic procurement requirements at the FPR (Fuel Processing Restoration) facility at INEL (Idaho National Engineering Laboratory)

    International Nuclear Information System (INIS)

    Bingham, G.E.; Hardy, G.S.; Griffin, M.J.

    1989-01-01

    Traditional methods used to seismically qualify equipment for new facilities has been either by testing or analysis. Testing programs are generally expensive and their input loadings are conservative. It is also generally recognized that standard seismic analysis techniques produce overly conservative results. Seismic loads and response levels for equipment are typically calculated that far exceed the values actually experienced in earthquakes. A more efficient method for demonstrating the seismic adequacy of equipment has been developed which is based on conclusions derived from studying the performance of equipment that has been subjected to actual earthquake excitations. The earthquake experience data concludes that damage or malfunction to most types of equipment subjected to earthquakes is far less than that predicted by traditional testing and analysis techniques. The use of conclusions derived from experience data provides a more realistic approach in assessing the seismic ruggedness of equipment. By recognizing this inherently higher capacity that exists in specific classes of equipment, vendors can often supply off the shelf equipment without the need to perform expensive modifications to meet requirements imposed by conservative qualification analyses. This paper will describe the development of the experienced based method for equipment seismic qualification and its application at the FPR facility

  10. Waste Characterization Facility at the Idaho National Engineering Laboratory. Environmental Assessment

    International Nuclear Information System (INIS)

    1995-02-01

    DOE has prepared an Environmental Assessment (EA) on the proposed construction and operation of a Waste Characterization Facility (WCF) at INEL. This facility is needed to examine and characterize containers of transuranic (TRU) waste to certify compliance with transport and disposal criteria; to obtain information on waste constituents to support proper packaging, labeling, and storage; and to support development of treatment and disposal plans for waste that cannot be certified. The proposed WCF would be constructed at the Radioactive Waste Management Complex (RWMC). In accordance with the Council on Environmental Quality (CEQ) requirements in 40 CFR Parts 1500-1508, the EA examined the potential environmental impacts of the proposed WCF and discussed potential alternatives. Based on the analyses in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, and CEQ regulations at 40 CFR 1508.18 and 1508.27. Therefore, an Environmental Impact Statement is not required, and DOE is issuing this Finding of No Significant Impact

  11. Evaluation of engineered barrier materials for surface disposal facilities. Appendix 2: Brazil

    International Nuclear Information System (INIS)

    Endo, L.S.

    2001-01-01

    Full text: In practice, those nuclear installations that generate most wastes in Brazil often have interim storage facilities at the same site. They can also accommodate wastes from small users that have no suitable place to manage their wastes. The forecast at the time of the CRP for Brazilian waste generation due to all nuclear and radioactive activities by the year 2010 is to be about 5000 m 3 , not including the waste of 3500 m 3 from Goiania accident. With the impact of the accident on the public opinion, the quest for a safe disposal facility became more urgent, especially the siting and licensing a disposal facility which could receive the Goiania waste. Although the construction of a national repository was a matter of future decision at the time of the CRP, research programmes were being developed and carried out by the research institutes of the Brazilian National Commission of Nuclear Energy. The R and D programmes were primarily intended to establish required technical capability in dealing with the subject especially in terms of issues related to the evaluation of disposal facility performance and lifetime. Some activities of the programmes were within the scope of the CRP, namely: study of diffusion through cementitious materials; degradation of concrete due to chemical corrosion and microbiological attack; evaluation of additives for the improvement of structural concrete and cemented wasteform quality. In the work relating to the improvement of wasteforms and concrete, silica-fume was being evaluated as an admixture in the cementation process. Ion-exchange resins, a typical power reactor waste, and simulated liquid waste from fission production were used as reference wastes. The performance of the produced wasteforms was evaluated by measuring four properties of interest: setting time; heat developed during hydration process, compressive strength, and leachability. Results showed that the addition of silica-fume increased the compressive strength

  12. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's facilities in fiscal 1993

    International Nuclear Information System (INIS)

    1994-01-01

    This publication summarizes the results of the joint utilization of the research 'Yayoi' and the electron beam accelerator in the Nuclear Engineering Research Laboratory, University of Tokyo, in the fiscal year 1993. In this report, the gists of 15 researches which were carried out on pile of the Yayoi, 9 researches off pile of the Yayoi and 14 researches by using the linear accelerator are collected. In addition, the 13 reports of Yayoi Study Meeting held in fiscal year 1993 are collected. Moreover, the list of the events carried out in the facility in fiscal year 1993, the registers of names of various committees, and the register of the names of persons who were in charge of joint utilization experiments in fiscal year 1993 are attached. (K.I.)

  13. Evaluation of Butanol–Gasoline Blends in a Port Fuel-injection, Spark-Ignition Engine Évaluation de mélange butanol-essence dans un moteur à allumage commandé à injection indirecte

    Directory of Open Access Journals (Sweden)

    Dernotte J.

    2009-11-01

    Full Text Available This paper assesses different butanol–gasoline blends used in a port fuel-injection, spark-ignition engine to quantify the influence of butanol addition on the emission of unburned hydrocarbons, carbon monoxide, and nitrogen oxide. Furthermore, in-cylinder pressure was measured to quantify combustion stability and to compare the ignition delay and fully developed turbulent combustion phases as given by 0%–10% and 10%–90% Mass Fraction Burned (MFB. The main findings are: 1 a 40% butanol/60% gasoline blend by volume (B40 minimizes HC emissions; 2 no significant change in NOx emissions were observed, with the exception of the 80% butanol/20% gasoline blend; 3 the addition of butanol improves combustion stability as measured by the COV of IMEP; 4 butanol added to gasoline reduces ignition delay (0%–10% MFB; and 5 the specific fuel consumption of B40 blend is within 10% of that of pure gasoline for stoichiometric mixture. Cet article évalue le potentiel de l’utilisation de différents mélanges butanolessence dans un moteur à allumage commandé à injection indirecte afin de quantifier l’influence de l’ajout de butanol sur les émissions des hydrocarbures imbrûlés (HC, le monoxyde de carbone (CO et les oxydes d’azote (NOx. De plus, l’influence sur la stabilité de combustion, le délai d’inflammation et sur la durée de la phase de combustion turbulente développée y sont également présentés. Les principaux résultats: 1 un mélange de 40% butanol et 60% essence (B40 par volume diminue les émissions de HC; 2 aucun effet significatif sur les émissions de NOx n’a été observé à l’exception du mélange 80% butanol/20% essence; 3 l’ajout de butanol améliore la stabilité de combustion ; 4 l’ajout de butanol réduit le délai d’inflammation, quantifié par la durée pour consommer 10% de masse de gaz frais; et 5 la consommation spécifique de carburant pour un mélange stoechiométrique de B40 est 10% sup

  14. Incident Command System - Environmental Unit responsibilities

    International Nuclear Information System (INIS)

    Hillman, S. O.

    1997-01-01

    The Incident Command System (ICS) for crisis management, used for response to oil spills by the Alyeska Pipeline Service Company throughout its facilities, including the Trans Alaska Pipeline and the Valdez Marine Terminal, was described. Special attention was given to the Environmental Unit within the ICS which functions as a primary support unit for the Incident Operations Section. Details of the Unit's function were provided. These include the collection, evaluation and dissemination of information on all environmental issues concerning the crisis, provision of advice and direction on environmental aspects, and up-front agency interaction. A checklist of tasks is included. 7 refs

  15. Glovebox glove deterioration in the Hanford Engineering Development Laboratory fuel fabrication facility

    International Nuclear Information System (INIS)

    Greenhalgh, W.O.; Smith, R.C.; Powell, D.L.

    1979-07-01

    Neoprene glovebox gloves have been found susceptible to periodic rapid deterioration under normal operating conditions in fuel fabrication facilities. Examinations of glove failure histories and measurements of the atmospheres in inert atmosphere dry-boxes indicated ozone at low concentrations of 100 to 500 ppB was probably the most important factor in rapid glove deterioration. Testing of a varity of new glove materials indicated that Hypalon and ethylene-propylene-diamine monomer (EDPM) gloves have greater than 30 times the longevity of neoprene in low-level ozone concentration atmospheres. comparative tests over a 30-month period have also confirmed that the two glove candidates have a significantly longer operative life. 14 figures

  16. Intended long term performances of cementitious engineered barriers for future storage and disposal facilities for radioactive wastes in Romania

    Directory of Open Access Journals (Sweden)

    Sociu F.

    2013-07-01

    Full Text Available Considering the EU statements, Romania is engaged to endorse in the near future the IAEA relevant publications on geological repository (CNCANa, to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Currently, for example, spent fuel is wet stored for 6 years and after this period it is transported to dry storage in MACSTOR-200 (a concrete monolithic module where it is intended to remain at least 50 years. The present situation for radioactive waste management in Romania is reviewed in the present paper. Focus will be done on existent disposal facilities but, also, on future facilities planned for storage / disposal of radioactive wastes. Considering specific data for Romanian radioactive waste inventory, authors are reviewing the advance in the radioactive waste management in Romania considering its particularities. The team tries to highlight the expected limitations and unknown data related with cementitious engineered barriers that has to be faced in the near future incase of interim storage or for the upcoming long periods of disposal.

  17. Facile synthesis of biphasic calcium phosphate microspheres with engineered surface topography for controlled delivery of drugs and proteins.

    Science.gov (United States)

    Zarkesh, Ibrahim; Ghanian, Mohammad Hossein; Azami, Mahmoud; Bagheri, Fatemeh; Baharvand, Hossein; Mohammadi, Javad; Eslaminejad, Mohamadreza Baghaban

    2017-09-01

    Biphasic calcium phosphate (BCP) microspheres are of great interest due to their high stability and osteoinductive properties at specific compositions. However, the need for optimal performance at a unique composition limits their flexibility for tuning drug release by modulation of bulk properties and presents the question of engineering surface topography as an alternative. It is necessary to have a facile method to control surface topography at a defined bulk composition. Here, we have produced BCP microspheres with different surface topographies that have the capability to be used as tunable drug release systems. We synthesized calcium deficient hydroxyapatite (CDHA) microparticles by precipitating calcium and phosphate ions onto ethylenediaminetetraacetic acid (EDTA) templates. The morphology and surface topography of CDHA microparticles were controlled using process parameters, which governed nucleation and growth. These parameters included template concentration, heat rate, and stirring speed. Under low heat rate and static conditions, we could obtain spherical microparticles with long and short nanosheets on their surfaces at low and high EDTA concentrations, respectively. These nanostructured microspheres were subsequently crystallized by thermal treatment to produce EDTA-free BCP microspheres with intact morphology. These biocompatible BCP microspheres were highly effective in loading and prolonged release of both small molecule [dexamethasone (Dex)] and protein [bovine serum albumin (BSA)] models. This strategy has enabled us to control the surface topography of BCP microspheres at defined compositions and holds tremendous promise for drug delivery and tissue engineering applications. Copyright © 2017 Elsevier B.V. All rights reserved.

  18. Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

  19. Engineering and construction projects for oil and gas processing facilities: Contracting, uncertainty and the economics of information

    International Nuclear Information System (INIS)

    Berends, Kees

    2007-01-01

    The amount of oil and gas processing capacity required to meet demand during the next 20 years is more than twice the amount realised during the last decades. Engineering and Construction contractors (ECs) play a key role in the development and implementation of Large Engineering and Construction Projects (LECPs) for these facilities. We examine the characteristics of LECPs, demand and supply of the contracting market and the strategies traditionally adopted by owners to contract out the development and implementation of these projects to ECs. We demonstrate that these traditional strategies are not longer effective, in the current 'sellers market', to mitigate the oligopolistic economic inefficiencies. As the 'overheating' of the contracting market is expected to continue for a considerable period of time, alternative contracting strategies are required. Contract theory, particularly the economics of information on LECPs, indicates how alternative contracting strategies can be used to overcome economic inefficiencies. The effective use of these alternative strategies requires increased owner involvement and their effectiveness is contingent upon owner competency and ECs acting as the owner's agent rather than its adversary. This will require an organisational and behavioural change process for both owners and ECs

  20. A facile synthesis method of hydroxyethyl cellulose-silver nanoparticle scaffolds for skin tissue engineering applications.

    Science.gov (United States)

    Zulkifli, Farah Hanani; Hussain, Fathima Shahitha Jahir; Zeyohannes, Senait Sileshi; Rasad, Mohammad Syaiful Bahari Abdull; Yusuff, Mashitah M

    2017-10-01

    Green porous and ecofriendly scaffolds have been considered as one of the potent candidates for tissue engineering substitutes. The objective of this study is to investigate the biocompatibility of hydroxyethyl cellulose (HEC)/silver nanoparticles (AgNPs), prepared by the green synthesis method as a potential host material for skin tissue applications. The substrates which contained varied concentrations of AgNO 3 (0.4%-1.6%) were formed in the presence of HEC, were dissolved in a single step in water. The presence of AgNPs was confirmed visually by the change of color from colorless to dark brown, and was fabricated via freeze-drying technique. The outcomes exhibited significant porosity of >80%, moderate degradation rate, and tremendous value of water absorption up to 1163% in all samples. These scaffolds of HEC/AgNPs were further characterized by SEM, UV-Vis, ATR-FTIR, TGA, and DSC. All scaffolds possessed open interconnected pore size in the range of 50-150μm. The characteristic peaks of Ag in the UV-Vis spectra (417-421nm) revealed the formation of AgNPs in the blend composite. ATR-FTIR curve showed new existing peak, which implies the oxidation of HEC in the cellulose derivatives. The DSC thermogram showed augmentation in T g with increased AgNO 3 concentration. Preliminary studies of cytotoxicity were carried out in vitro by implementation of the hFB cells on the scaffolds. The results substantiated low toxicity of HEC/AgNPs scaffolds, thus exhibiting an ideal characteristic in skin tissue engineering applications. Copyright © 2017 Elsevier B.V. All rights reserved.

  1. Command History. 1964. Sanitized

    Science.gov (United States)

    1964-01-01

    O tion was ompleted at Bien Nba in August but was still underway t Soc %trng. Howeer, for the majority of the personnel in MACV recre- ational...facilities were restricted to tennis, volleyball, basketball , 𔃺,; and other foraLUY organized sports requiring limited resources. (9) Supplenenting the FM

  2. Mobility of Tritium in Engineered and Earth Materials at the NuMI Facility, Fermilab: Progress report for work performed between June 13 and September 30, 2006

    International Nuclear Information System (INIS)

    Pruess, Karsten; Conrad, Mark; Finsterle, Stefan; Kennedy, Mack; Kneafsey, Timothy; Salve, Rohit; Su, Grace; Zhou, Quanlin

    2006-01-01

    This report details the work done between June 13 and September 30, 2006 by Lawrence Berkeley National Laboratory (LBNL) scientists to assist Fermi National Accelerator Laboratory (Fermilab) staff in understanding tritium transport at the Neutrino at the Main Injector (NuMI) facility. As a byproduct of beamline operation, the facility produces (among other components) tritium in engineered materials and the surrounding rock formation. Once the tritium is generated, it may be contained at the source location, migrate to other regions within the facility, or be released to the environment

  3. Software takes command

    CERN Document Server

    Manovich, Lev

    2013-01-01

    Software has replaced a diverse array of physical, mechanical, and electronic technologies used before 21st century to create, store, distribute and interact with cultural artifacts. It has become our interface to the world, to others, to our memory and our imagination - a universal language through which the world speaks, and a universal engine on which the world runs. What electricity and combustion engine were to the early 20th century, software is to the early 21st century. Offering the the first theoretical and historical account of software for media authoring and its effects on the prac

  4. Facilities Engineering Management System Study: Catalog of Automatic Data Processing Applications Developed by USACERL (U.S. Army Construction Engineering Research Laboratory) for Army Installation Directories of Engineering and Housing

    Science.gov (United States)

    1989-08-01

    Programming Languages Used: AUTOCAD Command, AUTOLISP Type of Commercial Program Used: CAD Specific Commercial Program Used: AUTOCAD Version: 1.0... AUTOCAD .................................... 94 Teaching Assistant for Microstation ................................... 95 Training Area Maintenance...System Support Remote Terminals?: Programming Languages Used: AUTOCAD Command Type of Commercial Program Used: CAD Specific Commercial Program Used

  5. Microstructured surfaces engineered using biological templates: a facile approach for the fabrication of superhydrophobic surfaces

    Directory of Open Access Journals (Sweden)

    DUSAN LOSIC

    2008-10-01

    Full Text Available The fabrication of microstructured surfaces using biological templates was investigated with the aim of exploring of a facile and low cost approach for the fabrication of structured surfaces with superhydrophobic properties. Two soft lithographic techniques, i.e., replica moulding and nano-imprinting, were used to replicate the surfaces of a biological substrate. Leaves of the Agave plant (Agave attenuate, a cost-free biological template, were used as a model of a biosurface with superhydrophobic properties. The replication process was performed using two polymers: an elastomeric polymer, poly(dimethylsiloxane (PDMS, and a polyurethane (PU based, UV-curable polymer (NOA 60. In the first replication step, negative polymer replicas of the surface of leaves were fabricated, which were used as masters to fabricate positive polymer replicas by moulding and soft imprinting. The pattern with micro and nanostructures of the surface of the leaf possesses superhydrophobic properties, which was successfully replicated into both polymers. Finally, the positive replicas were coated with a thin gold film and modified with self-assembled monolayers (SAMs to verify the importance of the surface chemistry on the hydrophobic properties of the fabricated structures. Wetting (contact angle and structural (light microscopy and scanning electron microscopy characterisation was performed to confirm the hydrophobic properties of the fabricated surfaces (> 150°, as well as the precision and reproducibility of the replication process.

  6. Performance of engineered barriers materials in near surface disposal facilities in Spain. Appendix 11: Spain

    International Nuclear Information System (INIS)

    Zuloaga, P.

    2001-01-01

    In October 1992 the Ministry of Industry and Energy issued the Operating License of El Cabril Near Surface Disposal Facility, in the province of Cordoba, some 100 km away from Cordoba city. Waste packages, mainly 0.22 m 3 steel drums, containing solidified waste in a cement based waste form or pellets coming from the super-compaction process, are placed inside concrete disposal containers. These containers are made of reinforced concrete and in their construction fabrication joints have been avoided. Once these containers are filled with 18 drums (0.22 m 3 ) or 30 to 60 compaction pellets, they are backfilled and sealed with a mortar grout, resulting into a solid block. These blocks are then disposed of inside concrete vaults, called disposal cells, each one with a capacity for 320 containers. The full vaults are backfilled with gravel in the existing central gap left to absorb fabrication and handling tolerances. Then a plastic film is placed on the containers to prevent a true union between the last layer of disposal containers and the massed concrete layer cast to protect the workers during the construction of the closing slab. This 0.5 m thick closing slab is made of reinforced concrete and is protected by acrylic/fibreglass unperceived film. Galleries are made of a 300 kg/cm 2 characteristic strength concrete

  7. Engineering/design of a co-generation waste-to-energy facility

    International Nuclear Information System (INIS)

    Bajaj, K.S.; Virgilio, R.J.

    1992-01-01

    Five hundred fifteen thousand tons of Municipal Solid Waste (MSW) is being generated every day in America. At present 68% of this trash is dumped into landfill operations. As the amount of garbage is increasing daily, the amount of land reserved for landfills is diminishing rapidly. With the sentiment of the public that you produce it, you keep it, the import-export of waste between the counties and states for the landfills, no longer appears to be feasible, especially when combined with expensive disposal costs. One method of reducing the quantity of waste sent to landfills is through the use of waste-to-energy facilities - the technology of resource recovery - the technology of today INCINERATION. All cogeneration projects are not alike. This paper examines several aspects of the electrical system of a particular municipal solid waste-to-energy project at Charleston, S.C. which includes plant auxiliary loads as well as a utility interconnection through a step-up transformer

  8. ICPP calcined solids storage facility closure study. Volume III: Engineering design files

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

    The following information was calculated to support cost estimates and radiation exposure calculations for closure activities at the Calcined Solids Storage Facility (CSSF). Within the estimate, volumes were calculated to determine the required amount of grout to be used during closure activities. The remaining calcine on the bin walls, supports, piping, and floor was also calculated to approximate the remaining residual calcine volumes at different stages of the removal process. The estimates for remaining calcine and vault void volume are higher than what would actually be experienced in the field, but are necessary for bounding purposes. The residual calcine in the bins may be higher than was is experienced in the field as it was assumed that the entire bin volume is full of calcine before removal activities commence. The vault void volumes are higher as the vault roof beam volumes were neglected. The estimations that follow should be considered rough order of magnitude, due to the time constraints as dictated by the project`s scope of work. Should more accurate numbers be required, a new analysis would be necessary.

  9. ICPP calcined solids storage facility closure study. Volume III: Engineering design files

    International Nuclear Information System (INIS)

    1998-02-01

    The following information was calculated to support cost estimates and radiation exposure calculations for closure activities at the Calcined Solids Storage Facility (CSSF). Within the estimate, volumes were calculated to determine the required amount of grout to be used during closure activities. The remaining calcine on the bin walls, supports, piping, and floor was also calculated to approximate the remaining residual calcine volumes at different stages of the removal process. The estimates for remaining calcine and vault void volume are higher than what would actually be experienced in the field, but are necessary for bounding purposes. The residual calcine in the bins may be higher than was is experienced in the field as it was assumed that the entire bin volume is full of calcine before removal activities commence. The vault void volumes are higher as the vault roof beam volumes were neglected. The estimations that follow should be considered rough order of magnitude, due to the time constraints as dictated by the project's scope of work. Should more accurate numbers be required, a new analysis would be necessary

  10. Conceptual study of nuclear power generation facilities life-cycle support versatile engineering database. Procedure of development and consideration of fundamental functions

    International Nuclear Information System (INIS)

    Endo, Hidetoshi

    2009-05-01

    International Atomic Energy Agency (IAEA) stands out the activity of the knowledge management of nuclear safety and the movement to introduce the idea of the life cycle management into the quality control of maintenance of the nuclear power generation facilities to assure the knowledge preservation and to succeed the technology of facilities. Japan Atomic Energy Agency (JAEA) also has such activities as the knowledge preservation of research and development, and related information. The facilities' performance reliability can be easily checked with the technology of data processing in the general industry and the results of the knowledge repository, transmitting technology and knowledge management by referring to the information and knowledge if the information and knowledge at each step of the life-cycle of facilities can be built. This report shows the strategy of the construction of the engineering database to support the life cycle of facilities and the basic function of the management system. (author)

  11. Paramount Interest: Command Relationships in Amphibious Warfare

    National Research Council Canada - National Science Library

    Peabody, Hitch

    2004-01-01

    In 2001, U.S. amphibious forces abandoned sixty years of established command and control doctrine, replacing the traditional senior-subordinate relationship between Navy and Marine commanders with coequal command. Why did it change...

  12. Mercury removal at Idaho National Engineering and Environmental Laboratory's New Waste Calcining Facility

    Energy Technology Data Exchange (ETDEWEB)

    S. C. Ashworth

    2000-02-27

    Technologies were investigated to determine viable processes for removing mercury from the calciner (NWCF) offgas system at the Idaho National Engineering and Environmental Laboratory. Technologies for gas phase and aqueous phase treatment were evaluated. The technologies determined are intended to meet EPA Maximum Achievable Control Technology (MACT) requirements under the Clean Air Act and Resource Conservation and Recovery Act (RCRA). Currently, mercury accumulation in the calciner off-gas scrubbing system is transferred to the tank farm. These transfers lead to accumulation in the liquid heels of the tanks. The principal objective for aqueous phase mercury removal is heel mercury reduction. The system presents a challenge to traditional methods because of the presence of nitrogen oxides in the gas phase and high nitric acid in the aqueous scrubbing solution. Many old and new technologies were evaluated including sorbents and absorption in the gas phase and ion exchange, membranes/sorption, galvanic methods, and UV reduction in the aqueous phase. Process modifications and feed pre-treatment were also evaluated. Various properties of mercury and its compounds were summarized and speciation was predicted based on thermodynamics. Three systems (process modification, NOxidizer combustor, and electrochemical aqueous phase treatment) and additional technology testing were recommended.

  13. Mercury Removal at Idaho National Engineering and Environmental Laboratory's New Waste Calcining Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ashworth, Samuel Clay; Wood, R. A.; Taylor, D. D.; Sieme, D. D.

    2000-03-01

    Technologies were investigated to determine viable processes for removing mercury from the calciner (NWCF) offgas system at the Idaho National Engineering and Environmental Laboratory. Technologies for gas phase and aqueous phase treatment were evaluated. The technologies determined are intended to meet EPA Maximum Achievable Control Technology (MACT) requirements under the Clean Air Act and Resource Conservation and Recovery Act (RCRA). Currently, mercury accumulation in the calciner off-gas scrubbing system is transferred to the tank farm. These transfers lead to accumulation in the liquid heels of the tanks. The principal objective for aqueous phase mercury removal is heel mercury reduction. The system presents a challenge to traditional methods because of the presence of nitrogen oxides in the gas phase and high nitric acid in the aqueous scrubbing solution. Many old and new technologies were evaluated including sorbents and absorption in the gas phase and ion exchange, membranes/sorption, galvanic methods, and UV reduction in the aqueous phase. Process modifications and feed pre-treatment were also evaluated. Various properties of mercury and its compounds were summarized and speciation was predicted based on thermodynamics. Three systems (process modification, NOxidizer combustor, and electrochemical aqueous phase treatment) and additional technology testing were recommended.

  14. Mercury removal at Idaho National Engineering and Environmental Laboratory's New Waste Calciner Facility

    International Nuclear Information System (INIS)

    Ashworth, S.C.

    2000-01-01

    Technologies were investigated to determine viable processes for removing mercury from the calciner (NWCF) offgas system at the Idaho National Engineering and Environmental Laboratory. Technologies for gas phase and aqueous phase treatment were evaluated. The technologies determined are intended to meet EPA Maximum Achievable Control Technology (MACT) requirements under the Clean Air Act and Resource Conservation and Recovery Act (RCRA). Currently, mercury accumulation in the calciner off-gas scrubbing system is transferred to the tank farm. These transfers lead to accumulation in the liquid heels of the tanks. The principal objective for aqueous phase mercury removal is heel mercury reduction. The system presents a challenge to traditional methods because of the presence of nitrogen oxides in the gas phase and high nitric acid in the aqueous scrubbing solution. Many old and new technologies were evaluated including sorbents and absorption in the gas phase and ion exchange, membranes/sorption, galvanic methods, and UV reduction in the aqueous phase. Process modifications and feed pre-treatment were also evaluated. Various properties of mercury and its compounds were summarized and speciation was predicted based on thermodynamics. Three systems (process modification, NOxidizer combustor, and electrochemical aqueous phase treatment) and additional technology testing were recommended

  15. Command and Control of Joint Air Operations through Mission Command

    Science.gov (United States)

    2016-06-01

    and outlines the C2 architecture systems, processes, and philosophy of com- mand required to enable mission command effectively. Mission Command...General Dempsey highlights the fact that “trust is the moral sinew that binds the distributed Joint Force 2020 together” and observes that “unless...con- fident about how their subordinates will make decisions and adapt to the dynamic battlespace environment. Processes, Systems, and Philosophy of

  16. A facile route to the synthesis of anilinic electroactive colloidal hydrogels for neural tissue engineering applications.

    Science.gov (United States)

    Zarrintaj, Payam; Urbanska, Aleksandra M; Gholizadeh, Saman Seyed; Goodarzi, Vahabodin; Saeb, Mohammad Reza; Mozafari, Masoud

    2018-04-15

    An innovative drug-loaded colloidal hydrogel was synthesized for applications in neural interfaces in tissue engineering by reacting carboxyl capped aniline dimer and gelatin molecules. Dexamethasone was loaded into the gelatin-aniline dimer solution as a model drug to form an in situ drug-loaded colloidal hydrogel. The conductivity of the hydrogel samples fluctuated around 10 -5  S/cm which appeared suitable for cellular activities. Cyclic voltammetry was used for electroactivity determination, in which 2 redox states were observed, suggesting that the short chain length and steric hindrance prevented the gel from achieving a fully oxidized state. Rheological data depicted the modulus decreasing with aniline dimer increment due to limited hydrogen bonds accessibility. Though the swelling ratio of pristine gelatin (600%) decreased by the introduction and increasing the concentration of aniline dimer because of its hydrophobic nature, it took the value of 300% at worst, which still seems promising for drug delivery uses. Degradation rate of hydrogel was similarly decreased by adding aniline dimer. Drug release was evaluated in passive and stimulated patterns demonstrating tendency of aniline dimer to form a vesicle that controls the drug release behavior. The optimal cell viability, proper cell attachment and neurite extension was achieved in the case of hydrogel containing 10 wt% aniline dimer. Based on tissue/organ behavior, it was promisingly possible to adjust the characteristics of the hydrogels for an optimal drug release. The outcome of this simple and effective approach can potentially offer additional tunable characteristics for recording and stimulating purposes in neural interfaces. Copyright © 2018 Elsevier Inc. All rights reserved.

  17. Global Command and Control Management Structure

    National Research Council Canada - National Science Library

    1995-01-01

    This instruction establishes: responsibilities for the Joint Staff, Services, Defense agencies, combatant and functional unified commands, and other activities regarding management of Global Command and Control (GCC...

  18. The calculation and estimation of wastes generated by decommissioning of nuclear facilities. Tokai works and Ningyo-toge Environmental Engineering Center

    International Nuclear Information System (INIS)

    Ayame, Y.; Tanabe, T.; Takahashi, K.; Takeda, S.

    2001-07-01

    This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decommissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decommissioning of the nuclear facilities are as follows. (1) Tokai works: The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2) Ningyo-toge Environmental Engineering Center: The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton. (author)

  19. Modeling of release of radionuclides from an engineered disposal facility for shallow-land disposal of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Matsuzuru, H.; Suzuki, A.

    1989-01-01

    The computer code, ENBAR-1, for the simulation of radionuclide releases from an engineered disposal facility has been developed to evaluate the source term for subsequent migration of radionuclides in and through a natural barrier. The system considered here is that a waste package (waste form and container) is placed, together with backfill materials, into a concrete pit as a disposal unit for shallow-land disposal of low-level radioactive wastes. The code developed includes the following modules: water penetration into a concrete pit, corrosion of a drum as a container, leaching of radionuclides from a waste form, migration of radionuclides in backfill materials, release of radionuclides from the pit. The code has the advantage of its simplicity of operation and presentation while still allowing comprehensive evaluation of each element of an engineered disposal facility to be treated. The performance and source term of the facility might be readily estimated with a few key parameters to define the problem

  20. Command in the Objective Force

    National Research Council Canada - National Science Library

    Wilbeck, Christopher

    2003-01-01

    This paper seeks to answer what type of command will best serve the Army's Objective Force in gaining the initiative, building momentum, and exploiting success to achieve land dominance in the future...

  1. Combatant Commanders Informational Series: USPACOM

    National Research Council Canada - National Science Library

    Comnick, Michael

    1996-01-01

    ...) introducing potential joint staff officers to their specific command. Inbound staff officers, prepared by reviewing this product, arrive on station ready to receive specialized training without needing background indoctrination...

  2. Idaho National Engineering Laboratory response to the December 13, 1991, Congressional inquiry on offsite release of hazardous and solid waste containing radioactive materials from Department of Energy facilities

    International Nuclear Information System (INIS)

    Shapiro, C.; Garcia, K.M.; McMurtrey, C.D.; Williams, K.L.; Jordan, P.J.

    1992-05-01

    This report is a response to the December 13, 1991, Congressional inquiry that requested information on all hazardous and solid waste containing radioactive materials sent from Department of Energy facilities to offsite facilities for treatment or disposal since January 1, 1981. This response is for the Idaho National Engineering Laboratory. Other Department of Energy laboratories are preparing responses for their respective operations. The request includes ten questions, which the report divides into three parts, each responding to a related group of questions. Part 1 answers Questions 5, 6, and 7, which call for a description of Department of Energy and contractor documentation governing the release of waste containing radioactive materials to offsite facilities. ''Offsite'' is defined as non-Department of Energy and non-Department of Defense facilities, such as commercial facilities. Also requested is a description of the review process for relevant release criteria and a list of afl Department of Energy and contractor documents concerning release criteria as of January 1, 1981. Part 2 answers Questions 4, 8, and 9, which call for information about actual releases of waste containing radioactive materials to offsite facilities from 1981 to the present, including radiation levels and pertinent documentation. Part 3 answers Question 10, which requests a description of the process for selecting offsite facilities for treatment or disposal of waste from Department of Energy facilities. In accordance with instructions from the Department of Energy, the report does not address Questions 1, 2, and 3

  3. Spaceport Command and Control System User Interface Testing

    Science.gov (United States)

    Huesman, Jacob

    2016-01-01

    The Spaceport Command and Control System will be the National Aeronautics and Space Administration's newest system for launching commercial and government owned spacecraft. It's a large system with many parts all in need of testing. To improve upon testing already done by NASA engineers, the Engineering Directorate, Electrical Division (NE-E) of Kennedy Space Center has hired a group of interns each of the last few semesters to develop novel ways of improving the testing process.

  4. COR1 Engineering Test Unit Measurements at the NCAR/HAO Vacuum Tunnel Facility, October-November 2002

    Science.gov (United States)

    Thompson, William

    2002-01-01

    The Engineering Test Unit (ETU) of COR1 was made in two configurations. The first configuration, ETU-1, was for vibration testing, while the second, ETU-2, was for optical testing. This is a report on the optical testing performed on ETU-2 at the NCAR/HAO Vacuum Tunnel Facility during the months of October and November, 2002. This was the same facility used to test the two previous breadboard models. In both configurations, the first two tube sections were complete, with all optical elements aligned. The vibration model ETU-1 had the remaining tube sections attached, with mass models for the remaining optics, for the various mechanisms, and for the focal plane assembly. It was then converted into the optical model ETU-2 by removing tube sections 3 to 5, and mounting the remaining optics on commercial mounts. (The bandpass filter was also installed into tube 2, which had been replaced in ETU-1 by a mass model, so that pre- and post-vibration optical measurements could be made.) Doublet 2 was installed in a Newport LP-2 carrier, and aligned to the other optics in the first two tube sections. The LP-2 adjustment screws were then uralened so that the alignment could be maintained during shipping. Because neither the flight polarizer nor Hollow Core Motor were available, they were simulated by a commercial polarizer and rotational mount, both from Oriel corporation. The Oriel rotational stage was not designed for vacuum use, but it was determined after consultation with the company, and lab testing, that the stage could be used in the moderate vacuum conditions at the NCAR/HAO facility. The shutter and focal plane assembly were simulated with the same camera used for the previous two breadboard tests. The focal plane mask was simulated with a plane of BK7 glass with a mask glued on, using the same procedure as for the Lyot spot on Doublet 1, and mounted in an adjustable LP-2 carrier. Two masks were made, one made to the precise specifications of the optical design, the

  5. Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

    International Nuclear Information System (INIS)

    1988-09-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S ampersand A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S ampersand A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S ampersand A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs

  6. 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

  7. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1983

    International Nuclear Information System (INIS)

    1984-01-01

    Much achievement was obtained also in fiscal 1983 by the common utilization of the nuclear reactor ''Yayoi'' and the linear accelerator in the Nuclear Engineering Research Laboratory, University of Tokyo. These results were summarized, and this report is published. In the utilization of the reactor ''Yayoi'', the period of operation and the maximum output were limited very much, because long cooling period is necessary to prepare for the repair of fuel cladding in the next year. Also foreign research students commonly utilized the reactor ''Yayoi''. The common utilization of the linear accelerator was begun six years ago, and now it is carried out widely and smoothly. The total number of those who commonly utilized the facilities reached 3,179. The summaries of the results of 5 on-pile researches, 17 off-pile researches, and 16 researches using the linear accelerator are collected. The committee meetings and study meetings held in fiscal 1983 are listed. The names of the members of various committees and the names of those in charge of various experiments are given. (Kako, I.)

  8. Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

    Energy Technology Data Exchange (ETDEWEB)

    1988-09-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs.

  9. Design of multi-megawatt actively cooled beam dumps for the Neutral-Beam Engineering Test Facility

    International Nuclear Information System (INIS)

    Paterson, J.A.; Koehler, G.; Wells, R.P.

    1981-10-01

    The Neutral Beam Engineering Test Facility will test Neutral Beam Sources up to 170 keV, 65 Amps, with 30 second beam-on times. For this application actively cooled beam dumps for both the neutral and ionized particles will be required. The dumps will be able to dissipate a wide range of power density profiles by utilizing a standard modular panel design which is incorporated into a moveable support structure. The thermal hydraulic design of the panels permit the dissipation of 2 kW/cm 2 anywhere on the panel surface. The water requirements of the dumps are optimized by restricting the flow to panel sections where the heat flux falls short of the design value. The mechanical design of the beam-dump structures is described along with tests performed on a prototype panel. The prototype tests were performed on two different panel designs, one manufactured by Mc Donnell Douglas (MDAC) the other by United Technologies (UT). The dissipation capabilities of the panels were tested at the critical regions to verify their use in the beam dump assemblies

  10. The ergonomics of command and control

    OpenAIRE

    Stanton, NA; Baber, C

    2006-01-01

    Since its inception, just after the Second World War, ergonomics research has paid special attention to the issues surrounding human control of systems. Command and Control environments continue to represent a challenging domain for Ergonomics research. We take a broad view of Command and Control research, to include C2 (Command and Control), C3 (Command, Control and Communication), and C4 (Command, Control, Communication and Computers) as well as human supervisory control paradigms. This spe...

  11. Facility Bench of Stationary Engines for Study of Emissions (E65-PO) CIEMAT; Instalacion Banco de Motores Estacionarios para Estudio de Emisiones (E65-PO) CIEMAT

    Energy Technology Data Exchange (ETDEWEB)

    Rojas Garcia, E; Rodriguez Maroto, J J

    2007-07-01

    The Project of Technology of Aerosols in Generation of Energy, of the Department of Fossil Fuels of the CIEMAT, began in the year 2004, a research activity line, based on the study of the emissions coming from internal combustion engines, particularly of Diesel technology. Activity was continued by the Polluting Emissions Group of the Department of Environment, when becoming the original Project in this Group. From the concession to the Group, of the project GR/AMB/0119/2004 Evaluation of the Emissions of Biodiesel supported by the Autonomous Community of Madrid together with the European Regional Development Fund (ERDF), this activity was encourage, with the design, assembly and to get ready of the facility Bench of stationary engines for study of emissions, located in the building 65 at CIEMAT, Madrid. The present report constitutes a detailed technical description of each one of the elements that the installation Bench of stationary engines for study of emissions it integrated within the framework of the referred project (GR/AMB/0119/2004) and whose capacity includes studies of the effects of the engine, fuel, operation conditions, and methodology of sampling and measurement of emissions (gases and particles). The fundamental parts of facility describes in the present report are: engine test cell (cabin of sound insulation , ventilation and refrigeration system, anti vibrations mounting, engine, dynamometric brake), lines of preconditioning of particles and gases emissions (exhaust line, primary and secondary dilution lines, gases cleaning system...), other general parts of facility (sampling and measurement station, service lines...). The present report not only reflects the characteristics of the systems involved, but rather also in certain cases specified the procedure and reason for their choice. (Author) 10 refs.

  12. Summary of activities at the Engineered Barriers Test Facility, October 1, 1995 to January 31, 1997, and initial data

    International Nuclear Information System (INIS)

    Porro, I.; Keck, K.N.

    1997-03-01

    Replicates of two engineered barrier designs (a thick soil barrier and a bio/capillary barrier) were constructed in the test plots of the facility. Prior to placement of any soil in the test plots, instruments were calibrated and attached to plot instrument towers, which were then installed in the test plots. Soil from Spreading Area B was installed in the test plots in lifts and compacted. Instruments attached to the instrument tower were placed in shallow trenches dug in the lifts and buried. Each instrument was checked to make sure it functioned prior to installation of the next lift. Soil samples were collected from each lift in one plot during construction for later determination of physical and hydraulic properties. After completion of the test plots, the data acquisition system was finalized, and data collection began. Appropriate instrument calibration equations and equation coefficients are presented, and data reduction techniques are described. Initial data show test plot soils drying throughout the summer and early fall. This corresponds to low rainfall during this period. Infiltration of water into the test plots was first detected around mid-November with several subsequent episodes in December. Infiltration was verified by corresponding measurements from several different instruments ime domain reflectometry (TDR), neutron probe, thermocouple psychrometers, and heat dissipation sensors Tensiometer data does not appear to corroborate data from the other instruments. Test plots were warmer on the side closest to the access trench indicating a temperature effect from the trench. This resulted in greater soil moisture freezing with less and shallower infiltration on the far side of the plots than on the side closest to the trench. At the end of this monitoring period, infiltration in all but two of the test plots has reached the 155-cm depth. Infiltration in test plots B2 and S3 has reached only the 140-cm depth. The monitored infiltration events have not

  13. Radiological transportation risk assessment of the shipment of sodium-bonded fuel from the Fast Flux Test Facility to the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Green, J.R.

    1995-01-31

    This document was written in support of Environmental Assessment: Shutdown of the Fast Flux Test Facility (FFTF), Hanford Site, Richland, Washington. It analyzes the potential radiological risks associated with the transportation of sodium-bonded metal alloy and mixed carbide fuel from the FFTF on the Hanford Site in Washington State to the Idaho Engineering Laboratory in Idaho in the T-3 Cask. RADTRAN 4 is used for the analysis which addresses potential risk from normal transportation and hypothetical accident scenarios.

  14. Assessment of the Effectiveness of Clay Soil Covers as Engineered Barriers in Waste Disposal Facilities with Emphasis on Modeling Cracking Behavior

    Science.gov (United States)

    2008-06-01

    standard proctor hammer (ASTM D698), which was dropped a sufficient number of times to achieve the desired dry density ERDC TR-08-7 34 Figure...using a standard proctor hammer to an equivalent dry density as was found in Experiment 1. ERDC TR-08-7 45 Figure 25. Sample container for...ER D C TR -0 8- 7 Assessment of the Effectiveness of Clay Soil Covers as Engineered Barriers in Waste Disposal Facilities with Emphasis

  15. Radiological transportation risk assessment of the shipment of sodium-bonded fuel from the Fast Flux Test Facility to the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Green, J.R.

    1995-01-01

    This document was written in support of Environmental Assessment: Shutdown of the Fast Flux Test Facility (FFTF), Hanford Site, Richland, Washington. It analyzes the potential radiological risks associated with the transportation of sodium-bonded metal alloy and mixed carbide fuel from the FFTF on the Hanford Site in Washington State to the Idaho Engineering Laboratory in Idaho in the T-3 Cask. RADTRAN 4 is used for the analysis which addresses potential risk from normal transportation and hypothetical accident scenarios

  16. Indonesian Automatic Speech Recognition For Command Speech Controller Multimedia Player

    Directory of Open Access Journals (Sweden)

    Vivien Arief Wardhany

    2014-12-01

    Full Text Available The purpose of multimedia devices development is controlling through voice. Nowdays voice that can be recognized only in English. To overcome the issue, then recognition using Indonesian language model and accousticc model and dictionary. Automatic Speech Recognizier is build using engine CMU Sphinx with modified english language to Indonesian Language database and XBMC used as the multimedia player. The experiment is using 10 volunteers testing items based on 7 commands. The volunteers is classifiedd by the genders, 5 Male & 5 female. 10 samples is taken in each command, continue with each volunteer perform 10 testing command. Each volunteer also have to try all 7 command that already provided. Based on percentage clarification table, the word “Kanan” had the most recognize with percentage 83% while “pilih” is the lowest one. The word which had the most wrong clarification is “kembali” with percentagee 67%, while the word “kanan” is the lowest one. From the result of Recognition Rate by male there are several command such as “Kembali”, “Utama”, “Atas “ and “Bawah” has the low Recognition Rate. Especially for “kembali” cannot be recognized as the command in the female voices but in male voice that command has 4% of RR this is because the command doesn’t have similar word in english near to “kembali” so the system unrecognize the command. Also for the command “Pilih” using the female voice has 80% of RR but for the male voice has only 4% of RR. This problem is mostly because of the different voice characteristic between adult male and female which male has lower voice frequencies (from 85 to 180 Hz than woman (165 to 255 Hz.The result of the experiment showed that each man had different number of recognition rate caused by the difference tone, pronunciation, and speed of speech. For further work needs to be done in order to improving the accouracy of the Indonesian Automatic Speech Recognition system

  17. The Unspoken Consequence of Command, Control Communications Technology: Enhanced Micromanagement by Risk-Averse Commanders

    National Research Council Canada - National Science Library

    Carozza, John

    2004-01-01

    .... However, along with its benefits, this command, control and communications (C3) network includes the dangerous consequence of eroding the autonomy of tactical command through enhanced micromanagement by risk-averse operational commanders...

  18. Current status of a decommissioning project in the Enrichment Engineering Facility. Results in the second-half of the fiscal year of 2014

    International Nuclear Information System (INIS)

    Matsumoto, Takashi; Hayashibara, Kenichi; Ishimori, Yuu; Mita, Yutaka; Kakiya, Hideyoshi; Takahashi, Nobuo

    2016-11-01

    The Enrichment Engineering Facility of the Ningyo-toge Environmental Engineering Center was constructed in order to establish the technological basis of plant engineering for uranium enrichment in Japan. Uranium enrichment tests, using natural and reprocessed uranium, were carried out from 1979 to 1989 with two operation units in the facility. According to the decommissioning plan of the facility, UF 6 handling equipment and supplemental equipment in these plants are intended to be dismantled by 2019 in order to make vacant spaces for future projects use, for example, inventory investigation, precipitation treatment, etc. This report shows the current state of the decommissioning project in the second-half of the fiscal year of 2014, with indicating its schedule, procedure, situation, results, and so on. The dismantled materials generated amounted to 69 mesh containers and 191 drums, and the secondary waste generated amounted to 1,585.7 kg during the half year. In the fiscal year of 2014, the project was carried out according to the plan. The dismantled materials generated amounted to 153,938.1 kg as the whole of this period, and 36,343 kg from among them was treated as non-radioactive materials. (author)

  19. FENIX [Fusion ENgineering International eXperimental]: A test facility for ITER [International Thermonuclear Experimental Reactor] and other new superconducting magnets

    International Nuclear Information System (INIS)

    Slack, D.S.; Patrick, R.E.; Miller, J.R.

    1990-01-01

    The Fusion ENgineering International eXperimental (FENIX) Test Facility which is nearing completion at Lawrence Livermore National Laboratory, is a 76-t set of superconducting magnets housed in a 4-m-diameter cryostat. It represents a significant step toward meeting the testing needs for the development of superconductors appropriate for large-scale magnet applications such as the International Thermonuclear Experimental Reactor (ITER). The magnet set is configured to allow radial access to the 0.4-m-diameter high-field region where maximum fields up to 14 T will be provided. The facility is fitted with a thermally isolated test well with a port to the high-field region that allows insertion and removal of test conductors without disturbing the cryogenic environment of the magnets. It is expected that the facility will be made available to magnet developers internationally, and this paper discusses its general design features, its construction, and its capabilities

  20. 10 commandments of smile esthetics

    Science.gov (United States)

    Machado, Andre Wilson

    2014-01-01

    The search for esthetic treatment has persisted in the routine of dental professionals. Following this trend, dental patients have sought treatment with the primary aim of improving smile esthetics. The aim of this article is to present a protocol to assess patient's smile: The 10 Commandments of smile esthetics. PMID:25279532

  1. United States Southern Command * Home

    Science.gov (United States)

    or concerns please email or call us at 305-437-2287. Testing The USAG- Miami Joint Education Testing the Air Force | The Air University | US Air Force Academy Army: Army Continued Education System | Army Marine Corps Institute | US Marine Corps Training and Education Command | US Marine Corps University Navy

  2. Control of fast non linear systems - application to a turbo charged SI engine with variable valve timing; controle des systemes rapides non lineaires - application au moteur a allumage commande turbocompresse a distribution variable

    Energy Technology Data Exchange (ETDEWEB)

    Colin, G.

    2006-10-15

    Spark ignition engine control has become a major issue for the compliance with emissions legislation while ensuring driving comfort. Engine down-sizing is one of the promising ways to reduce fuel consumption and resulting CO{sub 2} emissions. Combining several existing technologies such as supercharging and variable valve actuation, down-sizing is a typical example of the problems encountered in Spark Ignited (SI) engine control: nonlinear systems with saturation of actuators; numerous major physical phenomena not measurable; limited computing time; control objectives (consumption, pollution, performance) often competing. A methodology of modelling and model-based control (internal model and predictive control) for these systems is also proposed and applied to the air path of the down-sized engine. Models, physicals and generics, are built to estimate in-cylinder air mass, residual burned gases mass and air scavenged mass from the intake to the exhaust. The complete and generic engine torque control architecture for the turbo-charged SI engine with variable cam-shaft timing was tested in simulation and experimentally (on engine and vehicle). These tests show that new possibilities are offered in order to decrease pollutant emissions and optimize engine efficiency. (author)

  3. 32 CFR 700.1053 - Commander of a task force.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 5 2010-07-01 2010-07-01 false Commander of a task force. 700.1053 Section 700... Command Detail to Duty § 700.1053 Commander of a task force. (a) A geographic fleet commander, and any other naval commander, may detail in command of a task force, or other task command, any eligible...

  4. A Real-Time Implementable NMPC Output Feedback for a Diesel Engine Air Path Commande prédictive non linéaire avec retour de sortie implémentable en temps-réel pour un circuit d’air d’un moteur Diesel

    Directory of Open Access Journals (Sweden)

    Murilo A.

    2011-09-01

    Full Text Available In this paper, an experimental validation of a parameterized Nonlinear Model Predictive Control (NMPC scheme with a Moving Horizon Observer (MHO is presented for a Diesel engine air path. The control design based on the parameterized approach leads to a low dimensional optimization problem which makes the proposed controller real-time implementable. An attractive feature of this control strategy lies in its compatibility with more elaborated and fully nonlinear models since it uses the model as a black box predictor. Dans cet article, une validation expérimentale d’un schéma de commande prédictive non linéaire (CPNL paramétrique avec un observateur à horizon glissant a été proposé pour le circuit d’air d’un moteur Diesel. La stratégie de commande basée sur l’approche paramétrique à faible dimension s’est montrée implémentable en temps réel et peut être utilisée aussi en tant qu’une solution du type boîte noire indépendamment de la structure du modèle non linéaire.

  5. Ready...Set... Command! Rethinking Training for Squadron Commanders

    Science.gov (United States)

    2016-02-16

    commander faces many difficult challenges. When discussing the Air Force’s troubling trend in suicide rates, Airmen “blame being overworked ...Air Forces total suicides despite making up only 16 percent of the service.3 Three years later the Air Force Times reveals continued challenges in...23 challenges. They must address complex issues facing the Air Force, such as troubling suicide rates, manning shortfalls, decreasing resources

  6. 76 FR 19893 - Unified Command Plan 2011

    Science.gov (United States)

    2011-04-08

    ... Plan 2011 Memorandum for the Secretary of Defense Pursuant to my authority as Commander in Chief, I hereby approve and direct the implementation of the revised Unified Command Plan. Consistent with title...

  7. Issues and Solutions for Command Post Simulations

    National Research Council Canada - National Science Library

    Stytz, Martin R; Banks, Sheila B

    2006-01-01

    .... Unfortunately, the modeling of joint command post teams is still very much in its infancy and this lack of foundational research hinders our ability to assess the performance of command post teams...

  8. Command Decision-Making: Experience Counts

    National Research Council Canada - National Science Library

    Wolgast, Kelly A

    2005-01-01

    Decision-making is the mainstay of military leadership and command. Due to the changed nature of the current military environment, military commanders can no longer rely solely on the traditional Military Decision-making Process (MDMP...

  9. XRF, XRD and SEM facilities in the School of Materials and Mineral Resources Engineering, Universiti Sains Malaysia

    International Nuclear Information System (INIS)

    Azmi Rahmat

    1996-01-01

    The School has acquired excellent facilities for elemental analysis by XRF and EDX and phase analysis by XRD. The type of research work carried out in the School is described. The school also assists the local industries in trying to solve their problems fully utilizing these facilities along with other testing units

  10. Ground facility for information reception, processing, dissemination and scientific instruments management setup in the CORONAS-PHOTON space project

    Science.gov (United States)

    Buslov, A. S.; Kotov, Yu. D.; Yurov, V. N.; Bessonov, M. V.; Kalmykov, P. A.; Oreshnikov, E. M.; Alimov, A. M.; Tumanov, A. V.; Zhuchkova, E. A.

    2011-06-01

    This paper deals with the organizational structure of ground-based receiving, processing, and dissemination of scientific information created by the Astrophysics Institute of the Scientific Research Nuclear University, Moscow Engineering Physics Institute. Hardware structure and software features are described. The principles are given for forming sets of control commands for scientific equipment (SE) devices, and statistics data are presented on the operation of facility during flight tests of the spacecraft (SC) in the course of one year.

  11. Considerations on command and response language features for a network of heterogeneous autonomous computers

    Science.gov (United States)

    Engelberg, N.; Shaw, C., III

    1984-01-01

    The design of a uniform command language to be used in a local area network of heterogeneous, autonomous nodes is considered. After examining the major characteristics of such a network, and after considering the profile of a scientist using the computers on the net as an investigative aid, a set of reasonable requirements for the command language are derived. Taking into account the possible inefficiencies in implementing a guest-layered network operating system and command language on a heterogeneous net, the authors examine command language naming, process/procedure invocation, parameter acquisition, help and response facilities, and other features found in single-node command languages, and conclude that some features may extend simply to the network case, others extend after some restrictions are imposed, and still others require modifications. In addition, it is noted that some requirements considered reasonable (user accounting reports, for example) demand further study before they can be efficiently implemented on a network of the sort described.

  12. On Preparing for Squadron Command

    Science.gov (United States)

    1988-04-01

    Gortler, Majur Gordon D. "Management Development---Could the Air Force Be Doing More?" Resear,;h Study, Air Command and Staff College. 1 07:3. 20...ABSTRACT (Continue on reverse If necessary and identify by block number) -This study addresses the broad issue of preparing Air Force officers for...are obsolete. SECURITY CLASSIFICATION OF THIS PAGE UNCLASSIFIED - - PREFACE This study addresses the broad Issue of preparing Air Force officers to

  13. Command and Control : faster decisions

    CSIR Research Space (South Africa)

    Venter, C

    2012-10-01

    Full Text Available Decisions 4th Biennial Conference Presented by Cobus Venter 10 October 2012 ? CSIR 2012 Slide 2 Command and Control Planning TaskingControl Assessment Si tu at io n DPSS Objective Ends Increase the Defence Capability of South Africa Ways... Supported by SAAB THALES Global CommsDPSS DDSI ERGOTECH Cooperation to make it work Example 1: Future SA Army Strategy and Joint Operations Support Campus Experiment Example 1: Future SA Army Strategy and Joint Operations Support Campus Experiment...

  14. Disposal facility building also is mining engineering. Germany can tap into this expertise and planning potential; Endlagerbergbau ist auch Bergbau. Erfahrungs- und Planungspotential in Deutschland

    Energy Technology Data Exchange (ETDEWEB)

    Hucke, Andreas; Kohl, Nadine; Scior, Carsten; Gutberlet, Daniela [DMT GmbH und Co.KG, Essen (Germany)

    2015-07-01

    The conventional mining industry has a rich tradition and as mining is practised all over the world under a whole range of different conditions the industry has witnessed all kinds of technical developments aimed at controlling strata behaviour and winning the target mineral as efficiently as possible. The proposed use of deep geological deposits as disposal facilities for nuclear waste has transformed the role of the mining Industry and instead of extracting material from the ground mining engineers are now focussing more on how to store waste material safely deep below the earth's surface. Nevertheless, this new remit retains many of the key aspects of conventional mining and the experience that the industry has built up over the years Is still of vital importance when it comes to selecting a suitable disposal site and planning a final waste disposal facility in deep geological formations. These processes benefit from the support of specialists with a mining engineering background, as this can help to avoid unnecessary delays, additional costs and potential damage to public image. The following paper describes some of the expertises and methods developed by the conventional extraction industry that are also of relevance for the construction of disposal facilities.

  15. Savannah River Plant engineering and design history. Volume 4: 300/700 Areas & general services and facilities

    Energy Technology Data Exchange (ETDEWEB)

    1957-01-01

    The primary function of the 300 Area is the production and preparation of the fuel and target elements required for the 100 Area production reactors. Uranium slugs and lithium-aluminium alloy control and blanket rods are prepared in separate structures. Other facilities include a test pile, a physics assembly laboratory, an office and change house, an electrical substation, and various service facilities such as rail lines, roads, sewers, steam and water distribution lines, etc. The 700 Area contains housing and facilities for plant management, general plant services, and certain technical activities. The technical buildings include the Main Technical Laboratory, the Waste Concentration Building, the Health Physics Headquarters, and the Health Physics Calibration building. Sections of this report describe the following: development of the 300-M Area; selection and description of process; design of main facilities of the 300 Area; development of the 700-A Area; design of the main facilities of the 700 Area; and general services and facilities, including transportation, plant protection, waste disposal and drainage, site work, pilot plants, storage, and furniture and fixtures.

  16. STS-29 Commander Coats in JSC fixed base (FB) shuttle mission simulator (SMS)

    Science.gov (United States)

    1986-01-01

    STS-29 Discovery, Orbiter Vehicle (OV) 103, Commander Michael L. Coats sits at commanders station forward flight deck controls in JSC fixed base (FB) shuttle mission simulator (SMS). Coats, wearing communications kit assembly headset and flight coveralls, looks away from forward control panels to aft flight deck. Pilots station seat back appears in foreground. FB-SMS is located in JSC Mission Simulation and Training Facility Bldg 5.

  17. STS-26 Commander Hauck in fixed based (FB) shuttle mission simulator (SMS)

    Science.gov (United States)

    1988-01-01

    STS-26 Discovery, Orbiter Vehicle (OV) 103, Commander Frederick H. Hauck, wearing comunications kit assembly headset and seated in the commanders seat on forward flight deck, looks over his shoulder toward the aft flight deck. A flight data file (FDF) notebook rests on his lap. The STS-26 crew is training in the fixed base (FB) shuttle mission simulator (SMS) located in JSC Mission Simulation and Training Facility Bldg 5.

  18. Principal provisions of engineering and geological survey methodology in designing and construction of underground laboratory as a part of facility of RW underground isolation

    International Nuclear Information System (INIS)

    Prokopova, O.A.

    2006-01-01

    The most critical moment is the choice of a site for radioactive waste geological repository. Here the role of engineering and geological prospecting as a basis for the construction of a facility for underground isolation appears especially important; it is followed by finding a suitable area and subsequent allocation of the site and facility construction sites. The decision on the selection of construction site for the underground repository is taken by the principle 'descent from the general to the particular', which is a continuous process with the observance of stages in research for the design and exploration work. Each stage of research is typified by specific scale and methods of geological and geophysical studies and scientific research to be fulfilled in scopes sufficient for solution of basic problems for the designing. (author)

  19. Heated Tube Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Heated Tube Facility at NASA GRC investigates cooling issues by simulating conditions characteristic of rocket engine thrust chambers and high speed airbreathing...

  20. Field Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Field Research Facility (FRF) located in Duck, N.C. was established in 1977 to support the U.S. Army Corps of Engineers' coastal engineering mission. The FRF is...

  1. Definition and implementation of internal model control laws for a direct injection engine; Definition et mise en oeuvre de lois de commande a modele interne pour un moteur thermique a injection directe d'essence

    Energy Technology Data Exchange (ETDEWEB)

    Grousson, F.

    2000-10-03

    This study has been achieved in order to improve the direct injection engine control, by using internal model control strategies. Its aim is to optimise the engine performance and to decrease the polluting emissions through a better dynamic control. The use of internal model controls brings robustness in order to face the engine parameter disparity and allows great improvements in the control calibration thanks to a shorter tuning time. The first part gives the outlines of thermic engine operating and focuses on modeling with the final control in view. The second part tackles the implementation of regulation algorithms. Firstly, the air path control uses the state feedback linearization mixed with the predictive control. Secondly, the torque control of the driver's requests is performed with a static inversion using the Jacobian matrix. Finally, a simplified predictive control makes it possible to solve idle speed regulation problems. The last part is devoted to real time and fast proto-typing tests. The main simulation results have been validated through experimental tests on a direct injection car. (author)

  2. Cognitive Systems Modeling and Analysis of Command and Control Systems

    Science.gov (United States)

    Norlander, Arne

    2012-01-01

    Military operations, counter-terrorism operations and emergency response often oblige operators and commanders to operate within distributed organizations and systems for safe and effective mission accomplishment. Tactical commanders and operators frequently encounter violent threats and critical demands on cognitive capacity and reaction time. In the future they will make decisions in situations where operational and system characteristics are highly dynamic and non-linear, i.e. minor events, decisions or actions may have serious and irreversible consequences for the entire mission. Commanders and other decision makers must manage true real time properties at all levels; individual operators, stand-alone technical systems, higher-order integrated human-machine systems and joint operations forces alike. Coping with these conditions in performance assessment, system development and operational testing is a challenge for both practitioners and researchers. This paper reports on research from which the results led to a breakthrough: An integrated approach to information-centered systems analysis to support future command and control systems research development. This approach integrates several areas of research into a coherent framework, Action Control Theory (ACT). It comprises measurement techniques and methodological advances that facilitate a more accurate and deeper understanding of the operational environment, its agents, actors and effectors, generating new and updated models. This in turn generates theoretical advances. Some good examples of successful approaches are found in the research areas of cognitive systems engineering, systems theory, and psychophysiology, and in the fields of dynamic, distributed decision making and naturalistic decision making.

  3. Evaluation of the Space and Naval Warfare Systems Command (SPAWAR) Cost and Performance Measurement

    OpenAIRE

    Flavell, Drew G.; Dorwin, Timothy E.

    1999-01-01

    Approved for public release; distribution is unlimited. This thesis examines the Cost and Performance Measurements within four Program Directorates at the Space and Naval Warfare Systems Command (SPAWAR). SPAWAR is the Navy's full-spectrum research, development, test and evaluation, engineering and fleet support center for Command, Control and Communications Systems, Ocean Surveillance Systems and the integration of those systems that overarch multiplatforms. In the era of lean military bu...

  4. National Solar Thermal Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The National Solar Thermal Test Facility (NSTTF) is the only test facility in the United States of its type. This unique facility provides experimental engineering...

  5. Commanders of the Great Victory

    Directory of Open Access Journals (Sweden)

    Anatoly Dmitriyevich Borshchov

    2015-01-01

    Full Text Available The honorary title of «commander» as well as the «admiral» is granted to a military or naval figure on the basis of public recognition of his personal contribution to the success of actions. Generals are usually individuals with creative thinking, the ability to foresee the development of military events. Generals usually have such personality traits as a strong will and determination, rich combat experience, credibility and high organizational skills. In an article dedicated to the 70th anniversary of the Soviet victory in the Great War examines the experience of formation and practice of the most talent-ed Soviet military leaders.

  6. Spark ignition engine control: estimation and prediction of the in-cylinder mass and chemical species; Controle moteur a allumage commande: estimation / prediction de la masse et de la composition du melange enferme dans le cylindre

    Energy Technology Data Exchange (ETDEWEB)

    Giansetti, P.

    2005-09-15

    Spark ignition engine control has become a major issue regarding compliance with emissions legislation while ensuring driving comfort. The objective of this thesis was to estimate the mass and composition of gases inside the cylinder of an engine based on physics in order to insure better control of transient phases taking into account residual gases as well as exhaust gas recirculation. Residual gas fraction has been characterized using two experiments and one CFD code. A model has been validated experimentally and integrated into an observer which predicts pressure and temperature inside the manifold. The predictions of the different gas flows and the chemical species inside the cylinder are deduced. A closed loop observer has been validated experimentally and in simulation. Moreover, an algorithm estimating the fresh and burned gas mass from the cylinder pressure has been proposed in order to obtain the information cycle by cycle and cylinder by cylinder. (author)

  7. Report of the research results with University of Tokyo Nuclear Engineering Research Laboratory's facilities in fiscal 1975

    International Nuclear Information System (INIS)

    1976-08-01

    Results of the research works by educational institutions using fast neutron source reactor 'Yayoi' etc. of Nuclear Engineering Research Laboratory in fiscal 1975 are reported in individual summaries. Fields of research are the following: shielding benchmark experiment, research on medical irradiation, irradiation experiments, experiments by small research groups, fast neutron streaming experiment, and so on. (Mori, K.)

  8. DolphinAtack: Inaudible Voice Commands

    OpenAIRE

    Zhang, Guoming; Yan, Chen; Ji, Xiaoyu; Zhang, Taimin; Zhang, Tianchen; Xu, Wenyuan

    2017-01-01

    Speech recognition (SR) systems such as Siri or Google Now have become an increasingly popular human-computer interaction method, and have turned various systems into voice controllable systems(VCS). Prior work on attacking VCS shows that the hidden voice commands that are incomprehensible to people can control the systems. Hidden voice commands, though hidden, are nonetheless audible. In this work, we design a completely inaudible attack, DolphinAttack, that modulates voice commands on ultra...

  9. Scale-free Enterprise Command & Control

    National Research Council Canada - National Science Library

    Bayne, Jay; Paul, Raymond

    2005-01-01

    ...) services that provide allied teams of commanders, planners and operations personnel with collaborative, grid-based and realtime situation assessment, plan generation, and plan execution services...

  10. Structured multi-stream command language

    International Nuclear Information System (INIS)

    Glad, A.S.

    1982-12-01

    A multi-stream command language was implemented to provide the sequential and decision-making operations necessary to run the neutral-beam ion sources connected to the Doublet III tokamak fusion device. A multi-stream command language was implemented in Pascal on a Classic 7870 running under MAX IV. The purpose of this paper is threefold. First, to provide a brief description of the programs comprising the command language including the operating system interaction. Second, to give a description of the language syntax and commands necessary to develop a procedure stream. Third, to provide a description of the normal operating procedures for executing either the sequential or interactive streams

  11. Command and Control for Homeland Security

    National Research Council Canada - National Science Library

    Greene, Marjorie

    2007-01-01

    ... Analysis of the Toronto SARS Outbreak, Vertical Integration, Vertical Integration in a Military Command Hierarchy, Information flows for a domestic incident, C2 for Homeland Security will benefit...

  12. Mission Command: Elasticity, Equilibrium, Culture, and Intent

    National Research Council Canada - National Science Library

    Stewart, Keith G

    2006-01-01

    .... It is enabled by decentralization of authority and responsibility that allows subordinate commanders the latitude to plan and conduct operations based upon their understanding of the local situation...

  13. Mesure et modélisation multidimensionnelle des transferts thermiques gaz-paroi dans le cas des moteurs à allumage commandé Measurement and Multidimensional Modeling of Gas-Wall Heat Transfers in Spark-Ignition Engines

    Directory of Open Access Journals (Sweden)

    Gilaber P.

    2006-11-01

    formulation k-epsilon de la turbulence a été adoptée. La sensibilité du modèle aux effets de densité et de turbulence a été testée par l'intermédiaire de variations de l'avance à l'allumage et du régime. La comparaison entre mesure et simulation a montré un bon accord, tant en termes de flux thermiques locaux et instantanés, qu'en termes de bilan global. The computational fluid dynamics codes, which help to predict the behaviour of combusting gas in reciprocating engines, need, as boundary conditions for the momentum and energy equations, to approximate wall frictions and heat transfer between gas and walls. The purpose of this work is to validate a heat transfer model for spark ignited engines. Two steps of research have been worked on to meet this objective: an experimental phase and a computational phase. In the experimental phase, measurements were made on a test-engine instrumented with fast-response surface heat flux gages. Each gage consisted of a steel cylinder, containing two thermocouples. To analyze the influence of fluid dynamics on heat transfer, a Laser Doppler Velocimeter was used, by means of a spacer placed between the engine head and cylinder. The spacer was equiped with two windows and two heat-flux gages permitting simultaneous measurements of the heat flux and of the fluid dynamics outside the boundary layer. Two other gages were present in the head of the engine and up to ten data inputs could be simultaneously recorded at each crank-angle, including two velocity components and the cylinder pressure. A parametric analysis was carried out revealing the following trends:- the global heat transfer rate for a thermodynamic cycle of the engine decreases as the speed of the engine is increased, but the peak value of the wall heat-flux increases because of the increase of the turbulence level. - the volumetric efficiency appeared to have little effect on the turbulence level, and its influence on the heat transfer is mainly due to the increase of

  14. Preliminary engineering report waste area grouping 5, Old Hydrofracture Facility Tanks content removal project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1996-06-01

    The Superfund Amendments and Reauthorization Act of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facilities Agreement (FFA) for federal facilities placed on the National Priorities List. The Oak Ridge Reservation was placed on that list on December 21, 1989, and the agreement was signed in November 1991 by the U.S. Department of Energy (DOE) Oak Ridge Operations Office, the U.S. Environmental Protection Agency (EPA) Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA is January 1, 1992. One objective of the FFA is to ensure that liquid low-level waste (LLLW) tanks that are removed from service are evaluated and remediated through the CERCLA process. Five inactive LLLW tanks, designated T-1, T-2, T-3, T-4, and T-9, located at the Old Hydrofracture (OHF) Facility in the Melton Valley area of Oak Ridge National Laboratory (ORNL) have been evaluated and are now entering the remediation phase. As a precursor to final remediation, this project will remove the current liquid and sludge contents of each of the five tanks (System Requirements Document, Appendix A). It was concluded in the Engineering Evaluation/Cost Analysis [EE/CA] for the Old Hydrofracture Facility Tanks (DOE 1996) that sluicing and pumping the contaminated liquid and sludge from the five OHF tanks was the preferred removal action. Evaluation indicated that this alternative meets the removal action objective and can be effective, implementable, and cost-effective. Sluicing and removing the tank contents was selected because this action uses (1) applicable experience, (2) the latest information about technologies and techniques for removing the wastes from the tanks, and (3) activities that are currently acceptable for storage of transuranic (TRU) mixed waste

  15. Command and Service Module Communications

    Science.gov (United States)

    Interbartolo, Michael

    2009-01-01

    This viewgraph presentation examines Command and Service Module (CSM) Communications. The communication system's capabilities are defined, including CSM-Earth, CSM-Lunar Module and CSM-Extravehicular crewman communications. An overview is provided for S-band communications, including data transmission and receiving rates, operating frequencies and major system components (pre-modulation processors, unified S-band electronics, S-band power amplifier and S-band antennas). Additionally, data transmission rates, operating frequencies and the capabilities of VHF communications are described. Major VHF components, including transmitters and receivers, and the VHF multiplexer and antennas are also highlighted. Finally, communications during pre-launch, ascent, in-flight and entry are discussed. Overall, the CSM communication system was rated highly by flight controllers and crew. The system was mostly autonomous for both crew and flight controllers and no major issues were encountered during flight.

  16. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1986

    International Nuclear Information System (INIS)

    1987-01-01

    This book contains a large number of reports of studies made in 1986 through joint utilization of the nuclear reactor 'Yayoi' and electron beam type accelerator which are installed in the Nuclear engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The reports presented deal with 'Behaviors of Neutrons in Fast Reactor Blanket Shield', 'Effect of Fast Neutron Radiation on Organic Materials', 'Production and Recovery of Tritium in Nuclear Fusion Reactor Blanket System', 'Bench Mark Experiment of Effect of Atmospheric Scattering of Neutron', 'Experimental Evaluation of Nuclear Heat Rate', 'Fast Neutron Shielding Experiment', 'Effect of Fast Neutron Radiation on Hot Water', 'Neutron Shielding Experiment', 'Biological and Medical Application of 'Yayoi' Neutron', 'Effect of Fission-Fusion Correlation Radiation on Semiconductors (Si, GaAs)', 'Application of Fast Neutron to Radiography Technology', 'Streaming in Offset Slit', 'Design and Evaluation of New Reactor', 'LET Effect on Organic Material', 'Handling, Separation and Recovery of Transuranium Elements', 'Reactor Operation Support System Using Knowledge Engineering Technique', 'Application of Shape Memory Alloys to Nuclear Reactor Devices', 'Numerical Simulation of Turbulent Hear Transfer', and many other studies. (Nogami, K.)

  17. A mathematical model for the performance assessment of engineering barriers of a typical near surface radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Antonio, Raphaela N.; Rotunno Filho, Otto C. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Lab. de Hidrologia e Estudos do Meio Ambiente]. E-mail: otto@hidro.ufrj.br; Ruperti Junior, Nerbe J.; Lavalle Filho, Paulo F. Heilbron [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)]. E-mail: nruperti@cnen.gov.br

    2005-07-01

    This work proposes a mathematical model for the performance assessment of a typical radioactive waste disposal facility based on the consideration of a multiple barrier concept. The Generalized Integral Transform Technique is employed to solve the Advection-Dispersion mass transfer equation under the assumption of saturated one-dimensional flow, to obtain solute concentrations at given times and locations within the medium. A test-case is chosen in order to illustrate the performance assessment of several configurations of a multi barrier system adopted for the containment of sand contaminated with Ra-226 within a trench. (author)

  18. A mathematical model for the performance assessment of engineering barriers of a typical near surface radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Antonio, Raphaela N.; Rotunno Filho, Otto C.

    2005-01-01

    This work proposes a mathematical model for the performance assessment of a typical radioactive waste disposal facility based on the consideration of a multiple barrier concept. The Generalized Integral Transform Technique is employed to solve the Advection-Dispersion mass transfer equation under the assumption of saturated one-dimensional flow, to obtain solute concentrations at given times and locations within the medium. A test-case is chosen in order to illustrate the performance assessment of several configurations of a multi barrier system adopted for the containment of sand contaminated with Ra-226 within a trench. (author)

  19. 32 CFR 215.7 - Command relationships.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 2 2010-07-01 2010-07-01 false Command relationships. 215.7 Section 215.7 National Defense Department of Defense (Continued) OFFICE OF THE SECRETARY OF DEFENSE (CONTINUED) MISCELLANEOUS EMPLOYMENT OF MILITARY RESOURCES IN THE EVENT OF CIVIL DISTURBANCES § 215.7 Command relationships...

  20. The Marihuana Dilemma: Challenge to Commanders.

    Science.gov (United States)

    The marihuana dilemma poses a major challenge to commanders in the US Army today. The problem was analyzed as to the characteristics of the drug...available to commanders to meet the challenge. The essay concludes that marihuana should not be legalized; drug users or former drug users should not be

  1. XTCE. XML Telemetry and Command Exchange Tutorial

    Science.gov (United States)

    Rice, Kevin; Kizzort, Brad; Simon, Jerry

    2010-01-01

    An XML Telemetry Command Exchange (XTCE) tutoral oriented towards packets or minor frames is shown. The contents include: 1) The Basics; 2) Describing Telemetry; 3) Describing the Telemetry Format; 4) Commanding; 5) Forgotten Elements; 6) Implementing XTCE; and 7) GovSat.

  2. Capturing a Commander's decision making style

    Science.gov (United States)

    Santos, Eugene; Nguyen, Hien; Russell, Jacob; Kim, Keumjoo; Veenhuis, Luke; Boparai, Ramnjit; Stautland, Thomas Kristoffer

    2017-05-01

    A Commander's decision making style represents how he weighs his choices and evaluates possible solutions with regards to his goals. Specifically, in the naval warfare domain, it relates the way he processes a large amount of information in dynamic, uncertain environments, allocates resources, and chooses appropriate actions to pursue. In this paper, we describe an approach to capture a Commander's decision style by creating a cognitive model that captures his decisionmaking process and evaluate this model using a set of scenarios using an online naval warfare simulation game. In this model, we use the Commander's past behaviors and generalize Commander's actions across multiple problems and multiple decision making sequences in order to recommend actions to a Commander in a manner that he may have taken. Our approach builds upon the Double Transition Model to represent the Commander's focus and beliefs to estimate his cognitive state. Each cognitive state reflects a stage in a Commander's decision making process, each action reflects the tasks that he has taken to move himself closer to a final decision, and the reward reflects how close he is to achieving his goal. We then use inverse reinforcement learning to compute a reward for each of the Commander's actions. These rewards and cognitive states are used to compare between different styles of decision making. We construct a set of scenarios in the game where rational, intuitive and spontaneous decision making styles will be evaluated.

  3. 32 CFR 552.65 - Command supervision.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 3 2010-07-01 2010-07-01 true Command supervision. 552.65 Section 552.65 National Defense Department of Defense (Continued) DEPARTMENT OF THE ARMY MILITARY RESERVATIONS AND NATIONAL CEMETERIES REGULATIONS AFFECTING MILITARY RESERVATIONS Solicitation on Military Reservations § 552.65 Command supervision. (a) All insurance...

  4. Investigation of Thermal Comfort Conditions in Higher Education Facilities: A Case Study for Engineering Faculty in Edirne

    Directory of Open Access Journals (Sweden)

    E. Mıhlayanlar

    2017-02-01

    Full Text Available In this study, a higher education institution in Edirne (Trakya University Engineering Faculty is investigated for indoor thermal comfort conditions of the classrooms (indoor temperature, relative humidity, average radiant temperature, “Satisfaction from thermal environment” (PMV and “Dissatisfaction from thermal environment” (PPD. The classrooms in the institution are heated by a central heating system and utilise natural ventilation system. Measurements were taken with the proper devices at the same time of the weekdays during lecture times in winter (heating season in December. The results obtained from measurements are given in graphics and compared with the values given in ASHRAE 55 and ISO 7730 standards.

  5. Report of the research results with University of Tokyo, Nuclear Engineering Research laboratory's Facilities in fiscal 1992

    International Nuclear Information System (INIS)

    1993-01-01

    This publication summarizes the results of the joint utilization of the research 'Yayoi' and the electron beam accelerator in the Nuclear Engineering Research Laboratory, University of Tokyo, in the fiscal year 1992. The Yayoi was operated smoothly through the year, and the number of research themes, for which the reactor Yayoi was jointly utilized and the related themes reached 23 cases. The research themes of the linac count up to 17, after its reconstruction to be twin-linac. In this publication, in addition to the utilization reports, also the 16 reports of Yayoi Study Meetings held in fiscal year 1992 are collected. (J.P.N.)

  6. Evaluation of technologies for remediation of disposed radioactive and hazardous wastes in a facility at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Reno, H.W.; Martin, D.D.; Rasmussen, T.L.

    1989-01-01

    For the past twenty years the US Department of Energy has been investigating and evaluating technologies for the long term management of disposed transuranic contaminated wastes at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. More than fifty technologies have been investigated and evaluated and three technologies have been selected for feasibility study demonstration at the complex. This paper discusses the evaluation of those technologies and describes the three technologies selected for demonstration. The paper further suggests that future actions under the Comprehensive Environmental Response, Compensation, and Liability Act should build from previous evaluations completed heretofore. 18 refs., 3 figs., 1 tab

  7. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1989

    International Nuclear Information System (INIS)

    1990-01-01

    This is the report of the results of research carried out by the common utilization of the reactor 'Yayoi' and an electron accelerator in the Nuclear Engineering Research Laboratory in fiscal year 1989. In fiscal year 1989, the research themes using the reactor Yayoi or related to it were 15, and those using the linear accelerator reached 12, thus the common utilization attracted the strong interest of users. The Yayoi has been operated satisfactorily without trouble. The results of the research carried out by the common utilization of the Yayoi and a linac and the reports of 12 Yayoi research meetings in fiscal year 1989 are collected. (J.P.N.)

  8. Collaborative Russian-US work in nuclear material protection, control and accounting at the Institute of Physics and Power Engineering. II. extension to additional facilities

    International Nuclear Information System (INIS)

    Kuzin, V.V.; Pshakin, G.M.; Belov, A.P.

    1996-01-01

    During 1995, collaborative Russian-US nuclear material protection, control and accounting (MPC ampersand A) tasks at the Institute of Physics and Power Engineering (IPPE) in Obninsk, Russia focused on improving the protection of nuclear materials at the BFS Fast Critical Facility. BFS has thousands of fuel disks containing highly enriched uranium and weapons-grade plutonium that are used to simulate the core configurations of experimental reactors in two critical assemblies. Completed tasks culminated in demonstrations of newly implemented equipment and methods that enhanced the MPC ampersand A at BFS through computerized accounting, nondestructive inventory verification measurements, personnel identification and assess control, physical inventory taking, physical protection, and video surveillance. The collaborative work is now being extended. The additional tasks encompass communications and tamper-indicating devices; new storage alternatives; and systemization of the MPC ampersand A elements that are being implemented

  9. An incident command system in practice and reality

    International Nuclear Information System (INIS)

    Spitzer, J.D.

    1992-01-01

    The basic organizational problems and options for forming a pollution response organization are described. Problems with multi-agency response organizations include poor coordination and lack of accountability. Alternatives to autonomous organizations operating with minimal coordination are the multi-agency/organization teams working under a controlling organization, and organizations formed into a single response organization (the incident command system or ICS). Design criteria for an ICS include flexibility as to the jurisdiction and agency, adaptable organizational structure, capability to expand in a logical manner, and uniform elements in terminology, organization, and procedures. ICS in practice is illustrated both by the CANUSLAK exercise undertaken in August 1990 and a real incident that occurred several days after the exercise was finished. CANUSLAK involved the US Coast Guard and its Canadian and Michigan counterparts in a simulated incident in the St. Clair river. The real incident was the explosion of the gasoline-carrying tank vessel Jupiter in the Saginaw River. In both instances, ICS combined many organizations into one team with a single incident commander. The eight basic components of ICS are common terminology, modular organization, integrated communications, unified command structure, consolidated action plan, manageable span of control, designated incident facilities, and comprehensive resource management. ICS has been tailored to a wide range of applications and is not only used in major disasters but as a part of routine operations. 18 refs., 5 figs

  10. Component Test Facility (Comtest) Phase 1 Engineering For 760°C (1400°F) Advanced Ultrasupercritical (A-USC) Steam Generator Development

    Energy Technology Data Exchange (ETDEWEB)

    Weitzel, Paul [Babcock & Wilcox Power Generation Group, Inc., Barberton, OH (United States)

    2016-05-13

    The Babcock & Wilcox Company (B&W) performed a Pre-Front End Engineering Design (Pre-FEED) of an A-USC steam superheater for a proposed component test program achieving 760°C (1400°F) steam temperature. This would lead to follow-on work in a Phase 2 and Phase 3 that would involve detail design, manufacturing, construction and operation of the ComTest. Phase 1 results have provided the engineering data necessary for proceeding to the next phase of ComTest. The steam generator superheater would subsequently supply the steam to an A-USC prototype intermediate pressure steam turbine. The ComTest program is important in that it will place functioning A-USC components in operation and in coordinated boiler and turbine service. It is also important to introduce the power plant operation and maintenance personnel to the level of skills required and provide the first background experience with hands-on training. The project will provide a means to exercise the complete supply chain events required in order to practice and perfect the process for A-USC power plant design, supply, manufacture, construction, commissioning, operation and maintenance. Representative participants will then be able to transfer knowledge and recommendations to the industry. ComTest is conceived in the manner of using a separate standalone plant facility that will not jeopardize the host facility or suffer from conflicting requirements in the host plant’s mission that could sacrifice the nickel alloy components and not achieve the testing goals. ComTest will utilize smaller quantities of the expensive materials and reduce the risk in the first operational practice for A-USC technology in the United States. Components at suitable scale in ComTest provide more assurance before putting them into practice in the full size A-USC demonstration plant.

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

    International Nuclear Information System (INIS)

    Fujisaki, Kiyoshi; Suzuki, Hideaki; Fujita, Tomoo

    2008-03-01

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

  12. Report of the research results with University of Tokyo, Nuclear Engineering Research Laboratory's Facilities in fiscal 1991

    International Nuclear Information System (INIS)

    1992-01-01

    This publication summarizes the results of the joint utilization of the nuclear reactor 'Yayoi' and the electron beam accelerator in the Nuclear Engineering Research Laboratory, University of Tokyo, in fiscal year 1991. The Yayoi was operated smoothly throughout the year, and the number of research themes, for which the reactor Yayoi was jointly utilized, and the related themes reached 21 cases. After the linear accelerator was reconstructed as the twin linac, the joint utilization was resumed in October, 1989, and the number of research themes, was 15 cases. In this publication, in addition to the utilization reports, also the reports of 15 cases of Yayoi Study Meetings held in fiscal year 1991 are collected. (K.I.)

  13. Structural evaluation of spent nuclear fuel storage facilities under aircraft crash impact (2). Horizontal impact test onto reduced scale metal cask due to aircraft engine missile

    International Nuclear Information System (INIS)

    Namba, Kosuke; Shirai, Koji; Saegusa, Toshiari

    2009-01-01

    In this study, to confirm the sealing performance of a metal cask subjected to impact force due to possible commercial aircraft crash against a spent fuel storage facility, the horizontal impact test was carried out. In the test, an aircraft engine missile with a speed of 57.3 m/s attacked the reduced scale metal cask containing helium gas, which stands vertically. Then the leak rate and sliding displacement of the lid were measured. The leak rate increased rapidly and reached to 4.0 x 10 -6 Pa·m 3 /sec. After that, the leak rate decreased slowly and converged to 1.0x10 -6 Pa·m 3 /sec after 20 hours from the impact test. The leak rate of a full scale cask was evaluated using that of reduced scale cask obtained by the test. Then the leak rate of the full scale cask was 3.5x10 -5 Pa·m 3 /sec. This result showed that the sealing performance of the full scale metal cask would not be affected immediately by the horizontal impact of the aircraft engine with a speed of 57.3 m/s. (author)

  14. Conceptual Engineering Method for Attenuating He Ion Interactions on First Wall Components in the Fusion Test Facility (FTF) Employing a Low-Pressure Noble Gas

    International Nuclear Information System (INIS)

    Gentile, C.A.; Blanchard, W.R.; Kozub, T.; Priniski, C.; Zatz, I.; Obenschain, S.

    2009-01-01

    It has been shown that post detonation energetic helium ions can drastically reduce the useful life of the (dry) first wall of an IFE reactor due to the accumulation of implanted helium. For the purpose of attenuating energetic helium ions from interacting with first wall components in the Fusion Test Facility (FTF) target chamber, several concepts have been advanced. These include magnetic intervention (MI), deployment of a dynamically moving first wall, use of a sacrificial shroud, designing the target chamber large enough to mitigate the damage caused by He ions on the target chamber wall, and the use of a low pressure noble gas resident in the target chamber during pulse power operations. It is proposed that employing a low-pressure (∼ 1 torr equivalent) noble gas in the target chamber will thermalize energetic helium ions prior to interaction with the wall. The principle benefit of this concept is the simplicity of the design and the utilization of (modified) existing technologies for pumping and processing the noble ambient gas. Although the gas load in the system would be increased over other proposed methods, the use of a 'gas shield' may provide a cost effective method of greatly extending the first wall of the target chamber. An engineering study has been initiated to investigate conceptual engineering methods for implementing a viable gas shield strategy in the FTF.

  15. 77 FR 27743 - Notice of Public Meetings for the Draft Environmental Impact Statement/Overseas Environmental...

    Science.gov (United States)

    2012-05-11

    ... via the U.S. Postal Service to Naval Facilities Engineering Command, Southwest, Attention: HSTT EIS.... FOR FURTHER INFORMATION CONTACT: Naval Facilities Engineering Command, Southwest, Attention: HSTT EIS... available upon written request by contacting: Naval Facilities Engineering Command, Southwest, Attention...

  16. Thorium-U Recycle Facility (7930)

    Data.gov (United States)

    Federal Laboratory Consortium — The Thorium-U Recycle Facility (7930), along with the Transuranic Processing Facility (7920). comprise the Radiochemical Engineering Development Complex. 7930 is a...

  17. ASC Addresses Unit Commanders' Concerns through LBE and Reset Programs

    National Research Council Canada - National Science Library

    Young, Mark E

    2008-01-01

    .... Army Sustainment Command (ASC), part of the U.S. Army Materiel Command (AMC) team, is available to assist, identify, and resolve equipment and maintenance problems as well as materiel readiness issues for combatant commanders...

  18. Unity of Command in Afghanistan: A Forsaken Principle of War

    National Research Council Canada - National Science Library

    Hope, Ian

    2008-01-01

    ... in the evolution of military command for Afghanistan. It examines how there was an unprecedented departure from the principle of unity of command in Afghanistan in 2006, when Combined Forces Command-Afghanistan (CFC...

  19. Unity of Command in Afghanistan: A Forsaken Principle of War

    National Research Council Canada - National Science Library

    Hope, Ian

    2008-01-01

    ... of military command for Afghanistan. It examines the unprecedented departure from the principle of unity of command in Afghanistan in 2006, when Combined Forces Command-Afghanistan passed control of the ground fight to the International...

  20. Astronaut John Young in Command Module Simulator during Apollo Simulation

    Science.gov (United States)

    1968-01-01

    Astronaut John W. Young, command module pilot, inside the Command Module Simulator in bldg 5 during an Apollo Simulation. Astronauts Thomas P. Stafford, commander and Eugene A. Cernan, lunar module pilot are out of the view.

  1. Three astronauts inside Command Module Simulator during Apollo Simulation

    Science.gov (United States)

    1968-01-01

    Three astronauts inside the Command Module Simulator in bldg 5 during an Apollo Simulation. Left to right are Astronauts Thomas P. Stafford, commander; John W. Young, command module pilot; and Eugene A. Cernan, lunar module pilot.

  2. Analysis of Unit Process Cost for an Engineering-Scale Pyroprocess Facility Using a Process Costing Method in Korea

    Directory of Open Access Journals (Sweden)

    Sungki Kim

    2015-08-01

    Full Text Available Pyroprocessing, which is a dry recycling method, converts spent nuclear fuel into U (Uranium/TRU (TRansUranium metal ingots in a high-temperature molten salt phase. This paper provides the unit process cost of a pyroprocess facility that can process up to 10 tons of pyroprocessing product per year by utilizing the process costing method. Toward this end, the pyroprocess was classified into four kinds of unit processes: pretreatment, electrochemical reduction, electrorefining and electrowinning. The unit process cost was calculated by classifying the cost consumed at each process into raw material and conversion costs. The unit process costs of the pretreatment, electrochemical reduction, electrorefining and electrowinning were calculated as 195 US$/kgU-TRU, 310 US$/kgU-TRU, 215 US$/kgU-TRU and 231 US$/kgU-TRU, respectively. Finally the total pyroprocess cost was calculated as 951 US$/kgU-TRU. In addition, the cost driver for the raw material cost was identified as the cost for Li3PO4, needed for the LiCl-KCl purification process, and platinum as an anode electrode in the electrochemical reduction process.

  3. Literature review on medical incident command.

    Science.gov (United States)

    Rimstad, Rune; Braut, Geir Sverre

    2015-04-01

    It is not known what constitutes the optimal emergency management system, nor is there a consensus on how effectiveness and efficiency in emergency response should be measured or evaluated. Literature on the role and tasks of commanders in the prehospital emergency services in the setting of mass-casualty incidents has not been summarized and published. This comprehensive literature review addresses some of the needs for future research in emergency management through three research questions: (1) What are the basic assumptions underlying incident command systems (ICSs)? (2) What are the tasks of ambulance and medical commanders in the field? And (3) How can field commanders' performances be measured and assessed? A systematic literature search in MEDLINE, PubMed, PsycINFO, Embase, Cochrane Central Register of Controlled Trials, Cochrane Library, ISI Web of Science, Scopus, International Security & Counter Terrorism Reference Center, Current Controlled Trials, and PROSPERO covering January 1, 1990 through March 1, 2014 was conducted. Reference lists of included literature were hand searched. Included papers were analyzed using Framework synthesis. The literature search identified 6,049 unique records, of which, 76 articles and books where included in qualitative synthesis. Most ICSs are described commonly as hierarchical, bureaucratic, and based on military principles. These assumptions are contested strongly, as is the applicability of such systems. Linking of the chains of command in cooperating agencies is a basic difficulty. Incident command systems are flexible in the sense that the organization may be expanded as needed. Commanders may command by direction, by planning, or by influence. Commanders' tasks may be summarized as: conducting scene assessment, developing an action plan, distributing resources, monitoring operations, and making decisions. There is considerable variation between authors in nomenclature and what tasks are included or highlighted

  4. Linux Command Line and Shell Scripting Bible

    CERN Document Server

    Blum, Richard

    2011-01-01

    The authoritative guide to Linux command line and shell scripting?completely updated and revised [it's not a guide to Linux as a whole ? just to scripting] The Linux command line allows you to type specific Linux commands directly to the system so that you can easily manipulate files and query system resources, thereby permitting you to automate commonly used functions and even schedule those programs to run automatically. This new edition is packed with new and revised content, reflecting the many changes to new Linux versions, including coverage of alternative shells to the default bash shel

  5. The Linux command line a complete introduction

    CERN Document Server

    Shotts, William E

    2012-01-01

    You've experienced the shiny, point-and-click surface of your Linux computer—now dive below and explore its depths with the power of the command line. The Linux Command Line takes you from your very first terminal keystrokes to writing full programs in Bash, the most popular Linux shell. Along the way you'll learn the timeless skills handed down by generations of gray-bearded, mouse-shunning gurus: file navigation, environment configuration, command chaining, pattern matching with regular expressions, and more.

  6. Apollo experience report: Guidance and control systems. Engineering simulation program

    Science.gov (United States)

    Gilbert, D. W.

    1973-01-01

    The Apollo Program experience from early 1962 to July 1969 with respect to the engineering-simulation support and the problems encountered is summarized in this report. Engineering simulation in support of the Apollo guidance and control system is discussed in terms of design analysis and verification, certification of hardware in closed-loop operation, verification of hardware/software compatibility, and verification of both software and procedures for each mission. The magnitude, time, and cost of the engineering simulations are described with respect to hardware availability, NASA and contractor facilities (for verification of the command module, the lunar module, and the primary guidance, navigation, and control system), and scheduling and planning considerations. Recommendations are made regarding implementation of similar, large-scale simulations for future programs.

  7. Command and Control of Private Security Contractors: Are They a Viable Force Option for the Combatant Commander?

    National Research Council Canada - National Science Library

    Sherard, Scott H

    2008-01-01

    If a Combatant Commander (CCDR) or Joint Force Commander (JFC) were to take command of the approximately 25,000 security contractors in Iraq, a force of such size and capability would prove to be a valuable operational asset...

  8. Toward Unity of Command for Multinational Air Forces

    National Research Council Canada - National Science Library

    Asjes, David

    1998-01-01

    To assure unity of command in future multinational air operations, combatant commanders must embrace the necessity of multinational air forces, maximize the integration of allied officers within air...

  9. A Global Survey of Deep Underground Facilities; Examples of Geotechnical and Engineering Capabilities, Achievements, Challenges (Mines, Shafts, Tunnels, Boreholes, Sites and Underground Facilities for Nuclear Waste and Physics R&D): A Guide to Interactive Global Map Layers, Table Database, References and Notes

    International Nuclear Information System (INIS)

    Tynan, Mark C.; Russell, Glenn P.; Perry, Frank V.; Kelley, Richard E.; Champenois, Sean T.

    2017-01-01

    These associated tables, references, notes, and report present a synthesis of some notable geotechnical and engineering information used to create four interactive layer maps for selected: 1) deep mines and shafts; 2) existing, considered or planned radioactive waste management deep underground studies or disposal facilities 3) deep large diameter boreholes, and 4) physics underground laboratories and facilities from around the world. These data are intended to facilitate user access to basic information and references regarding “deep underground” facilities, history, activities, and plans. In general, the interactive maps and database provide each facility’s approximate site location, geology, and engineered features (e.g.: access, geometry, depth, diameter, year of operations, groundwater, lithology, host unit name and age, basin; operator, management organization, geographic data, nearby cultural features, other). Although the survey is not comprehensive, it is representative of many of the significant existing and historical underground facilities discussed in the literature addressing radioactive waste management and deep mined geologic disposal safety systems. The global survey is intended to support and to inform: 1) interested parties and decision makers; 2) radioactive waste disposal and siting option evaluations, and 3) safety case development applicable to any mined geologic disposal facility as a demonstration of historical and current engineering and geotechnical capabilities available for use in deep underground facility siting, planning, construction, operations and monitoring.

  10. A Global Survey of Deep Underground Facilities; Examples of Geotechnical and Engineering Capabilities, Achievements, Challenges (Mines, Shafts, Tunnels, Boreholes, Sites and Underground Facilities for Nuclear Waste and Physics R&D): A Guide to Interactive Global Map Layers, Table Database, References and Notes

    Energy Technology Data Exchange (ETDEWEB)

    Tynan, Mark C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Russell, Glenn P. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Perry, Frank V. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kelley, Richard E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Champenois, Sean T. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-06-13

    These associated tables, references, notes, and report present a synthesis of some notable geotechnical and engineering information used to create four interactive layer maps for selected: 1) deep mines and shafts; 2) existing, considered or planned radioactive waste management deep underground studies or disposal facilities 3) deep large diameter boreholes, and 4) physics underground laboratories and facilities from around the world. These data are intended to facilitate user access to basic information and references regarding “deep underground” facilities, history, activities, and plans. In general, the interactive maps and database provide each facility’s approximate site location, geology, and engineered features (e.g.: access, geometry, depth, diameter, year of operations, groundwater, lithology, host unit name and age, basin; operator, management organization, geographic data, nearby cultural features, other). Although the survey is not comprehensive, it is representative of many of the significant existing and historical underground facilities discussed in the literature addressing radioactive waste management and deep mined geologic disposal safety systems. The global survey is intended to support and to inform: 1) interested parties and decision makers; 2) radioactive waste disposal and siting option evaluations, and 3) safety case development applicable to any mined geologic disposal facility as a demonstration of historical and current engineering and geotechnical capabilities available for use in deep underground facility siting, planning, construction, operations and monitoring.

  11. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical

  12. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns

  13. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

  14. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 2, Chemical constituents

    Energy Technology Data Exchange (ETDEWEB)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report contains health and safety information relating to the chemicals that have been identified in the mixed waste streams at the Waste Treatment Facility at the Idaho National Engineering Laboratory. Information is summarized in two summary sections--one for health considerations and one for safety considerations. Detailed health and safety information is presented in material safety data sheets (MSDSs) for each chemical.

  15. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory. Part 1, Waste streams and treatment technologies

    Energy Technology Data Exchange (ETDEWEB)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

  16. Mixed and low-level waste treatment project: Appendix C, Health and safety criteria for the mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Neupauer, R.M.; Thurmond, S.M.

    1992-09-01

    This report describes health and safety concerns associated with the Mixed and Low-level Waste Treatment Facility at the Idaho National Engineering Laboratory. Various hazards are described such as fire, electrical, explosions, reactivity, temperature, and radiation hazards, as well as the potential for accidental spills, exposure to toxic materials, and other general safety concerns.

  17. New Global Missions for Strategic Command

    National Research Council Canada - National Science Library

    Graham, David

    2002-01-01

    .... The focus of this White Paper is on the external decisions that will be needed to provide the Command with a clear mission, and the authority, resources and organizational support necessary to perform the mission...

  18. U.S. Pacific Command > Leadership

    Science.gov (United States)

    USPACOM U.S. Pacific Command Search USPACOM: Search Search Search USPACOM: Search Home Leadership Directory Media Inquiries Home : Leadership Admiral Harry B. Harris, Jr., U.S. Navy Read the full biography

  19. The Road to a New Unified Command

    Science.gov (United States)

    2008-01-01

    The Directorate of Command, Control, Communications, and Computers (C4) Systems is chartered with information architecture (including in Africa...Friday afternoon cinema presentations where a documentary or feature film covering an African historic event was played, followed by dialogue

  20. Spacecraft command and control using expert systems

    Science.gov (United States)

    Norcross, Scott; Grieser, William H.

    1994-01-01

    This paper describes a product called the Intelligent Mission Toolkit (IMT), which was created to meet the changing demands of the spacecraft command and control market. IMT is a command and control system built upon an expert system. Its primary functions are to send commands to the spacecraft and process telemetry data received from the spacecraft. It also controls the ground equipment used to support the system, such as encryption gear, and telemetry front-end equipment. Add-on modules allow IMT to control antennas and antenna interface equipment. The design philosophy for IMT is to utilize available commercial products wherever possible. IMT utilizes Gensym's G2 Real-time Expert System as the core of the system. G2 is responsible for overall system control, spacecraft commanding control, and spacecraft telemetry analysis and display. Other commercial products incorporated into IMT include the SYBASE relational database management system and Loral Test and Integration Systems' System 500 for telemetry front-end processing.

  1. Unit Testing for Command and Control Systems

    Science.gov (United States)

    Alexander, Joshua

    2018-01-01

    Unit tests were created to evaluate the functionality of a Data Generation and Publication tool for a command and control system. These unit tests are developed to constantly evaluate the tool and ensure it functions properly as the command and control system grows in size and scope. Unit tests are a crucial part of testing any software project and are especially instrumental in the development of a command and control system. They save resources, time and costs associated with testing, and catch issues before they become increasingly difficult and costly. The unit tests produced for the Data Generation and Publication tool to be used in a command and control system assure the users and stakeholders of its functionality and offer assurances which are vital in the launching of spacecraft safely.

  2. Basic interrupt and command structures and applications

    International Nuclear Information System (INIS)

    Davies, R.C.

    1974-01-01

    Interrupt and command structures of a real-time system are described through specific examples. References to applications of a real-time system and programing development references are supplied. (auth)

  3. An Operational Commander's Guide to the Media

    National Research Council Canada - National Science Library

    McCartney, Michael

    2005-01-01

    ... of the embedded reporter . The Operational Commander is wise to review media relations and the successes and pitfalls of past conflicts, and to examine closely the results of Operation Iraqi Freedom so as to...

  4. Focused Logistics: Time for Functional Command

    National Research Council Canada - National Science Library

    Mintzlaff, Jeffrey G

    2005-01-01

    .... Military's distribution system -- the parts of the Department of Defense (DoD) that manage and execute the storage and movement of supplies to military customers -- consists of multiple entities and agencies made up of separate Services and commands...

  5. Distributed computing environment for Mine Warfare Command

    OpenAIRE

    Pritchard, Lane L.

    1993-01-01

    Approved for public release; distribution is unlimited. The Mine Warfare Command in Charleston, South Carolina has been converting its information systems architecture from a centralized mainframe based system to a decentralized network of personal computers over the past several years. This thesis analyzes the progress Of the evolution as of May of 1992. The building blocks of a distributed architecture are discussed in relation to the choices the Mine Warfare Command has made to date. Ar...

  6. Control of automated system with voice commands

    OpenAIRE

    Švara, Denis

    2012-01-01

    In smart houses contemporary achievements in the fields of automation, communications, security and artificial intelligence, increase comfort and improve the quality of user's lifes. For the purpose of this thesis we developed a system for managing a smart house with voice commands via smart phone. We focused at voice commands most. We want move from communication with fingers - touches, to a more natural, human relationship - speech. We developed the entire chain of communication, by which t...

  7. Defense or Diplomacy Geographic Combatant Commands

    Science.gov (United States)

    2011-06-01

    originally ruled by 1 Priest, Dana , The Mission: Waging War and Keeping Peace with America’s Military...events. US Central Command. Dana Priest describes General Zinni‟s experience as a GCC commander, wherein General Zinni found that in many ways...ignored altogether. Dr. James Forsyth and Lt Col Chance Saltzman make this argument in their Air and Space Power Journal article “Stay Out —Why

  8. An Advanced Commanding and Telemetry System

    Science.gov (United States)

    Hill, Maxwell G. G.

    The Loral Instrumentation System 500 configured as an Advanced Commanding and Telemetry System (ACTS) supports the acquisition of multiple telemetry downlink streams, and simultaneously supports multiple uplink command streams for today's satellite vehicles. By using industry and federal standards, the system is able to support, without relying on a host computer, a true distributed dataflow architecture that is complemented by state-of-the-art RISC-based workstations and file servers.

  9. Generalized plotting facility

    Energy Technology Data Exchange (ETDEWEB)

    Burris, R.D.; Gray, W.H.

    1978-01-01

    A command which causes the translation of any supported graphics file format to a format acceptable to any supported device was implemented on two linked DECsystem-10s. The processing of the command is divided into parsing and translating phases. In the parsing phase, information is extracted from the command and augmented by default data. The results of this phase are saved on disk, and the appropriate translating routine is invoked. Twenty-eight translating programs were implemented in this system. They support four different graphics file formats, including the DISSPLA and Calcomp formats, and seven different types of plotters, including Tektronix, Calcomp, and Versatec devices. Some of the plotters are devices linked to the DECsystem-10s, and some are driven by IBM System/360 computers linked via a communications network to the DECsystem-10s. The user of this facility can use any of the supported packages to create a file of graphics data, preview the file on an on-line scope, and, when satisfied, cause the same data to be plotted on a hard-copy device. All of the actions utilize a single simple command format. 2 figures.

  10. Baseline radionuclide concentrations in soils and vegetation around the proposed Weapons Engineering Tritium Facility and the Weapons Subsystems Laboratory at TA-16

    International Nuclear Information System (INIS)

    Fresquez, P.R.; Ennis, M.

    1995-09-01

    A preoperational environmental survey is required by the Department of Energy (DOE) for all federally funded research facilities that have the potential to cause adverse impacts on the environment. Therefore, in accordance with DOE Order 5400.1, an environmental survey was conducted over the proposed sites of the Weapons Engineering Tritium Facility (WETF) and the Weapons Subsystems Laboratory (WSL) at Los Alamos National Laboratory (LANL) at TA-16. Baseline concentrations of tritium ( 3 H), plutonium ( 238 Pu and 239 Pu) and total uranium were measured in soils, vegetation (pine needles and oak leaves) and ground litter. Tritium was also measured from air samples, while cesium ( 137 Cs) was measured in soils. The mean concentration of airborne tritiated water during 1987 was 3.9 pCi/m 3 . Although the mean annual concentration of 3 H in soil moisture at the 0--5 cm (2 in) soil depth was measured at 0.6 pCi/mL, a better background level, based on long-term regional data, was considered to be 2.6 pCi/mL. Mean values for 137 Cs, 218 Pu, 239 Pu, and total uranium in soils collected from the 0--5 cm depth were 1.08 pCi/g, 0.0014 pCi/g, 0.0325 pCi/g, and 4.01 microg/g, respectively. Ponderosa pine (Pinus ponderosa) needles contained higher values of 238 Pu, 239 Pu, and total uranium than did leaves collected from gambel's oak (Quercus gambelii). In contrast, leaves collected from gambel's oak contained higher levels of 137 Cs than what pine needles did

  11. 77 FR 68114 - Notice of Extension of Comment Period for the Draft Environmental Impact Statement for Military...

    Science.gov (United States)

    2012-11-15

    ... may be submitted in writing to Naval Facilities Engineering Command Northwest, Attention: Mrs. Amy... Facilities Engineering Command Northwest, 1101 Tautog Circle Suite 203, Silverdale, Washington, 98315-1101...

  12. Visualisation of Gasoline and Exhaust Gases Distribution in a 4-Valve Si Engine; Effects of Stratification on Combustion and Pollutants Visualisation de la répartition du carburant et des gaz brûlés dans un moteur à 4 soupapes à allumage commandé ; effet de la stratification sur la combustion et les polluants

    Directory of Open Access Journals (Sweden)

    Deschamps B.

    2006-12-01

    Full Text Available sAn indirect method to map the burned gases in SI engine has been developed. It is based on visualisation by Laser Induced Fluorescence of the unburned mixture seeded with biacetyl. Both internally and externally recirculated burned gases are monitored. This diagnostic is complementary to the LIF technique applied to measure the gasoline distribution. These LIF gasoline and burned gases measurements are applied in a 4-valve optical access SI engine for a large range of operating conditions. These include variations of both fuel injection and burned gas recirculation modes causing different types of stratification leading to very distinct heat release and exhaust emissions characteristics. Tumble level and spark location are also modified. The observation of the actual stratification in the engine forms a sound basis explanation of the engine performance. Parameters allowing an optimisation of NOx and HC levels can be inferred, and in particular the effectiveness of recirculation and fuel injection strategies. The conclusions are confirmed by measurements in a single engine cylinder conventional head with the same geometry. Une méthode indirecte pour cartographier les gaz brûlés dans un moteur à allumage commandé a été développée. Elle est fondée sur une visualisation à partir de la fluorescence induite par laser (LIF du mélange air-carburant non brûlé et ensemencé avec du biacétyl. Les gaz brûlés provenant à la fois des recirculations internes et externes sont observés. Ce type de diagnostic est complémentaire des techniques de LIF utilisées pour observer la distribution du carburant. Ces mesures de concentration sont réalisées dans un moteur à 4 soupapes avec accès optiques, pour une gamme étendue de conditions opératoires. Celles-ci comprennent des variations des modes d'injection du carburant et des modes de recirculation des gaz brûlés, provoquant ainsi différents types de stratifications qui correspondent

  13. Tactical Command and Control in the Combined Arms Battalion Task Force,

    Science.gov (United States)

    1988-03-08

    described as [ •follows. -.. Acquire information in the basic categories of mission, enemy, terrain, and troops available on a * continual basis through a...became the basic unit." 55 A study by Dr. Gabel describes a wide range of organizational and -*"" control structures which were ultimately used to...FreLelonolSystell each orce evel Commander * Procedures/acioa otrlS a / eCommunication $ 0’ Automation/// _. Other Notion’$ Command *e Facilities ’/ a nd Control

  14. Test Telemetry And Command System (TTACS)

    Science.gov (United States)

    Fogel, Alvin J.

    1994-01-01

    The Jet Propulsion Laboratory has developed a multimission Test Telemetry and Command System (TTACS) which provides a multimission telemetry and command data system in a spacecraft test environment. TTACS reuses, in the spacecraft test environment, components of the same data system used for flight operations; no new software is developed for the spacecraft test environment. Additionally, the TTACS is transportable to any spacecraft test site, including the launch site. The TTACS is currently operational in the Galileo spacecraft testbed; it is also being provided to support the Cassini and Mars Surveyor Program projects. Minimal personnel data system training is required in the transition from pre-launch spacecraft test to post-launch flight operations since test personnel are already familiar with the data system's operation. Additionally, data system components, e.g. data display, can be reused to support spacecraft software development; and the same data system components will again be reused during the spacecraft integration and system test phases. TTACS usage also results in early availability of spacecraft data to data system development and, as a result, early data system development feedback to spacecraft system developers. The TTACS consists of a multimission spacecraft support equipment interface and components of the multimission telemetry and command software adapted for a specific project. The TTACS interfaces to the spacecraft, e.g., Command Data System (CDS), support equipment. The TTACS telemetry interface to the CDS support equipment performs serial (RS-422)-to-ethernet conversion at rates between 1 bps and 1 mbps, telemetry data blocking and header generation, guaranteed data transmission to the telemetry data system, and graphical downlink routing summary and control. The TTACS command interface to the CDS support equipment is nominally a command file transferred in non-real-time via ethernet. The CDS support equipment is responsible for

  15. Agency Data on User Facilities

    Data.gov (United States)

    National Aeronautics and Space Administration — The purpose of the Aerospace Technical Facility Inventory is to facilitate the sharing of specialized capabilities within the aerospace research/engineering...

  16. Authorized Limits for the Release of a 25 Ton Locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly Facility, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Gwin, Jeremy; Frenette, Douglas

    2010-01-01

    This document contains process knowledge and radiological data and analysis to support approval for release of the 25-ton locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly (EMAD) Facility, located on the Nevada Test Site (NTS). The 25-ton locomotive is a small, one-of-a-kind locomotive used to move railcars in support of the Nuclear Engine for Rocket Vehicle Application project. This locomotive was identified as having significant historical value by the Nevada State Railroad Museum in Boulder City, Nevada, where it will be used as a display piece. A substantial effort to characterize the radiological conditions of the locomotive was undertaken by the NTS Management and Operations Contractor, National Security Technologies, LLC (NSTec). During this characterization process, seven small areas on the locomotive had contamination levels that exceeded the NTS release criteria (limits consistent with U.S. Department of Energy (DOE) Order DOE O 5400.5, 'Radiation Protection of the Public and the Environment'). The decision was made to perform radiological decontamination of these known accessible impacted areas to further the release process. On February 9, 2010, NSTec personnel completed decontamination of these seven areas to within the NTS release criteria. Although all accessible areas of the locomotive had been successfully decontaminated to within NTS release criteria, it was plausible that inaccessible areas of the locomotive (i.e., those areas on the locomotive where it was not possible to perform radiological surveys) could potentially have contamination above unrestricted release limits. To access the majority of these inaccessible areas, the locomotive would have to be disassembled. A complete disassembly for a full radiological survey could have permanently destroyed parts and would have ruined the historical value of the locomotive. Complete disassembly would also add an unreasonable financial burden for the

  17. Advanced Microscopy Facility

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: Provides a facility for high-resolution studies of complex biomolecular systems. The goal is an understanding of how to engineer biomolecules for various...

  18. Airborne Evaluation Facility

    Data.gov (United States)

    Federal Laboratory Consortium — AFRL's Airborne Evaluation Facility (AEF) utilizes Air Force Aero Club resources to conduct test and evaluation of a variety of equipment and concepts. Twin engine...

  19. 32 CFR 700.1054 - Command of a naval base.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 5 2010-07-01 2010-07-01 false Command of a naval base. 700.1054 Section 700.1054 National Defense Department of Defense (Continued) DEPARTMENT OF THE NAVY UNITED STATES NAVY... Command Detail to Duty § 700.1054 Command of a naval base. The officer detailed to command a naval base...

  20. Laboratory Testing of a MEMS Sensor System for In-Situ Monitoring of the Engineered Barrier in a Geological Disposal Facility

    Directory of Open Access Journals (Sweden)

    Wenbin Yang

    2017-05-01

    Full Text Available Geological disposal facilities for radioactive waste pose significant challenges for robust monitoring of environmental conditions within the engineered barriers that surround the waste canister. Temperatures are elevated, due to the presence of heat generating waste, relative humidity varies from 20% to 100%, and swelling pressures within the bentonite barrier can typically be 2–10 MPa. Here, we test the robustness of a bespoke design MEMS sensor-based monitoring system, which we encapsulate in polyurethane resin. We place the sensor within an oedometer cell and show that despite a rise in swelling pressure to 2 MPa, our relative humidity (RH measurements are unaffected. We then test the sensing system against a traditional RH sensor, using saturated bentonite with a range of RH values between 50% and 100%. Measurements differ, on average, by 2.87% RH, and are particularly far apart for values of RH greater than 98%. However, bespoke calibration of the MEMS sensing system using saturated solutions of known RH, reduces the measurement difference to an average of 1.97% RH, greatly increasing the accuracy for RH values close to 100%.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-06-01

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

  2. Chemical constituents in water from wells in the vicinity of the Naval Reactors Facility, Idaho National Engineering Laboratory, Idaho, 1990--91

    International Nuclear Information System (INIS)

    Bartholomay, R.C.; Knobel, L.L.; Tucker, B.J.

    1993-01-01

    The US Geological Survey, in response to a request from the US Department of Energy's Pittsburgh Naval Reactors Office, Idaho Branch Office, sampled 12 wells as part of a long-term project to monitor water quality of the Snake River Plain aquifer in the vicinity of the Naval Reactors Facility, Idaho National Engineering Laboratory, Idaho. Water samples were analyzed for manmade contaminants and naturally occurring constituents. Sixty samples were collected from eight groundwater monitoring wells and four production wells. Ten quality-assurance samples also were collected and analyzed. Most of the samples contained concentrations of total sodium and dissolved anions that exceeded reporting levels. The predominant category of nitrogen-bearing compounds was nitrite plus nitrate as nitrogen. Concentrations of total organic carbon ranged from less than 0.1 to 2.2 milligrams per liter. Total phenols in 52 of 69 samples ranged from 1 to 8 micrograms per liter. Extractable acid and base/neutral organic compounds were detected in water from 16 of 69 samples. Concentrations of dissolved gross alpha- and gross beta-particle radioactivity in all samples exceeded the reporting level. Radium-226 concentrations were greater than the reporting level in 63 of 68 samples

  3. Low-level waste drum staging building at Weapons Engineering Tritium Facility, TA-16, Los Alamos National Laboratory, Los Alamos, New Mexico. Environmental Assessment

    International Nuclear Information System (INIS)

    1994-08-01

    The proposed action is to place a 3 meter (m) by 4.5 m (10 ft x 15 ft) prefabricated storage building (transportainer) adjacent to the existing Weapons Engineering Tritium Facility (WETF) at Technical Area (TA-) 16, Los Alamos National Laboratory (LANL), and to use the building as a staging site for sealed 55 galllon drums of noncompactible waste contaminated with low levels of tritium (LLW). Up to eight drums of waste would be accumulated before the waste is moved by LANL Waste Management personnel to the existing on-site LLW disposal area at TA-54. The drum staging building would be placed on a bermed asphalt pad, near other existing accumulation structures for office trash and compactible LLW. The no-action alternative is to continue storing drums of LLW in the WETF laboratories where they occupy valuable work space, hamper movement of personnel and equipment, and require waste management personnel to enter those laboratories in order to remove filled drums. No new waste would be generated by implementing the proposed action; no changes or increases in WETF operations or waste production rate are anticipated as a result of staging drums of LLW outside the main laboratory building. The site for the LLW drum staging building would not impact any sensitive areas. Tritium emissions from the drums of LLW were included within the source term for normal operations at the WETF; the cumulative impacts would not be increased

  4. Mathematics in energy related research at the Tennessee Valley Authority, at Union Carbide's Oak Ridge Facilities, and at University of Tennessee College of Engineering. Final report

    International Nuclear Information System (INIS)

    Barett, L.K.

    1979-05-01

    This report contains a description of the work performed under the Department of Energy Contract No. ER078-S-05-5944 to the University of Tennessee. The major objective of this contract was to survey and to classify a selection of the mathematics used in energy-related activities at the Tennessee Valley Authority (TVA), at Union Carbide's Oak Ridge Facilities (UCORF), and at the University of Tennessee College of Engineering (UTCE). Eighty-seven projects were identified at these organizations in which mathematics plays a significant modeling or problem-solving role. Uniform abstracts of these projects are included in this report, as well as abstracts of twenty-seven presentations by TVA and UCORF personnel on the topic of mathematics in energy research, at the 1978 Fall SIAM meeting. Classifications of these one hundred and fourteen abstracts are given in terms of the energy area or function involved and in terms of the mathematical disciplines used in the activity. Only a selection of the mathematical activity at the TVA, UCORF, and UTCE involved in energy research was obtained due to time and budget constraints. However, it was possible to make some important observations and recommendations based upon these sample data, and these are included in the summary of this report

  5. STS-37 Commander Nagel in commanders seat on OV-104's flight deck

    Science.gov (United States)

    1991-01-01

    STS-37 Commander Steven R. Nagel, wearing launch and entry suit (LES), sits at commanders station on the forward flight deck of Atlantis, Orbiter Vehicle (OV) 104. Surrounding Nagel are the seat headrest, control panels, checklists, forward flight deck windows, and three drinking water containers with straws attached to forward panel F2.

  6. Command and Data Handling Branch Internship

    Science.gov (United States)

    Billings, Rachel Mae

    2016-01-01

    planes, layer stacks, and other specified design rules such as plane clearance and hole size. Multiple consultation sessions were held with Hester Yim, the technical discipline lead for the Command and Data Handling Branch, and Christy Herring, the lead PCB layout designer in the Electronic Design and Manufacturing Branch in order to ensure proper configuration. At themoment, the PCB is awaiting revision by the latter-mentioned branch. Afterwards, the board will begin to undergo the manufacturing and testing process.Throughout the internship at Johnson Space Center, I gained several technical and professional skills. I gained proficiency in Altium Designer and experience using subversion clients, as well as knowledge in PSpice with OrCAD and battery design for spaceflight from on-site. I also gained networking, organization, and communication skills throughout meetings with coworkers and other interns. This internship at Johnson Space Center has impacted my future aspirations by further inspiring me to follow a career path into space rated engineering technology and human spaceflight applications. After graduation, I plan to attend graduate school for a master's or doctorate degree in electrical or computer engineering.

  7. A Remote WIRELESS Facility

    Directory of Open Access Journals (Sweden)

    Kees Uiterwijk

    2007-10-01

    Full Text Available Continuing need for available distance learning facilities has led to the development of a remote lab facility focusing on wireless technology. In the field of engineering there is a student need of gaining experience in set-up, monitoring and maintenance of 802.11A/B/G based wireless LAN environments.

  8. Reticulospinal Systems for Tuning Motor Commands

    Directory of Open Access Journals (Sweden)

    Robert M. Brownstone

    2018-04-01

    Full Text Available The pontomedullary reticular formation (RF is a key site responsible for integrating descending instructions to execute particular movements. The indiscrete nature of this region has led not only to some inconsistencies in nomenclature, but also to difficulties in understanding its role in the control of movement. In this review article, we first discuss nomenclature of the RF, and then examine the reticulospinal motor command system through evolution. These command neurons have direct monosynaptic connections with spinal interneurons and motoneurons. We next review their roles in postural adjustments, walking and sleep atonia, discussing their roles in movement activation or inhibition. We propose that knowledge of the internal organization of the RF is necessary to understand how the nervous system tunes motor commands, and that this knowledge will underlie strategies for motor functional recovery following neurological injuries or diseases.

  9. STS-93 Commander Collins poses in front of Columbia

    Science.gov (United States)

    1999-01-01

    STS-93 Commander Eileen Collins poses in front of the Space Shuttle orbiter Columbia following her textbook landing on runway 33 at the Shuttle Landing Facility. Main gear touchdown occurred at 11:20:35 p.m. EDT on July 27. On this mission, Collins became the first woman to serve as a Shuttle commander. Also on board were her fellow STS-93 crew members: Pilot Jeffrey S. Ashby and Mission Specialists Stephen A. Hawley (Ph.D.), Catherine G. Coleman (Ph.D.) and Michel Tognini of France, with the Centre National d'Etudes Spatiales (CNES). The mission's primary objective was to deploy the Chandra X-ray Observatory, which will allow scientists from around the world to study some of the most distant, powerful and dynamic objects in the universe. This was the 95th flight in the Space Shuttle program and the 26th for Columbia. The landing was the 19th consecutive Shuttle landing in Florida and the 12th night landing in Shuttle program history.

  10. Linux command line and shell scripting bible

    CERN Document Server

    Blum, Richard

    2014-01-01

    Talk directly to your system for a faster workflow with automation capability Linux Command Line and Shell Scripting Bible is your essential Linux guide. With detailed instruction and abundant examples, this book teaches you how to bypass the graphical interface and communicate directly with your computer, saving time and expanding capability. This third edition incorporates thirty pages of new functional examples that are fully updated to align with the latest Linux features. Beginning with command line fundamentals, the book moves into shell scripting and shows you the practical application

  11. Communication for command and control systems

    CERN Document Server

    Morris, D J

    1983-01-01

    Communication for Command and Control Systems provides a thorough exposition of the basic theoretical and practical features involved in the design of communication networks for command and control systems. This book focuses primarily on the practical side of computer-controlled communication. This text concentrates on the communication sides of the subject by surveying the means of transferring data between the various processing points and by appraising their potential advantages and possible defects in implementation. In this respect, this book should prove useful for the practicing enginee

  12. Ice Engineering Research Area

    Data.gov (United States)

    Federal Laboratory Consortium — Refrigerated Physical Modeling of Waterways in a Controlled EnvironmentThe Research Area in the Ice Engineering Facility at the Cold Regions Research and Engineering...

  13. Engineering Sciences Experimental Facilities (ESEF)

    Data.gov (United States)

    Federal Laboratory Consortium — The ESEF complex contains several independent laboratories for experiments and advanced diagnostics in the fields of thermodynamics, heat transfer, fluid mechanics,...

  14. Safety analysis report for the Mixed Waste Storage Facility and portable storage units at the Idaho National Engineering Laboratory. Revision 4

    International Nuclear Information System (INIS)

    Peatross, R.

    1997-01-01

    This revision contains Section 2 only which gives a description of the Mixed Waste Storage Facility (MWSF) and its operations. Described are the facility location, services and utilities, process description and operation, and safety support systems. The MWSF serves as a storage and repackaging facility for low-level mixed waste

  15. A Novel wave-form command shaper for overhead cranes

    Directory of Open Access Journals (Sweden)

    KHALED ALHAZZA

    2013-12-01

    Full Text Available In this work, a novel command shaping control strategy for oscillation reduction of simple harmonic oscillators is proposed, and validated experimentally. A wave-form acceleration command shaper is derived analytically. The performance of the proposed shaper is simulated numerically, and validated experimentally on a scaled model of an overhead crane. Amplitude modulation is used to enhance the shaper performance, which results in a modulated wave-form command shaper. It is determined that the proposed wave-form and modulated wave-form command shaper profiles are capable of eliminating travel and residual oscillations. Furthermore, unlike traditional impulse and step command shapers, the proposed command shaper has piecewise smoother acceleration, velocity, and displacement profiles. Experimental results using continuous and discrete commands are presented. Experiments with discrete commands involved embedding a saturation model-based feedback in the algorithm of the command shaper.

  16. Command History. 1968. Volume 1. Sanitized.

    Science.gov (United States)

    1968-01-01

    battalions. Additionally, a diary captured on 19 December, Z1 kilometers southwest of Song Cau, revealed that on 19 November the author. a cadre member...the 306th and 312th ( AYA 308th) Bns. This reorga- nization was an apparent attempt by the headquarters of MR 3 to tighten its command and con- trol. (C

  17. Commandants' Managerial Capacity and Workers Productivity in ...

    African Journals Online (AJOL)

    The purpose of this study is to evaluate the commandant's managerial capacity as if relates to workers productivity with a view to determining whether their calling to the education terrain has been justified and to correct certain areas in need of improvement in the Nigeria Police Education set up. In doing this, the study took ...

  18. Command and Control in Littoral Operations

    Science.gov (United States)

    2016-05-13

    at the graphics on the wall displaying the position of the various forces under his command. Only a few of his 14 ships were in formation with him...Mainz, 2d MEB Lead Planner (November 11, 2014). Moskowitz, Michael, and Nolan Noble. Dawn Blitz 2015- Observations and Analysis. Exercise

  19. RELATIONSHIP BETWEEN LINGUISTIC UNITS AND MOTOR COMMANDS.

    Science.gov (United States)

    FROMKIN, VICTORIA A.

    ASSUMING THAT SPEECH IS THE RESULT OF A NUMBER OF DISCRETE NEUROMUSCULAR EVENTS AND THAT THE BRAIN CAN STORE ONLY A LIMITED NUMBER OF MOTOR COMMANDS WITH WHICH TO CONTROL THESE EVENTS, THE RESEARCH REPORTED IN THIS PAPER WAS DIRECTED TO A DETERMINATION OF THE SIZE AND NATURE OF THE STORED ITEMS AND AN EXPLANATION OF HOW SPEAKERS ENCODE A SEQUENCE…

  20. APOLLO 11 COMMANDER NEIL ARMSTRONG IN SIMULATOR

    Science.gov (United States)

    1969-01-01

    Apollo 11 commander Neil Armstrong is going through flight training in the lunar module simulator situated in the flight crew training building at KSC. Armstrong will pilot the lunar module to a moon landing on July 20, following launch from KSC on July 16.

  1. Command-And-Control or Taxation?

    DEFF Research Database (Denmark)

    Oh, Christina; Svendsen, Gert Tinggaard

    2015-01-01

    an ineffective command-and-control (CAC) tool, whereas Denmark has chosen the effective tool of taxation. One main explanation for this variation in policy choice is the variation in institutional setups, namely the corporatist route in Denmark versus the pluralistic route in California....

  2. Spaceport Command and Control System Automated Verification Software Development

    Science.gov (United States)

    Backus, Michael W.

    2017-01-01

    For as long as we have walked the Earth, humans have always been explorers. We have visited our nearest celestial body and sent Voyager 1 beyond our solar system1 out into interstellar space. Now it is finally time for us to step beyond our home and onto another planet. The Spaceport Command and Control System (SCCS) is being developed along with the Space Launch System (SLS) to take us on a journey further than ever attempted. Within SCCS are separate subsystems and system level software, each of which have to be tested and verified. Testing is a long and tedious process, so automating it will be much more efficient and also helps to remove the possibility of human error from mission operations. I was part of a team of interns and full-time engineers who automated tests for the requirements on SCCS, and with that was able to help verify that the software systems are performing as expected.

  3. Geoenvironmental engineering

    International Nuclear Information System (INIS)

    Shin, Eun Cheol; Park, Jeong Jun

    2009-08-01

    This book deals with definition of soil and scope of clean-up of soil, trend of geoenvironmental engineering at home and foreign countries, main concern of geoenvironmental engineering in domestic and abroad, design and building of landfills such as summary, trend of landfill policy in Korea, post management of landfill facilities, stabilizing and stability of landfill, research method and soil pollution source, restoration technology of soil pollution like restoration technique of oil pollution with thermal processing.

  4. LEGS data acquisition facility

    International Nuclear Information System (INIS)

    LeVine, M.J.

    1985-01-01

    The data acquisition facility for the LEGS medium energy photonuclear beam line is composed of an auxiliary crate controller (ACC) acting as a front-end processor, loosely coupled to a time-sharing host computer based on a UNIX-like environment. The ACC services all real-time demands in the CAMAC crate: it responds to LAMs generated by data acquisition modules, to keyboard commands, and it refreshes the graphics display at frequent intervals. The host processor is needed only for printing histograms and recording event buffers on magnetic tape. The host also provides the environment for software development. The CAMAC crate is interfaced by a VERSAbus CAMAC branch driver

  5. Hot cell verification facility update

    International Nuclear Information System (INIS)

    Titzler, P.A.; Moffett, S.D.; Lerch, R.E.

    1985-01-01

    The Hot Cell Verification Facility (HCVF) provides a prototypic hot cell mockup to check equipment for functional and remote operation, and provides actual hands-on training for operators. The facility arrangement is flexible and assists in solving potential problems in a nonradioactive environment. HCVF has been in operation for six years, and the facility is a part of the Hanford Engineering Development Laboratory

  6. Intelligent Tutoring System for Teaching Battlefield Command Reasoning Skills

    National Research Council Canada - National Science Library

    Domeshek, Eric

    2002-01-01

    .... Achieving expert levels of proficiency in high-level command reasoning skills-whether for battlefield commanders or for executives in industry-requires extensive practice, coaching, and feedback...

  7. 'The Danger of Divided Command': British civil and military disputes ...

    African Journals Online (AJOL)

    Commander-in-Chief of the Indian Army, Lord Kitchener, which culminated in Curzon's ... and the officers commanding forces would have no doubt as to their .... but assuming financial responsibility for its own defence would have been ...

  8. Maritime Coalitions: When is Unity of Command Required

    National Research Council Canada - National Science Library

    Gahlinger, Gregory J

    2007-01-01

    .... The concepts of Unity of Command, Unity of Effort and Parallel, Lead Nation, or Integrated coalition command structures are viable across a broad spectrum of maritime coalition operations but do have...

  9. GPS and the Joint Force Commander: Critical Asset, Critical Vulnerability

    National Research Council Canada - National Science Library

    McPherson, Michael

    2001-01-01

    Joint Force Commanders (JFCs) have become over reliant on military and commercial satellite systems for intelligence gathering and dissemination, weather, command, control, communications, and navigation/guidance functions, to name a few...

  10. U.S. Africa Command: Shaping Africa for the Future

    National Research Council Canada - National Science Library

    Sholley, Hans

    2006-01-01

    .... It is argued the current Unified Command Plan is ill designed to address the complexities of the continent of Africa and that a proposed United States Africa Command would be better positioned...

  11. The Warfighting Capacity of Air Combat Command's Numbered Air Forces

    National Research Council Canada - National Science Library

    Hanser, Lawrence

    2000-01-01

    ...) of the Air Combat Command (ACC), General Richard E. Hawley, the ACC Commander, asked if RAND could offer an analysis of the number of NAFs that were needed by ACC to meet warfighting requirements...

  12. Design of a hybrid command and control mobile botnet

    CSIR Research Space (South Africa)

    Pieterse, H

    2013-05-01

    Full Text Available and control mobile botnet. The hybrid design explores the efficiency of multiple command and control channels against the following objectives: no single point of failure within the topology, low cost for command dissemination, limited network activities...

  13. Incorrect Responses to Locative Commands: A Case Study.

    Science.gov (United States)

    Duchan, Judith; Siegel, Leo

    1979-01-01

    A six-year-old with a language problem responded consistently to 100 locative commands by putting objects in containers and on flat surfaces regardless of the preposition or order of the nouns in the commands. (Author/CL)

  14. Simultaneously firing two cylinders of an even firing camless engine

    Science.gov (United States)

    Brennan, Daniel G

    2014-03-11

    A valve control system includes an engine speed control module that determines an engine speed and a desired engine stop position. A piston position module determines a desired stopping position of a first piston based on the desired engine stop position. A valve control module receives the desired stopping position, commands a set of valves to close at the desired stopping position if the engine speed is less than a predetermined shutdown threshold, and commands the set of valves to reduce the engine speed if the engine speed is greater than the predetermined shutdown threshold.

  15. Soviet command and control in a historical context

    OpenAIRE

    Kern, Jeffrey A.

    1981-01-01

    Approved for public release; distribution is unlimited An examination is made of the historical antecedents of present day command and control doctrine in the Soviet Union. The continuity of principal characteristics is demonstrated. The ideological determinants shaping the command and control system are first developed. These include centralism, collective decision-making, unity of command, and redundancy. Practical consequences of these are explored. The functioning of Soviet command...

  16. A Phenomenological Heat Transfer Model of SI Engines – Application to the Simulation of a Full-Hybrid Vehicle Un modèle phénoménologique de transfert thermique au sein de moteurs à allumage commandé — Application à la simulation d’un véhicule full-hybride

    Directory of Open Access Journals (Sweden)

    Dubouil R.

    2013-02-01

    Full Text Available A hybrid thermal-electric vehicle allows some significant fuel economy due to its peculiar use of the Internal Combustion Engine (ICE that runs with better efficiency. However, this propulsion system impacts its thermal behaviour, especially during its warm-up after a cold start. The ICE can indeed be shut down when the vehicle is stopped (Stop&Start system and during full-electric propulsion mode (allowed at light speed and load if the battery state of charge is high enough resulting in a lack of heat source and a slow down of the warm-up. Moreover, the use of the ICE at higher loads while charging the batteries provides an increase of the heating power generated by the combustion. Control strategies in a hybrid vehicle (energy repartition between the two propulsions: thermal and electric have a significant effect on its final consumption. Therefore, the simulation of hybrid vehicles is then useful to evaluate the efficiency of these strategies. However, the consideration of the warm-up of the ICE in such a propulsion system was done in only few published studies. A simulation tool using the Amesim software has been developed in order to simulate the warm-up of an ICE used in a hybrid parallel propulsion system. The corresponding model is developed in order to take into account the thermal phenomena occurring between the different ICE components. Thus, a thermodynamic model is coupled with a thermal model of the metallic parts and the different fluid loops (water and oil. Their mean temperature dependence with different parameters like speed, the load, the cylinder geometry and the spark advance, is studied with the aim at reducing fuel consumption. The thermal model of the engine is finally integrated in a simulation of the whole vehicle. The thermal behaviour of a parallel electric full-hybrid vehicle using a spark ignition engine is then presented using this simulation tool. The simulation results show the impact of the peculiar use of the

  17. 32 CFR 700.1056 - Command of a ship.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 5 2010-07-01 2010-07-01 false Command of a ship. 700.1056 Section 700.1056 National Defense Department of Defense (Continued) DEPARTMENT OF THE NAVY UNITED STATES NAVY REGULATIONS AND OFFICIAL RECORDS UNITED STATES NAVY REGULATIONS AND OFFICIAL RECORDS Precedence, Authority and Command Detail to Duty § 700.1056 Command of a...

  18. U.S. Pacific Command > About USPACOM > History

    Science.gov (United States)

    USPACOM U.S. Pacific Command Search USPACOM: Search Search Search USPACOM: Search Home Leadership People's Republic of China, the Democratic People's Republic of Korea, Mongolia, and the Republic of its surrounding waters under the leadership of one commander, providing a unity of command absent from

  19. Design of a hybrid command and control mobile botnet: Presentation

    CSIR Research Space (South Africa)

    Pieterse, H

    2013-03-01

    Full Text Available smartphones controlled by a botmaster through a command and control network to serve a malicious purpose. This study presents the design of a hybrid command and control mobile botnet. It describes the propagation vectors, command and control channels...

  20. Applied Knowledge Management to Mitigate Cognitive Load in Network-Enabled Mission Command

    Science.gov (United States)

    2017-11-22

    ARL-TN-0859 ● NOV 2017 US Army Research Laboratory Applied Knowledge Management to Mitigate Cognitive Load in Network-Enabled...Applied Knowledge Management to Mitigate Cognitive Load in Network-Enabled Mission Command by John K Hawley Human Research and Engineering...REPORT TYPE Technical Note 3. DATES COVERED (From - To) 1 May 2016–20 April 2017 4. TITLE AND SUBTITLE Applied Knowledge Management to Mitigate

  1. System for Relay Protection Command Transmission by High-Voltage Lines

    Directory of Open Access Journals (Sweden)

    D. A. Yenkov

    2009-01-01

    Full Text Available Development of a system for relay protection command transmission by high-voltage lines is shown in the paper. The paper describes an architecture of the system, main principles of its operation, engineering aspects of the development that is accomplishment of technical requirements, solution of trades-off. Justification of the selected design and an algorithm of the reliable detection of relay protection signals are given in the paper.

  2. Review of Ground Systems Development and Operations (GSDO) Tools for Verifying Command and Control Software

    Science.gov (United States)

    Aguilar, Michael L.; Bonanne, Kevin H.; Favretto, Jeffrey A.; Jackson, Maddalena M.; Jones, Stephanie L.; Mackey, Ryan M.; Sarrel, Marc A.; Simpson, Kimberly A.

    2014-01-01

    The Exploration Systems Development (ESD) Standing Review Board (SRB) requested the NASA Engineering and Safety Center (NESC) conduct an independent review of the plan developed by Ground Systems Development and Operations (GSDO) for identifying models and emulators to create a tool(s) to verify their command and control software. The NESC was requested to identify any issues or weaknesses in the GSDO plan. This document contains the outcome of the NESC review.

  3. Operational Maneuver from the Sea and Amphibious Command Relationships: Is It time for a Joint Force Amphibious Component Commander?

    National Research Council Canada - National Science Library

    Bennett, Michael

    2004-01-01

    .... In a joint community that is becoming increasingly dependant on the use of functional component commanders in the execution of major operations, the need for a Joint Force Amphibious Component Commander (JFAMCC...

  4. Commanders’ Perception of Risk: Enabling Boldness

    Science.gov (United States)

    2008-04-01

    individual. Soldiers are trained over time to employ their weapon systems tinder a variety of conditions in, realistic simulations and scenarios, thus...from ground combat the specialty is, where th~ leader provides the same support in combat that he would in garrison with no direct relationship to an...34 safety paperwork and activities. 73 Senior commanders must aggressively search for means to communicate their intent and the relationship between

  5. Command and Control for Distributed Lethality

    Science.gov (United States)

    2017-06-01

    extended communications between the AFP CDR and the CCDR are required. As shown in Figure 20, the principle command relationships are between...frequency (RF) communications are limited by maximum antenna height of each surface platform without an airborne relay. LOS is estimated with an online ...documents the interconnections and relationship of information flow and the system requirements for maintaining the interconnection links during a

  6. Jimmy Doolittle: The Commander behind the Legend

    Science.gov (United States)

    2015-02-01

    was 35 percent and that, although luxury items were cheap, food and other necessities were expensive. He speculated that everyone in Germany...British Spitfire groups, one troop-carrier group, one light-bombardment group, and three medium-bombardment groups.123 He later observed, “I was a brand ...a very popular commander, Ira Eaker, was perhaps the first. Eaker had served in the Eighth since its incep- tion and led its first independent attack

  7. Tools virtualization for command and control systems

    Science.gov (United States)

    Piszczek, Marek; Maciejewski, Marcin; Pomianek, Mateusz; Szustakowski, Mieczysław

    2017-10-01

    Information management is an inseparable part of the command process. The result is that the person making decisions at the command post interacts with data providing devices in various ways. Tools virtualization process can introduce a number of significant modifications in the design of solutions for management and command. The general idea involves replacing physical devices user interface with their digital representation (so-called Virtual instruments). A more advanced level of the systems "digitalization" is to use the mixed reality environments. In solutions using Augmented reality (AR) customized HMI is displayed to the operator when he approaches to each device. Identification of device is done by image recognition of photo codes. Visualization is achieved by (optical) see-through head mounted display (HMD). Control can be done for example by means of a handheld touch panel. Using the immersive virtual environment, the command center can be digitally reconstructed. Workstation requires only VR system (HMD) and access to information network. Operator can interact with devices in such a way as it would perform in real world (for example with the virtual hands). Because of their procedures (an analysis of central vision, eye tracking) MR systems offers another useful feature of reducing requirements for system data throughput. Due to the fact that at the moment we focus on the single device. Experiments carried out using Moverio BT-200 and SteamVR systems and the results of experimental application testing clearly indicate the ability to create a fully functional information system with the use of mixed reality technology.

  8. Auftragstaktik: The Basis for Modern Military Command?

    Science.gov (United States)

    2012-12-06

    Pauli’s Nachf, 1892. Showalter, Dennis. The Wars of German Unification. London: Hodder Education , 2004. Simpkin, Richard. Race to the Swift. London...to the bourgeois class again, making education , not social position, the deciding factor for obtaining a commission.15 The army created a system of...only reflected the increased education and capability of the new officer corps, but also the reality of commanding an army in the Napoleonic era

  9. Mission Command In A Communications Denied Environment

    Science.gov (United States)

    2017-02-16

    the mutual trust between the echelons.8 In the United States armed forces, the Joint Chiefs have understood the value of...without being over controlling or micromanaging.12 During the execution phase the commander is the free to choose his position on the battlefield to... the Air Force Association Convention, National Harbor, MD, September 16, 2009, accessed at http://www.defenselink.mil/ speeches

  10. Naval Meteorology and Oceanography Command exhibit entrance

    Science.gov (United States)

    2000-01-01

    StenniSphere at NASA's John C. Stennis Space Center in Hancock County, Miss., invites visitors to discover why America comes to Stennis Space Center before going into space. Designed to entertain while educating, StenniSphere includes informative displays and exhibits from NASA and other agencies located at Stennis, such as this one from the Naval Meteorology and Oceanography Command. Visitors can 'travel' three-dimensionally under the sea and check on the weather back home in the Weather Center.

  11. Naval Meteorology and Oceanography Command exhibit

    Science.gov (United States)

    2000-01-01

    Designed to entertain while educating, StenniSphere at the John C. Stennis Space Center in Hancock County, Miss., includes informative displays and exhibits from NASA and other agencies located at Stennis, such as this one from the Naval Meteorology and Oceanography Command. Visitors can 'travel' three-dimensionally under the sea and check on the weather back home in the Weather Center. StenniSphere is open free of charge from 9 a.m. to 5 p.m. daily.

  12. Contribution to the automatic command in robotics - Application to the command by microprocessors of the articulated systems; Contribution a la commande automatique en robotique. Application a la commande par microprocesseurs des manipulateurs articules

    Energy Technology Data Exchange (ETDEWEB)

    Al Mouhamed, Mayez

    1982-01-29

    The first part of the present paper deals with the main methods of changing the coordinates for a general articulated system. After a definition of the coordinates changing, we propose a coordination system designed for easy programming of the movements. Its characteristic is to permit the action anywhere on the manipulated object. The second part deals with the force regulation problem. For this purpose we have developed a general force sensor. The informations delivered by the sensor are used by force regulators which are intended for the automatic assembly of subsystems. In the third part the dynamic problem of the articulated systems is exposed. We present a new method which allows to determine dynamic parameters from appropriate motions of the robot. These parameters are then used to implement the dynamic control. Several applications, using the powerful microprocessor INTEL 8086 and its arithmetic coprocessor 8087, are presented, in order to demonstrate the performances gained. (author) [French] Dans la premiere partie de ce memoire, nous exposons les principales methodes de changement de coordonnees pour un systeme articule general. Apres une definition adequate de ce dernier, nous proposons un systeme de coordination permettant une programmation facile des mouvements. Sa caracteristique est de prendre comme centre d'action un point quelconque de l'objet manipule. Dans la deuxieme partie, nous etudions la regulation en effort. Pour cela nous avons developpe un capteur de forces general. Les informations que delivre ce dernier sont utilisees par des regulateurs d'effort adaptes au contexte de l'assemblage automatique des pieces. Dans la troisieme partie, nous exposons une nouvelle methode de commande dynamique des systemes articules. Nous obtenons des parametres dynamiques du robot a partir de mouvements appropries. Ces derniers sont ensuite utilises dans l'elaboration des commandes. Des applications utilisant le microprocesseur INTEL 8086 avec son

  13. Command Interface ASIC - Analog Interface ASIC Chip Set

    Science.gov (United States)

    Ruiz, Baldes; Jaffe, Burton; Burke, Gary; Lung, Gerald; Pixler, Gregory; Plummer, Joe; Katanyoutanant,, Sunant; Whitaker, William

    2003-01-01

    A command interface application-specific integrated circuit (ASIC) and an analog interface ASIC have been developed as a chip set for remote actuation and monitoring of a collection of switches, which can be used to control generic loads, pyrotechnic devices, and valves in a high-radiation environment. The command interface ASIC (CIA) can be used alone or in combination with the analog interface ASIC (AIA). Designed primarily for incorporation into spacecraft control systems, they are also suitable for use in high-radiation terrestrial environments (e.g., in nuclear power plants and facilities that process radioactive materials). The primary role of the CIA within a spacecraft or other power system is to provide a reconfigurable means of regulating the power bus, actuating all valves, firing all pyrotechnic devices, and controlling the switching of power to all switchable loads. The CIA is a mixed-signal (analog and digital) ASIC that includes an embedded microcontroller with supporting fault-tolerant switch control and monitoring circuitry that is capable of connecting to a redundant set of interintegrated circuit (I(sup 2)C) buses. Commands and telemetry requests are communicated to the CIA. Adherence to the I(sup 2)C bus standard helps to reduce development costs by facilitating the use of previously developed, commercially available components. The AIA is a mixed-signal ASIC that includes the analog circuitry needed to connect the CIA to a custom higher powered version of the I(sup 2)C bus. The higher-powered version is designed to enable operation with bus cables longer than those contemplated in the I(sup 2)C standard. If there are multiple higher-power I(sup 2)C-like buses, then there must an AIA between the CIA and each such bus. The AIA includes two identical interface blocks: one for the side-A I(sup 2)C clock and data buses and the other for the side B buses. All the AIAs on each side are powered from a common power converter module (PCM). Sides A and B

  14. AMO EXPRESS: A Command and Control Experiment for Crew Autonomy

    Science.gov (United States)

    Stetson, Howard K.; Frank, Jeremy; Cornelius, Randy; Haddock, Angie; Wang, Lui; Garner, Larry

    2015-01-01

    NASA is investigating a range of future human spaceflight missions, including both Mars-distance and Near Earth Object (NEO) targets. Of significant importance for these missions is the balance between crew autonomy and vehicle automation. As distance from Earth results in increasing communication delays, future crews need both the capability and authority to independently make decisions. However, small crews cannot take on all functions performed by ground today, and so vehicles must be more automated to reduce the crew workload for such missions. NASA's Advanced Exploration Systems Program funded Autonomous Mission Operations (AMO) project conducted an autonomous command and control demonstration of intelligent procedures to automatically initialize a rack onboard the International Space Station (ISS) with power and thermal interfaces, and involving core and payload command and telemetry processing, without support from ground controllers. This autonomous operations capability is enabling in scenarios such as a crew medical emergency, and representative of other spacecraft autonomy challenges. The experiment was conducted using the Expedite the Processing of Experiments for Space Station (EXPRESS) rack 7, which was located in the Port 2 location within the U.S Laboratory onboard the International Space Station (ISS). Activation and deactivation of this facility is time consuming and operationally intensive, requiring coordination of three flight control positions, 47 nominal steps, 57 commands, 276 telemetry checks, and coordination of multiple ISS systems (both core and payload). The autonomous operations concept includes a reduction of the amount of data a crew operator is required to verify during activation or de-activation, as well as integration of procedure execution status and relevant data in a single integrated display. During execution, the auto-procedures provide a step-by-step messaging paradigm and a high level status upon termination. This

  15. Automatic Reverse Engineering of Private Flight Control Protocols of UAVs

    Directory of Open Access Journals (Sweden)

    Ran Ji

    2017-01-01

    Full Text Available The increasing use of civil unmanned aerial vehicles (UAVs has the potential to threaten public safety and privacy. Therefore, airspace administrators urgently need an effective method to regulate UAVs. Understanding the meaning and format of UAV flight control commands by automatic protocol reverse-engineering techniques is highly beneficial to UAV regulation. To improve our understanding of the meaning and format of UAV flight control commands, this paper proposes a method to automatically analyze the private flight control protocols of UAVs. First, we classify flight control commands collected from a binary network trace into clusters; then, we analyze the meaning of flight control commands by the accumulated error of each cluster; next, we extract the binary format of commands and infer field semantics in these commands; and finally, we infer the location of the check field in command and the generator polynomial matrix. The proposed approach is validated via experiments on a widely used consumer UAV.

  16. Spaceport Command and Control System Support Software Development

    Science.gov (United States)

    Brunotte, Leonard

    2016-01-01

    The Spaceport Command and Control System (SCCS) is a project developed and used by NASA at Kennedy Space Center in order to control and monitor the Space Launch System (SLS) at the time of its launch. One integral subteam under SCCS is the one assigned to the development of a data set building application to be used both on the launch pad and in the Launch Control Center (LCC) at the time of launch. This web application was developed in Ruby on Rails, a web framework using the Ruby object-oriented programming language, by a 15 - employee team (approx.). Because this application is such a huge undertaking with many facets and iterations, there were a few areas in which work could be more easily organized and expedited. As an intern working with this team, I was charged with the task of writing web applications that fulfilled this need, creating a virtual and highly customizable whiteboard in order to allow engineers to keep track of build iterations and their status. Additionally, I developed a knowledge capture web application wherein any engineer or contractor within SCCS could ask a question, answer an existing question, or leave a comment on any question or answer, similar to Stack Overflow.

  17. Work Plan for an Engineering Evaluation/Cost Analysis in Support of the Intrinsic Remediation (Natural Attenuation) Option at the Former AGE Fuel Facility (Building 4715)

    National Research Council Canada - National Science Library

    1995-01-01

    ...) fueling facility adjacent to Building 4715 located at Seymour Johnson Air Force Base (AFB), Goldsboro, NC. This EE/CA will provide the framework for the site's Corrective Action Plan under the North Carolina requirements...

  18. 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

  19. Facilities & Leadership

    Data.gov (United States)

    Department of Veterans Affairs — The facilities web service provides VA facility information. The VA facilities locator is a feature that is available across the enterprise, on any webpage, for the...

  20. Thermal Mode of Tanks for Storage Fuel of Thermal Power Plants and Boiler with the Influence of Engineering Facilities in the Area of their Placement

    Science.gov (United States)

    Polovnikov, V. Yu.; Makhsutbek, F. T.; Ozhikenova, Zh. F.

    2016-02-01

    This paper describes the numerical modeling of heat transfer in the area placing of the tank for storage fuel of thermal power plant and boiler with the influence of engineering construction. We have established that the presence of engineering structures in the area of placing of the tank for storage fuel of thermal power plant and boiler have little effect on the change of heat loss.