Posttest examination of Sodium Loop Safety Facility experiments. [LMFBR
DOE Office of Scientific and Technical Information (OSTI.GOV)
Holland, J.W.
In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehensive posttest examinations (PTE) to characterize the postirradiation condition of the cladding, fuel, and other test-subassembly components. PTE information and on-line instrumentation data, are analyzed to identify the sequence of events and the severity of the accident for each experiment. Following in-reactor experimentation, the SLSF loop and test assembly are transported to the Hot Fuel Examination Facility (HFEF) for initial disassembly. Goals of the HFEF-phase of the PTE are to retrieve the fuel bundle by dismantling the loop and withdrawing the test assembly, to assess the macro-conditionmore » of the fuel bundle by nondestructive examination techniques, and to prepare the fuel bundle for shipment to the Alpha-Gamma Hot Cell Facility (AGHCF) at Argonne National Laboratory.« less
DOE Office of Scientific and Technical Information (OSTI.GOV)
Rose, S.D.; Dearing, J.F.
An understanding of conditions that may cause sodium boiling and boiling propagation that may lead to dryout and fuel failure is crucial in liquid-metal fast-breeder reactor safety. In this study, the SABRE-2P subchannel analysis code has been used to analyze the ultimate transient of the in-core W-1 Sodium Loop Safety Facility experiment. This code has a 3-D simple nondynamic boiling model which is able to predict the flow instability which caused dryout. In other analyses dryout has been predicted for out-of-core test bundles and so this study provides additional confirmation of the model.
Experiment Needs and Facilities Study Appendix A Transient Reactor Test Facility (TREAT) Upgrade
DOE Office of Scientific and Technical Information (OSTI.GOV)
None
The TREAT Upgrade effort is designed to provide significant new capabilities to satisfy experiment requirements associated with key LMFBR Safety Issues. The upgrade consists of reactor-core modifications to supply the physics performance needed for the new experiments, an Advanced TREAT loop with size and thermal-hydraulics capabilities needed for the experiments, associated interface equipment for loop operations and handling, and facility modifications necessary to accommodate operations with the Loop. The costs and schedules of the tasks to be accomplished under the TREAT Upgrade project are summarized. Cost, including contingency, is about 10 million dollars (1976 dollars). A schedule for execution ofmore » 36 months has been established to provide the new capabilities in order to provide timely support of the LMFBR national effort. A key requirement for the facility modifications is that the reactor availability will not be interrupted for more than 12 weeks during the upgrade. The Advanced TREAT loop is the prototype for the STF small-bundle package loop. Modified TREAT fuel elements contain segments of graphite-matrix fuel with graded uranium loadings similar to those of STF. In addition, the TREAT upgrade provides for use of STF-like stainless steel-UO{sub 2} TREAT fuel for tests of fully enriched fuel bundles. This report will introduce the Upgrade study by presenting a brief description of the scope, performance capability, safety considerations, cost schedule, and development requirements. This work is followed by a "Design Description". Because greatly upgraded loop performance is central to the upgrade, a description is given of Advanced TREAT loop requirements prior to description of the loop concept. Performance requirements of the upgraded reactor system are given. An extensive discussion of the reactor physics calculations performed for the Upgrade concept study is provided. Adequate physics performance is essential for performance of experiments with the Advanced TREAT loop, and the stress placed on these calculations reflects this. Additional material on performance and safety is provided. Backup calculations on calculations of plutonium-release limits are described. Cost and schedule information for the Upgrade are presented.« less
DOE Office of Scientific and Technical Information (OSTI.GOV)
O'Brien, James E.; Sabharwall, Piyush; Yoon, Su -Jong
2014-09-01
This report presents a conceptual design for a new high-temperature multi fluid, multi loop test facility for the INL to support thermal hydraulic, materials, and thermal energy storage research for nuclear and nuclear-hybrid applications. In its initial configuration, the facility will include a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The three loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). Research topics to be addressed with this facility include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuit heat exchangers (PCHEs)more » at prototypical operating conditions, flow and heat transfer issues related to core thermal hydraulics in advanced helium-cooled and salt-cooled reactors, and evaluation of corrosion behavior of new cladding materials and accident-tolerant fuels for LWRs at prototypical conditions. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integral System Test (ARTIST) facility. Research performed in this facility will advance the state of the art and technology readiness level of high temperature intermediate heat exchangers (IHXs) for nuclear applications while establishing the INL as a center of excellence for the development and certification of this technology. The thermal energy storage capability will support research and demonstration activities related to process heat delivery for a variety of hybrid energy systems and grid stabilization strategies. Experimental results obtained from this research will assist in development of reliable predictive models for thermal hydraulic design and safety codes over the range of expected advanced reactor operating conditions. Proposed/existing IHX heat transfer and friction correlations and criteria will be assessed with information on materials compatibility and instrumentation needs. The experimental database will guide development of appropriate predictive methods and be available for code verification and validation (V&V) related to these systems.« less
IN-PILE CORROSION TEST LOOPS FOR AQUEOUS HOMOGENEOUS REACTOR SOLUTIONS
DOE Office of Scientific and Technical Information (OSTI.GOV)
Savage, H.C.; Jenks, G.H.; Bohlmann, E.G.
1960-12-21
An in-pile corrosion test loop is described which is used to study the effect of reactor radiation on the corrosion of materials of construction and the chemical stability of fuel solutions of interest to the Aqueous Homogeneous Reactor Program at ORNL. Aqueous solutions of uranyl sulfate are circulated in the loop by means of a 5-gpm canned-rotor pump, and the pump loop is designed for operation at temperatures to 300 ts C and pressures to 2000 psia while exposed to reactor radiation in beam-hole facilities of the LITR and ORR. Operation of the first loop in-pile was begun in Octobermore » 1954, and since that time 17 other in-pile loop experiments were completed. Design criteria of the pump loop and its associated auxiliary equipment and instrumentation are described. In-pile operating procedures, safety features, and operating experience are presented. A cost summary of the design, fabrication, and installation of the loop and experimental facillties is also included. (auth)« less
Software Tools for Developing and Simulating the NASA LaRC CMF Motion Base
NASA Technical Reports Server (NTRS)
Bryant, Richard B., Jr.; Carrelli, David J.
2006-01-01
The NASA Langley Research Center (LaRC) Cockpit Motion Facility (CMF) motion base has provided many design and analysis challenges. In the process of addressing these challenges, a comprehensive suite of software tools was developed. The software tools development began with a detailed MATLAB/Simulink model of the motion base which was used primarily for safety loads prediction, design of the closed loop compensator and development of the motion base safety systems1. A Simulink model of the digital control law, from which a portion of the embedded code is directly generated, was later added to this model to form a closed loop system model. Concurrently, software that runs on a PC was created to display and record motion base parameters. It includes a user interface for controlling time history displays, strip chart displays, data storage, and initializing of function generators used during motion base testing. Finally, a software tool was developed for kinematic analysis and prediction of mechanical clearances for the motion system. These tools work together in an integrated package to support normal operations of the motion base, simulate the end to end operation of the motion base system providing facilities for software-in-the-loop testing, mechanical geometry and sensor data visualizations, and function generator setup and evaluation.
33 CFR 154.2104 - Pigging system.
Code of Federal Regulations, 2014 CFR
2014-07-01
... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Pigging system. 154.2104 Section... Facilities-Vcs Design and Installation § 154.2104 Pigging system. (a) If a pigging system is used to clear... system (VCS), the pigging system must be designed with the following safety features: (1) A bypass loop...
A calibration loop to test hot-wire response under supercritical conditions
NASA Astrophysics Data System (ADS)
Radulović, Ivana; Vukoslavčević, P. V.; Wallace, J. M.
2004-11-01
A calibration facility to test the response of hot-wires in CO2 flow under supercritical conditions has been designed and constructed. It is capable of inducing variable speeds at different temperatures and pressures in the ranges of 0.15 - 2 m/s, 15 - 70 deg. C and 1 - 100 bar. The facility is designed as a closed loop with a test section, pump, electrical heater, DC motor and different regulating and measuring devices. The test section is a small tunnel, with a diffuser, honeycomb, screens and a nozzle to provide a uniform flow with a low turbulence level. The speed variation is created by a sealed, magnetic driven gear pump, with a variable rpm DC motor. Using the electrical heater and regulating the amount of CO2 in the facility, the desired temperature and pressure can be reached. The dimensions of the instalation are minimized to reduce the heat, pump power required, and CO2 consumption and to optimize safety. Preliminary testing of a single hot-wire velocity sensor at constant pressure (80 bar) and variable speed and temperature will be briefly described. The hot-wire probes calibrated in this loop will be used to measure turbulence properties in supercritical CO2 in support of improved designs of nuclear reactors to be cooled by supercritical fluids.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Hohne, Thomas; Kliem, Soren; Rohde, Ulrich
2006-07-01
Coolant mixing in the cold leg, downcomer and the lower plenum of pressurized water reactors is an important phenomenon mitigating the reactivity insertion into the core. Therefore, mixing of the de-borated slugs with the ambient coolant in the reactor pressure vessel was investigated at the four loop 1:5 scaled ROCOM mixing test facility. Thermal hydraulics analyses showed, that weakly borated condensate can accumulate in particular in the pump loop seal of those loops, which do not receive safety injection. After refilling of the primary circuit, natural circulation in the stagnant loops can re-establish simultaneously and the de-borated slugs are shiftedmore » towards the reactor pressure vessel (RPV). In the ROCOM experiments, the length of the flow ramp and the initial density difference between the slugs and the ambient coolant was varied. From the test matrix experiments with 0 resp. 2% density difference between the de-borated slugs and the ambient coolant were used to validate the CFD software ANSYS CFX. To model the effects of turbulence on the mean flow a higher order Reynolds stress turbulence model was employed and a mesh consisting of 6.4 million hybrid elements was utilized. Only the experiments and CFD calculations with modeled density differences show a stratification in the downcomer. Depending on the degree of density differences the less dense slugs flow around the core barrel at the top of the downcomer. At the opposite side the lower borated coolant is entrained by the colder safety injection water and transported to the core. The validation proves that ANSYS CFX is able to simulate appropriately the flow field and mixing effects of coolant with different densities. (authors)« less
Federal Register 2010, 2011, 2012, 2013, 2014
2012-11-05
.... The analyses for LSCS, Unit 2, Cycle 15 have concluded that a two-loop MCPR SL of >= 1.14, based on... safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the... has provided its analysis of the issue of no significant hazards consideration, which is presented...
DOE Office of Scientific and Technical Information (OSTI.GOV)
M.D. Stine
1996-01-23
The purpose of this analysis is to select the critical characteristics to be verified for steel sets and accessories and the verification methods to be implemented through a material dedication process for the procurement and use of commercial grade structural steel sets and accessories (which have a nuclear safety function) to be used in ground support (with the exception of alcove ground support and alcove opening framing, which are not addressed in this analysis) for the Exploratory Studies Facility (ESF) Topopah Spring (TS) Loop. The ESF TS Loop includes the North Ramp, Main Drift, and South Ramp underground openings.
Passive Safety Features Evaluation of KIPT Neutron Source Facility
DOE Office of Scientific and Technical Information (OSTI.GOV)
Zhong, Zhaopeng; Gohar, Yousry
2016-06-01
Argonne National Laboratory (ANL) of the United States and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have cooperated on the development, design, and construction of a neutron source facility. The facility was constructed at Kharkov, Ukraine and its commissioning process is underway. It will be used to conduct basic and applied nuclear research, produce medical isotopes, and train young nuclear specialists. The facility has an electron accelerator-driven subcritical assembly. The electron beam power is 100 kW using 100 MeV electrons. Tungsten or natural uranium is the target material for generating neutrons driving the subcritical assembly. The subcritical assemblymore » is composed of WWR-M2 - Russian fuel assemblies with U-235 enrichment of 19.7 wt%, surrounded by beryllium reflector assembles and graphite blocks. The subcritical assembly is seated in a water tank, which is a part of the primary cooling loop. During normal operation, the water coolant operates at room temperature and the total facility power is ~300 KW. The passive safety features of the facility are discussed in in this study. Monte Carlo computer code MCNPX was utilized in the analyses with ENDF/B-VII.0 nuclear data libraries. Negative reactivity temperature feedback was consistently observed, which is important for the facility safety performance. Due to the design of WWR-M2 fuel assemblies, slight water temperature increase and the corresponding water density decrease produce large reactivity drop, which offset the reactivity gain by mistakenly loading an additional fuel assembly. The increase of fuel temperature also causes sufficiently large reactivity decrease. This enhances the facility safety performance because fuel temperature increase provides prompt negative reactivity feedback. The reactivity variation due to an empty fuel position filled by water during the fuel loading process is examined. Also, the loading mistakes of removing beryllium reflector assemblies and replacing them with dummy assemblies were analyzed. In all these circumstances, the reactivity change results do not cause any safety concerns.« less
Hardware in the Loop at Megawatt-Scale Power | Energy Systems Integration
Facility | NREL Hardware in the Loop at Megawatt-Scale Power Hardware in the Loop at Megawatt -Scale Power Hardware-in-the-loop simulation is not new, but the Energy System Integration Facility's -in-the-loop co-simulation. For more information, read the power hardware-in-the-loop factsheet. Text
Tritium Mitigation/Control for Advanced Reactor System
DOE Office of Scientific and Technical Information (OSTI.GOV)
Sun, Xiaodong; Christensen, Richard; Saving, John P.
A tritium removal facility, which is similar to the design used for tritium recovery in fusion reactors, is proposed in this study for fluoride-salt-cooled high-temperature reactors (FHRs) to result in a two-loop FHR design with the elimination of an intermediate loop. Using this approach, an economic benefit can potentially be obtained by removing the intermediate loop, while the safety concern of tritium release can be mitigated. In addition, an intermediate heat exchanger (IHX) that can yield a similar tritium permeation rate to the production rate of 1.9 Ci/day in a 1,000 MWe PWR needs to be designed to prevent themore » residual tritium that is not captured in the tritium removal system from escaping into the power cycle and ultimately the environment. The main focus of this study is to aid the mitigation of tritium permeation issue from the FHR primary side to significantly reduce the concentration of tritium in the secondary side and the process heat application side (if applicable). The goal of the research is to propose a baseline FHR system without the intermediate loop. The specific objectives to accomplish the goals are: To estimate tritium permeation behavior in FHRs; To design a tritium removal system for FHRs; To meet the same tritium permeation level in FHRs as the tritium production rate of 1.9 Ci/day in 1,000 MWe PWRs; To demonstrate economic benefits of the proposed FHR system via comparing with the three-loop FHR system. The objectives were accomplished by designing tritium removal facilities, developing a tritium analysis code, and conducting an economic analysis. In the fusion reactor community, tritium extraction has been widely investigated and researched. Borrowing the experiences from the fusion reactor community, a tritium control and mitigation system was proposed. Based on mass transport theories, a tritium analysis code was developed, and the tritium behaviors were analyzed using the developed code. Tritium removal facilities were designed and laboratory-scale experiments were proposed for the validation of the proposed tritium removal facilities.« less
NASA Astrophysics Data System (ADS)
Chow, L. C.; Hahn, O. J.; Nguyen, H. X.
1992-08-01
This report presents the description of a liquid sodium heat transfer facility (sodium loop) constructed to support the study of transient response of heat pipes. The facility, consisting of the loop itself, a safety system, and a data acquisition system, can be safely operated over a wide range of temperature and sodium flow rate. The transient response of a heat pipe to pulse heat load at the condenser section was experimentally investigated. A 0.457 m screen wick, sodium heat pipe with an outer diameter of 0.127 m was tested under different heat loading conditions. A major finding was that the heat pipe reversed under a pulse heat load applied at the condenser. The time of reversal was approximately 15 to 25 seconds. The startup of the heat pipe from frozen state was also studied. It was found that during the startup process, at least part of the heat pipe was active. The active region extended gradually down to the end of the condenser until all of the working fluid in the heat pipe was molten.
Takata, Miki; Fukushima, Kazuyo; Kino-Kimata, Noriko; Nagao, Norio; Niwa, Chiaki; Toda, Tatsuki
2012-08-15
In Japan, a revised Food Recycling Law went into effect in 2007 to promote a "recycling loop" that requires food industries to purchase farm products that are grown using food waste-derived compost/animal feed. To realize and expand food recycling, it is necessary to evaluate how the recycling facilities work in the recycling loop. The purpose of this study is to assess the environmental and economic efficiency of the food recycling facilities that are involved in the recycling loop, which are also known as looped facilities. The global warming potential and running cost of five looped facilities were evaluated by LCA (life cycle assessment) and LCC (life cycle cost) approaches: machine integrated compost, windrow compost, liquid feed, dry feed, and bio-gasification. The LCA results showed low total GHG (greenhouse gas) emissions of -126 and -49 kg-CO(2)/t-waste, respectively, for dry feed and bio-gasification facilities, due to a high substitution effect. The LCC study showed a low running cost for composting facilities of -15,648 and -18,955 yen/t-waste, respectively, due to high revenue from the food waste collection. It was found that the mandatory reporting of food waste emitters to the government increased collection fees; however, the collection fee in animal feed facilities was relatively low because food waste was collected at a low price or nutritious food waste was purchased to produce quality feed. In the characterisation survey of various treatment methods, the composting facilities showed a relatively low environmental impact and a high economic efficiency. Animal feed facilities had a wide distribution of the total GHG emissions, depending on both the energy usage during the drying process and the substitution effect, which were related to the water content of the food waste and the number of recycled products. In comparison with incineration, the majority of the food recycling facilities showed low GHG emissions and economic effectiveness. This paper also reported on the effects of recycling loops by comparing looped and non-looped animal feed facilities, and confirmed that the looped facilities were economically effective, due to an increased amount of food waste collection. Copyright © 2012 Elsevier B.V. All rights reserved.
SLSF in-reactor local fault safety experiment P4. Final report
DOE Office of Scientific and Technical Information (OSTI.GOV)
Thompson, D. H.; Holland, J. W.; Braid, T. H.
The Sodium Loop Safety Facility (SLSF), a major facility in the US fast-reactor safety program, has been used to simulate a variety of sodium-cooled fast reactor accidents. SLSF experiment P4 was conducted to investigate the behavior of a "worse-than-case" local fault configuration. Objectives of this experiment were to eject molten fuel into a 37-pin bundle of full-length Fast-Test-Reactor-type fuel pins form heat-generating fuel canisters, to characterize the severity of any molten fuel-coolant interaction, and to demonstrate that any resulting blockage could either be tolerated during continued power operation or detected by global monitors to prevent fuel failure propagation. The designmore » goal for molten fuel release was 10 to 30 g. Explusion of molten fuel from fuel canisters caused failure of adjacent pins and a partial flow channel blockage in the fuel bundle during full-power operation. Molten fuel and fuel debris also lodged against the inner surface of the test subassembly hex-can wall. The total fuel disruption of 310 g evaluated from posttest examination data was in excellent agreement with results from the SLSF delayed neutron detection system, but exceeded the target molten fuel release by an order of magnitude. This report contains a summary description of the SLSF in-reactor loop and support systems and the experiment operations. results of the detailed macro- and microexamination of disrupted fuel and metal and results from the analysis of the on-line experimental data are described, as are the interpretations and conclusions drawn from the posttest evaluations. 60 refs., 74 figs.« less
Core characterization of the new CABRI Water Loop Facility
DOE Office of Scientific and Technical Information (OSTI.GOV)
Ritter, G.; Rodiac, F.; Beretz, D.
2011-07-01
The CABRI experimental reactor is located at the Cadarache nuclear research center, southern France. It is operated by the Atomic Energy Commission (CEA) and devoted to IRSN (Institut de Radioprotection et de Surete Nucleaire) safety programmes. It has been successfully operated during the last 30 years, enlightening the knowledge of FBR and LWR fuel behaviour during Reactivity Insertion Accident (RIA) and Loss Of Coolant Accident (LOCA) transients in the frame of IPSN (Institut de Protection et de Surete Nucleaire) and now IRSN programmes devoted to reactor safety. This operation was interrupted in 2003 to allow for a whole facility renewalmore » programme for the need of the CABRI International Programme (CIP) carried out by IRSN under the OECD umbrella. The principle of operation of the facility is based on the control of {sup 3}He, a major gaseous neutron absorber, in the core geometry. The purpose of this paper is to illustrate how several dosimetric devices have been set up to better characterize the core during the upcoming commissioning campaign. It presents the schemes and tools dedicated to core characterization. (authors)« less
[Experience feedback committee: a method for patient safety improvement].
François, P; Sellier, E; Imburchia, F; Mallaret, M-R
2013-04-01
An experience feedback committee (CREX, Comité de Retour d'EXpérience) is a method which contributes to the management of safety of care in a medical unit. Originally used for security systems of civil aviation, the method has been adapted to health care facilities and successfully implemented in radiotherapy units and in other specialties. We performed a brief review of the literature for studies reporting data on CREX established in hospitals. The review was performed using the main bibliographic databases and Google search results. The CREX is designed to analyse incidents reported by professionals. The method includes monthly meetings of a multi-professional committee that reviews the reported incidents, chooses a priority incident and designates a "pilot" responsible for investigating the incident. The investigation of the incident involves a systemic analysis method and a written synthesis presented at the next meeting of the committee. The committee agrees on actions for improvement that are suggested by the analysis and follows their implementation. Systems for the management of health care, including reporting systems, are organized into three levels: the medical unit, the hospital and the country as a triple loop learning process. The CREX is located in the base level, short loop of risk management and allows direct involvement of care professionals in patient safety. Safety of care has become a priority of health systems. In this context, the CREX can be a useful vehicle for the implementation of a safety culture in medical units. Copyright © 2013 Elsevier Masson SAS. All rights reserved.
The design of components for an advanced Rankine cycle test facility.
NASA Technical Reports Server (NTRS)
Bond, J. A.
1972-01-01
The design of a facility for testing components of an advanced Rankine cycle power system is summarized. The facility is a three-loop system in which lithium, potassium and NaK-78 are the working fluids of the primary, secondary and heat-rejection loops, respectively. Design bases and performance predictions for the major loop components, including the lithium heater and the potassium boiler, condenser and preheater, are outlined.
An Autonomous Flight Safety System
NASA Technical Reports Server (NTRS)
Bull, James B.; Lanzi, Raymond J.
2007-01-01
The Autonomous Flight Safety System (AFSS) being developed by NASA s Goddard Space Flight Center s Wallops Flight Facility and Kennedy Space Center has completed two successful developmental flights and is preparing for a third. AFSS has been demonstrated to be a viable architecture for implementation of a completely vehicle based system capable of protecting life and property in event of an errant vehicle by terminating the flight or initiating other actions. It is capable of replacing current human-in-the-loop systems or acting in parallel with them. AFSS is configured prior to flight in accordance with a specific rule set agreed upon by the range safety authority and the user to protect the public and assure mission success. This paper discusses the motivation for the project, describes the method of development, and presents an overview of the evolving architecture and the current status.
DOE Office of Scientific and Technical Information (OSTI.GOV)
McCulloch, R.W.; Post, D.W.; Lovell, R.T.
1981-04-01
Variable-width ribbon heating elements that provide a chopped-cosine variable heat flux profile have been fabricated for fuel pin simulators used in test loops by the Breeder Reactor Program Thermal-Hydraulic Out-of-Reactor Safety test facility and the Gas-Cooled Fast Breeder Reactor-Core Flow Test Loop. Thermal, mechanical, and electrical design considerations are used to derive an analytical expression that precisely describes ribbon contour in terms of the major fabrication parameters. These parameters are used to generate numerical control tapes that control ribbon cutting and winding machines. Infrared scanning techniques are developed to determine the optimum transient thermal profile of the coils and relatemore » this profile to that generated by the coils in completed fuel pin simulators.« less
An Innovative Hybrid Loop-Pool SFR Design and Safety Analysis Methods: Today and Tomorrow
DOE Office of Scientific and Technical Information (OSTI.GOV)
Hongbin Zhang; Haihua Zhao; Vincent Mousseau
2008-04-01
Investment in commercial sodium cooled fast reactor (SFR) power plants will become possible only if SFRs achieve economic competitiveness as compared to light water reactors and other Generation IV reactors. Toward that end, we have launched efforts to improve the economics and safety of SFRs from the thermal design and safety analyses perspectives at Idaho National Laboratory. From the thermal design perspective, an innovative hybrid loop-pool SFR design has been proposed. This design takes advantage of the inherent safety of a pool design and the compactness of a loop design to further improve economics and safety. From the safety analysesmore » perspective, we have initiated an effort to develop a high fidelity reactor system safety code.« less
Requirements for significant problem reporting and trend analysis
NASA Technical Reports Server (NTRS)
1988-01-01
This handbook supplements policies, requirements, and procedures of NMI 8070.3 to ensure that NASA management at each organizational level is: fully aware of trends affecting both the level of safety and the potential for mission success established for both NASA manned space programs and its supporting institutions; fully and independently informed of problems that represent significant risk to the safety of all personnel (including the general populace) and to the success of a mission or operation through a program mechanism herein defined as Significant Problem Reporting; and in full agreement with the level of elimination of these problems through the closed-loop accounting of corrective actions. The requirements of this handbook are supportive of the agency's safety, reliability, maintainability, and quality assurance (SRM&QA) program objectives and are applicable to all organizational elements of NASA connected with or supporting developmental or operational manned space program/projects (including associated payloads) and the related institutional facilities.
Model-Driven Safety Analysis of Closed-Loop Medical Systems
Pajic, Miroslav; Mangharam, Rahul; Sokolsky, Oleg; Arney, David; Goldman, Julian; Lee, Insup
2013-01-01
In modern hospitals, patients are treated using a wide array of medical devices that are increasingly interacting with each other over the network, thus offering a perfect example of a cyber-physical system. We study the safety of a medical device system for the physiologic closed-loop control of drug infusion. The main contribution of the paper is the verification approach for the safety properties of closed-loop medical device systems. We demonstrate, using a case study, that the approach can be applied to a system of clinical importance. Our method combines simulation-based analysis of a detailed model of the system that contains continuous patient dynamics with model checking of a more abstract timed automata model. We show that the relationship between the two models preserves the crucial aspect of the timing behavior that ensures the conservativeness of the safety analysis. We also describe system design that can provide open-loop safety under network failure. PMID:24177176
Model-Driven Safety Analysis of Closed-Loop Medical Systems.
Pajic, Miroslav; Mangharam, Rahul; Sokolsky, Oleg; Arney, David; Goldman, Julian; Lee, Insup
2012-10-26
In modern hospitals, patients are treated using a wide array of medical devices that are increasingly interacting with each other over the network, thus offering a perfect example of a cyber-physical system. We study the safety of a medical device system for the physiologic closed-loop control of drug infusion. The main contribution of the paper is the verification approach for the safety properties of closed-loop medical device systems. We demonstrate, using a case study, that the approach can be applied to a system of clinical importance. Our method combines simulation-based analysis of a detailed model of the system that contains continuous patient dynamics with model checking of a more abstract timed automata model. We show that the relationship between the two models preserves the crucial aspect of the timing behavior that ensures the conservativeness of the safety analysis. We also describe system design that can provide open-loop safety under network failure.
DOE Office of Scientific and Technical Information (OSTI.GOV)
James E. O'Brien; Piyush Sabharwall; SuJong Yoon
2001-11-01
Effective and robust high temperature heat transfer systems are fundamental to the successful deployment of advanced reactors for both power generation and non-electric applications. Plant designs often include an intermediate heat transfer loop (IHTL) with heat exchangers at either end to deliver thermal energy to the application while providing isolation of the primary reactor system. In order to address technical feasibility concerns and challenges a new high-temperature multi-fluid, multi-loop test facility “Advanced Reactor Technology Integral System Test facility” (ARTIST) is under development at the Idaho National Laboratory. The facility will include three flow loops: high-temperature helium, molten salt, and steam/water.more » Details of some of the design aspects and challenges of this facility, which is currently in the conceptual design phase, are discussed« less
Building Airport Surface HITL Simulation Capability
NASA Technical Reports Server (NTRS)
Chinn, Fay Cherie
2016-01-01
FutureFlight Central is a high fidelity, real-time simulator designed to study surface operations and automation. As an air traffic control tower simulator, FFC allows stakeholders such as the FAA, controllers, pilots, airports, and airlines to develop and test advanced surface and terminal area concepts and automation including NextGen and beyond automation concepts and tools. These technologies will improve the safety, capacity and environmental issues facing the National Airspace system. FFC also has extensive video streaming capabilities, which combined with the 3-D database capability makes the facility ideal for any research needing an immersive virtual and or video environment. FutureFlight Central allows human in the loop testing which accommodates human interactions and errors giving a more complete picture than fast time simulations. This presentation describes FFCs capabilities and the components necessary to build an airport surface human in the loop simulation capability.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
The Ingham County solar system consists of approximately 10,000 square feet of solar collectors connected in a closed configuration loop. The primary loop solution is a 1:12 mixture of water and propylene glycol which flows through the tube side of a heat exchanger connected to the primary storage tank. The heat energy which is supplied to the primary storage tank is subsequently used to preheat the temperature of the laundry water, kitchen water, and domestic potable water. Included in this report are: detailed drawings and flow chart; operational methodology; preventive maintenance instructions; general instructions and safety precautions; and a correctivemore » maintenance and tabulation of failure modes. Appendices include: manufacturers technical manual and component specifications; IBM data sensors and responsibilities; digital county monitor operations manual; and on site monitor operations manual. Reference CAPE-2834. (LS)« less
LOOP marine and estuarine monitoring program, 1978-95 : volume 5 : demersal nekton.
DOT National Transportation Integrated Search
1998-01-01
The Louisiana Offshore Oil Port (LOOP) facilities in coastal Louisiana provide the United States with the country's only Superport for off-loading deep draft tankers. The facilities transport oil ashore through pipelines, and temporarily store oil be...
Hazan, Hananel; Ziv, Noam E
2017-01-01
There is growing need for multichannel electrophysiological systems that record from and interact with neuronal systems in near real-time. Such systems are needed, for example, for closed loop, multichannel electrophysiological/optogenetic experimentation in vivo and in a variety of other neuronal preparations, or for developing and testing neuro-prosthetic devices, to name a few. Furthermore, there is a need for such systems to be inexpensive, reliable, user friendly, easy to set-up, open and expandable, and possess long life cycles in face of rapidly changing computing environments. Finally, they should provide powerful, yet reasonably easy to implement facilities for developing closed-loop protocols for interacting with neuronal systems. Here, we survey commercial and open source systems that address these needs to varying degrees. We then present our own solution, which we refer to as Closed Loop Experiments Manager (CLEM). CLEM is an open source, soft real-time, Microsoft Windows desktop application that is based on a single generic personal computer (PC) and an inexpensive, general-purpose data acquisition board. CLEM provides a fully functional, user-friendly graphical interface, possesses facilities for recording, presenting and logging electrophysiological data from up to 64 analog channels, and facilities for controlling external devices, such as stimulators, through digital and analog interfaces. Importantly, it includes facilities for running closed-loop protocols written in any programming language that can generate dynamic link libraries (DLLs). We describe the application, its architecture and facilities. We then demonstrate, using networks of cortical neurons growing on multielectrode arrays (MEA) that despite its reliance on generic hardware, its performance is appropriate for flexible, closed-loop experimentation at the neuronal network level.
Hazan, Hananel; Ziv, Noam E.
2017-01-01
There is growing need for multichannel electrophysiological systems that record from and interact with neuronal systems in near real-time. Such systems are needed, for example, for closed loop, multichannel electrophysiological/optogenetic experimentation in vivo and in a variety of other neuronal preparations, or for developing and testing neuro-prosthetic devices, to name a few. Furthermore, there is a need for such systems to be inexpensive, reliable, user friendly, easy to set-up, open and expandable, and possess long life cycles in face of rapidly changing computing environments. Finally, they should provide powerful, yet reasonably easy to implement facilities for developing closed-loop protocols for interacting with neuronal systems. Here, we survey commercial and open source systems that address these needs to varying degrees. We then present our own solution, which we refer to as Closed Loop Experiments Manager (CLEM). CLEM is an open source, soft real-time, Microsoft Windows desktop application that is based on a single generic personal computer (PC) and an inexpensive, general-purpose data acquisition board. CLEM provides a fully functional, user-friendly graphical interface, possesses facilities for recording, presenting and logging electrophysiological data from up to 64 analog channels, and facilities for controlling external devices, such as stimulators, through digital and analog interfaces. Importantly, it includes facilities for running closed-loop protocols written in any programming language that can generate dynamic link libraries (DLLs). We describe the application, its architecture and facilities. We then demonstrate, using networks of cortical neurons growing on multielectrode arrays (MEA) that despite its reliance on generic hardware, its performance is appropriate for flexible, closed-loop experimentation at the neuronal network level. PMID:29093659
DOE Office of Scientific and Technical Information (OSTI.GOV)
Shurupov, A. V.; Zavalova, V. E., E-mail: zavalova@fites.ru; Kozlov, A. V.
The report presents the results of the development and field testing of a mobile test facility based on a helical magnetic cumulative generator (MCGTF). The system is designed for full-scale modeling of lightning currents to study the safety of power plants of any type, including nuclear power plants. Advanced technologies of high-energy physics for solving both engineering and applied problems underlie this pilot project. The energy from the magnetic cumulative generator (MCG) is transferred to a high-impedance load with high efficiency of more than 50% using pulse transformer coupling. Modeling of the dynamics of the MEG that operates in amore » circuit with lumped parameters allows one to apply the law of inductance output during operation of the MCG, thus providing the required front of the current pulse in the load without using any switches. The results of field testing of the MCGTF are presented for both the ground loop and the model load. The ground loop generates a load resistance of 2–4 Ω. In the tests, the ohmic resistance of the model load is 10 Ω. It is shown that the current pulse parameters recorded in the resistive-inductive load are close to the calculated values.« less
High-Performance Computing Data Center Efficiency Dashboard | Computational
recovery water (ERW) loop Heat exchanger for energy recovery Thermosyphon Heat exchanger between ERW loop and cooling tower loop Evaporative cooling towers Learn more about our energy-efficient facility
Methods and systems for the production of hydrogen
Oh, Chang H [Idaho Falls, ID; Kim, Eung S [Ammon, ID; Sherman, Steven R [Augusta, GA
2012-03-13
Methods and systems are disclosed for the production of hydrogen and the use of high-temperature heat sources in energy conversion. In one embodiment, a primary loop may include a nuclear reactor utilizing a molten salt or helium as a coolant. The nuclear reactor may provide heat energy to a power generation loop for production of electrical energy. For example, a supercritical carbon dioxide fluid may be heated by the nuclear reactor via the molten salt and then expanded in a turbine to drive a generator. An intermediate heat exchange loop may also be thermally coupled with the primary loop and provide heat energy to one or more hydrogen production facilities. A portion of the hydrogen produced by the hydrogen production facility may be diverted to a combustor to elevate the temperature of water being split into hydrogen and oxygen by the hydrogen production facility.
Enabling Medical Device Interoperability for the Integrated Clinical Environment
2016-02-01
Pajic M, Mangharam R, Sokolsky O, Arney D, Goldman JM, Lee I. Model-Driven Safety Analysis of Closed - Loop Medical Systems. IEEE Transactions on...Manigel J, Osborn D, Roellike T, Weininger S, Westenskow D, “Development of a Standard for Physiologic Closed Loop Controllers in Medical Devices...3 2010. 27. Arney D, Pajic M, Goldman JM, Lee I, Mangharam R, Sokolsky O, “Toward Patient Safety in Closed - Loop Medical Device Systems,” In
High-Performance Computing Data Center Waste Heat Reuse | Computational
control room With heat exchangers, heat energy in the energy recovery water (ERW) loop becomes available to heat the facility's process hot water (PHW) loop. Once heated, the PHW loop supplies: Active loop in the courtyard of the ESIF's main entrance District heating loop: If additional heat is needed
Austin, Jodie A; Smith, Ian R; Tariq, Amina
2018-01-22
Closed-loop electronic medication management systems (EMMS) are recognised as an effective intervention to improve medication safety, yet evidence of their effectiveness in hospitals is limited. Few studies have compared medication turnaround time for a closed-loop electronic versus paper-based medication management environment. To compare medication turnaround times in a paper-based hospital environment with a digital hospital equipped with a closed-loop EMMS, consisting of computerised physician order entry, profiled automated dispensing cabinets packaged with unit dose medications and barcode medication administration. Data were collected during 2 weeks at three private hospital sites (one with closed-loop EMMS) within the same organisation network in Queensland, Australia. Time between scheduled and actual administration times was analysed for first dose of time-critical and non-critical medications located on the ward or sourced via pharmacy. Medication turnaround times at the EMMS site were less compared to the paper-based sites (median, IQR: 35 min, 8-57 min versus 120 min, 30-180 min, P < 0.001). For time-critical medications, 77% were administered within 60 min of scheduled time at the EMMS site versus 38% for the paper-based sites. Similar difference was observed for non-critical medications, 80% were administered within 60 min of their scheduled time at the EMMS site versus 41% at the paper-based facilities. The study indicates medication turnaround times utilising a closed-loop EMMS are less compared to paper-based systems. This improvement may be attributable to increased accessibility of medications using automated dispensing cabinets and electronic medication administration records flagging tasks to nurses in real time. © 2018 Royal Pharmaceutical Society.
Investigation of a “Sharps” Incident
Cournoyer, Michael Edward; Trujillo, Stanley; Schreiber, Stephen Bruce
2016-08-03
Special nuclear material research, process development, technology demonstration, and manufacturing capabilities are provided at the Los Alamos National Laboratory Plutonium Facility. Engineered barriers provide the most effective protection from radioactive and hazardous materials. The Worker Safety Security Team augments these passive safety feature by investigating incidents to identify appropriate prevention and mitigation measures. “Learning Teams” facilitate employee feedback loop and integration toward process improvement. Here, this article reports an investigation of a “Sharps” incident and reviews a case study of a technician that cuts his left thumb while making a gasket. Causal analysis of the sharps incident uncovered contributing factorsmore » that created the environment in which the incident occurred. Finally, latent organizational conditions that created error-likely situations or weakened defenses were identified and controlled. Effective improvements that reduce the probability or consequence of similar sharps incidents were implemented.« less
Energy Systems Integration Facility to Transform U.S. Energy Infrastructure
operations center. Fully integrated with hardware-in-the-loop at power capabilities, an experimental hardware- and systems-in-the-loop capability. Hardware-in-the-Loop at Power ESIF Snapshot Cost : $135M 2013 Hardware-in-the-loop simulation is not a new concept, but adding megawatt-scale power takes
Fault Detection and Safety in Closed-Loop Artificial Pancreas Systems
2014-01-01
Continuous subcutaneous insulin infusion pumps and continuous glucose monitors enable individuals with type 1 diabetes to achieve tighter blood glucose control and are critical components in a closed-loop artificial pancreas. Insulin infusion sets can fail and continuous glucose monitor sensor signals can suffer from a variety of anomalies, including signal dropout and pressure-induced sensor attenuations. In addition to hardware-based failures, software and human-induced errors can cause safety-related problems. Techniques for fault detection, safety analyses, and remote monitoring techniques that have been applied in other industries and applications, such as chemical process plants and commercial aircraft, are discussed and placed in the context of a closed-loop artificial pancreas. PMID:25049365
High-Performance Computing Data Center Cooling System Energy Efficiency |
approaches involve a cooling distribution unit (CDU) (2), which interfaces with the facility cooling loop and to the energy recovery water (ERW) loop (5), which is a closed-loop system. There are three heat rejection options for this IT load: When possible, heat energy from the energy recovery loop is transferred
Systems Performance Laboratory | Energy Systems Integration Facility | NREL
array access Small Commercial Power Hardware in the Loop The small commercial power-hardware-in-the-loop (PHIL) test bay is dedicated to small-scale power hardware-in-the-loop studies of inverters and other , natural gas supply Multi-Inverter Power Hardware in the Loop The multi-inverter test bay is dedicated to
PBF Reactor Building (PER620). Cubicle 10. Camera facing southeast. Loop ...
PBF Reactor Building (PER-620). Cubicle 10. Camera facing southeast. Loop pressurizer on right. Other equipment includes loop strained, control valves, loop piping, pressurizer interchanger, and cleanup system cooler. High-density shielding brick walls. Photographer: Kirsh. Date: November 2, 1970. INEEL negative no. 70-4908 - Idaho National Engineering Laboratory, SPERT-I & Power Burst Facility Area, Scoville, Butte County, ID
Environment, Safety, and Health: Status of DOE’s Reorganization of it’s Safety Oversight Function
1990-01-01
facilities. After deliberation, the Congress in late 1988 directed that the Defense Nuclear Facilities Safety Board be established to provide...nuclear safety matters will be conducted by either the Advisory Committee on Nuclear Facility Safety or the recently mandated Defense Nuclear Facilities Safety...the facilities under the statutory purview of the Defense Nuclear Facilities Safety Board once the board determines it is ready to assume independent
McEwan, Thomas E.
1997-01-01
A safety device includes a wire loop embedded in the glass of a passenger car window and routed near the closing leading-edge of the window. The wire loop carries microwave pulses around the loop to and from a transceiver with separate output and input ports. An evanescent field only and inch or two in radius is created along the wire loop by the pulses. Just about any object coming within the evanescent field will dramatically reduce the energy of the microwave pulses received back by the transceiver. Such a loss in energy is interpreted as a closing area blockage, and electrical interlocks are provided to halt or reverse a power window motor that is actively trying to close the window.
McEwan, T.E.
1997-08-26
A safety device includes a wire loop embedded in the glass of a passenger car window and routed near the closing leading-edge of the window. The wire loop carries microwave pulses around the loop to and from a transceiver with separate output and input ports. An evanescent field only an inch or two in radius is created along the wire loop by the pulses. Just about any object coming within the evanescent field will dramatically reduce the energy of the microwave pulses received back by the transceiver. Such a loss in energy is interpreted as a closing area blockage, and electrical interlocks are provided to halt or reverse a power window motor that is actively trying to close the window. 5 figs.
NASA Astrophysics Data System (ADS)
Juarsa, M.; Giarno; Rohman, A. N.; Heru K., G. B.; Witoko, J. P.; Sony Tjahyani, D. T.
2018-02-01
The need for large-scale experimental facilities to investigate the phenomenon of natural circulation flow rate becomes a necessity in the development of nuclear reactor safety management. The FASSIP-01 loop has been built to determine the natural circulation flow rate performance in the large-scale media and aimed to reduce errors in the results for its application in the design of new generation reactors. The commissioning needs to be done to define the capability of the FASSIP-01 loop and to prescribe the experiment limitations. On this commissioning, two scenarios experimental method has been used. The first scenario is a static condition test which was conducted to verify measurement system response during 24 hours without electrical load in heater and cooler, there is water and no water inside the rectangular loop. Second scenario is a dynamics condition that aims to understand the flow rate, a dynamic test was conducted using heater power of 5627 watts and coolant flow rate in the HSS loop of 9.35 LPM. The result of this test shows that the temperature characterization on static test provide a recommendation, that the experiments should be done at night because has a better environmental temperature stability compared to afternoon, with stable temperature around 1°C - 3°C. While on the dynamic test, the water temperature difference between the inlet-outlets in the heater area is quite large, about 7 times the temperature difference in the cooler area. The magnitude of the natural circulation flow rate calculated is much larger at about 300 times compared to the measured flow rate with different flow rate profiles.
Neutron Source Facility Training Simulator Based on EPICS
DOE Office of Scientific and Technical Information (OSTI.GOV)
Park, Young Soo; Wei, Thomas Y.; Vilim, Richard B.
A plant operator training simulator is developed for training the plant operators as well as for design verification of plant control system (PCS) and plant protection system (PPS) for the Kharkov Institute of Physics and Technology Neutron Source Facility. The simulator provides the operator interface for the whole plant including the sub-critical assembly coolant loop, target coolant loop, secondary coolant loop, and other facility systems. The operator interface is implemented based on Experimental Physics and Industrial Control System (EPICS), which is a comprehensive software development platform for distributed control systems. Since its development at Argonne National Laboratory, it has beenmore » widely adopted in the experimental physics community, e.g. for control of accelerator facilities. This work is the first implementation for a nuclear facility. The main parts of the operator interface are the plant control panel and plant protection panel. The development involved implementation of process variable database, sequence logic, and graphical user interface (GUI) for the PCS and PPS utilizing EPICS and related software tools, e.g. sequencer for sequence logic, and control system studio (CSS-BOY) for graphical use interface. For functional verification of the PCS and PPS, a plant model is interfaced, which is a physics-based model of the facility coolant loops implemented as a numerical computer code. The training simulator is tested and demonstrated its effectiveness in various plant operation sequences, e.g. start-up, shut-down, maintenance, and refueling. It was also tested for verification of the plant protection system under various trip conditions.« less
Energy Systems Integration News | Energy Systems Integration Facility |
-the-loop" (HIL) to connect physical devices to software models, EdgePower is drawing on NREL's are putting their controller into a synthetic environment that is called 'controller in-the-loop controller-in-the-loop platform allows us to observe the dynamics of these buildings as they implement the
Energy Systems Integration News | Energy Systems Integration Facility |
simulation and testing platforms from each organization. Power-hardware-in-the-loop technology at the power-hardware-in-the-loop and modeling capabilities together with real data from Duke Energy and GE's , communities, and microgrids. Hardware-in-the-loop testing for power systems will be used to verify the
Energy Systems Integration News | Energy Systems Integration Facility |
distribution feeder models for use in hardware-in-the-loop (HIL) experiments. Using this method, a full feeder ; proposes an additional control loop to improve frequency support while ensuring stable operation. The and Frequency Deviation," also proposes an additional control loop, this time to smooth the wind
Demonstration of Standard HVAC Single-Loop Digital Control Systems
1993-01-01
AD-A265 372 T N FEAP-TR-FE-93/05 REPORT January 1993 FACILITIES ENGINEERING APPLICATIONS PROGRAM Demonstration of Standard HVAC Single-Loop Digital...AND DATES COVERED January 1993 Final 4. TITLE AND SUBTITLE [5. FUNDING NUMBERS Demonstration of Standard HVAC Single-Loop Digital Control Systems FEAP...conditioning ( HVAC ) control systems provide guidance on designing and specifying standard HVAC control systems that use single-loop digital controllers
Monitoring long-term evolution of engineered barrier systems using magnets: Magnetic response.
Rigonat, N; Isnard, O; Harley, S L; Butler, I B
2018-01-05
Remote and non-destructive monitoring of the stability and performance of Engineered Barrier Systems for Geological Disposal Facility of is gaining considerable importance in establishing the safety cases for Higher Activity Wastes disposal. This study offers an innovative use of mineral magnetism for monitoring groundwater saturation of the barrier. Four mixtures of permanent magnets (Nd-Fe-B, coated and uncoated; SmCo and AlNiCo) and bentonite were reacted for 4, 8 and 12 months with mildly-saline, high-pH leachates, representing the fluids saturating a time-evolved engineered barrier. Coupled hysteresis and thermomagnetic analyses demonstrate how Nd-Fe-B feature a time-dependent transition from square-like ferromagnetic to superparamagnetic loop via pot-bellied and wasp-waist loops, whereas SmCo and AlNiCo do not show so extensive corrosion-related variations of the intrinsic and extrinsic magnetic properties. This study allowed to identify magnetic materials suitable for shorter- (Nd-Fe-B) and longer-term (SmCo and AlNiCo) monitoring purposes. Copyright © 2017 The Authors. Published by Elsevier B.V. All rights reserved.
Integration of Hardware-in-the-loop Facilities Over the Internet
2009-04-15
This briefing discusses a hardware in loop vehicle simulator in Warren, Michigan that provides the driver with realistic power response from the Power and Energy Systems Integration Lab over the internet.
Early Impacts of a Human-in-the-Loop Evaluation in a Space Vehicle Mock-up Facility
NASA Technical Reports Server (NTRS)
Byrne, Vicky; Vos, Gordon; Whitmore, Mihriban
2008-01-01
The development of a new space vehicle, the Orion Crew Exploration Vehicle (CEV), provides Human Factors engineers an excellent opportunity to have an impact early in the design process. This case study highlights a Human-in-the-Loop (HITL) evaluation conducted in a Space Vehicle Mock-Up Facility and will describe the human-centered approach and how the findings are impacting design and operational concepts early in space vehicle design. The focus of this HITL evaluation centered on the activities that astronaut crewmembers would be expected to perform within the functional internal volume of the Crew Module (CM) of the space vehicle. The primary objective was to determine if there are aspects of a baseline vehicle configuration that would limit or prevent the performance of dynamically volume-driving activities (e.g. six crewmembers donning their suits in an evacuation scenario). A second objective was to step through concepts of operations for known systems and evaluate them in integrated scenarios. The functional volume for crewmember activities is closely tied to every aspect of system design (e.g. avionics, safety, stowage, seats, suits, and structural support placement). As this evaluation took place before the Preliminary Design Review of the space vehicle with some designs very early in the development, it was not meant to determine definitely that the crewmembers could complete every activity, but rather to provide inputs that could improve developing designs and concepts of operations definition refinement.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Stein, W.
The operation of the emergency core cooling system and its related steam-binding problems in pressurized water reactors is the subject of a cooperative study by the United States, Germany, and Japan. Lawrence Livermore Laboratory and EG and G, Inc., San Ramon Operations, are responsible for the design, hardware, and software of the 80.8-mm and 113-mm spool piece measurement systems for the German Primarkreislauf (PKL) Test Facility at Kraftwerk Union in Erlangen, West Germany. This work was done for the US Nuclear Regulatory Commission, Division of Reactor Safety Research, under its 3-D Technical Support and Instrumentation Program. Four instrumented spools capablemore » of measuring individual phase parameters in two-phase flows were constructed. Each spool contains a flow turbine, drag screen, three-beam densitometer, and pressure and temperature probes. A computerized data acquisition system is also provided to store and analyze data from the four spools. The four spools were shipped to the PKL Test Facility in West Germany for acceptance testing in a water-flow loop. Spool measurements of velocity and momentum flux were compared to the values obtained from an orifice meter installed in the loop piping system. The turbine flowmeter velocity data for all tests were within allowable tolerances. Drag screen momentum flux measurements were also within tolerance with the exception of a few points.« less
Energy Systems Integration News | Energy Systems Integration Facility |
photovoltaic (PV) energy for its power. PV inverter hardware-in the loop testing was conducted at NREL's Energy -scale power-hardware-in-the-loop testing at the ESIF, which allows researchers and manufacturers to test field. In addition, the CGI provides hardware-in-the-loop capability combined with NWTC dynamometers
Microgrids | Energy Systems Integration Facility | NREL
Manager, Marine Corps Air Station (MCAS) Miramar Network Simulator-in-the-Loop Testing OMNeT++: simulates a network and links with real computers and virtual hosts. Power Hardware-in-the-Loop Simulation
Credit PSR. The flammable waste materials shed appears as seen ...
Credit PSR. The flammable waste materials shed appears as seen when looking south (186°) from South Liquid Loop Road. Note the catch basin for retaining accidentally spilled substances. Wastes are stored in drums and other safety containers until disposal by burning at the Incinerator (4249/E-50) or by other means. Note the nearby sign warning of corrosive, flammable materials, and calling attention to a fire extinguisher; a telephone is provided to call for assistance in the event of an emergency. This structure is isolated to prevent the spread of fire, and it is lightly built so damage from a fire will be inexpensive to repair - Jet Propulsion Laboratory Edwards Facility, Waste Flammable Storage Building, Edwards Air Force Base, Boron, Kern County, CA
Federal Register 2010, 2011, 2012, 2013, 2014
2011-07-19
... DEPARTMENT OF ENERGY DOE Response to Recommendation 2011-1 of the Defense Nuclear Facilities... Nuclear Facilities Safety Board, Office of Health, Safety and Security, U.S. Department of Energy, 1000... Department of Energy (DOE) acknowledges receipt of Defense Nuclear Facilities Safety Board (Board...
Vehicle Thermal Management Facilities | Transportation Research | NREL
Management Facilities Vehicle Thermal Management Facilities Image of a building with two semi truck evaluation facilities to develop advanced thermal management technologies for vehicles. Vehicle Testing and apparatus. Combined fluid loops bench research apparatus in the Vehicle Thermal Management Laboratory. Photo
Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-19
... Chemical Facility Safety and Security Listening Sessions AGENCY: National Protection and Programs... from stakeholders on issues pertaining to Improving Chemical Facility Safety and Security (Executive... regulations, guidance, and policies; and identifying best practices in chemical facility safety and security...
DOE Office of Scientific and Technical Information (OSTI.GOV)
Chatterton, Mike
The Recovery Act: Districtwide Geothermal Heating Conversion project performed by the Blaine County School District was part of a larger effort by the District to reduce operating costs, address deferred maintenance items, and to improve the learning environment of the students. This project evaluated three options for the ground source which were Open-Loop Extraction/Re-injection wells, Closed-Loop Vertical Boreholes, and Closed-Loop Horizontal Slinky approaches. In the end the Closed-Loop Horizontal Slinky approach had the lowest total cost of ownership but the majority of the sites associated with this project did not have enough available ground area to install the system somore » the second lowest option was used (Open-Loop). In addition to the ground source, this project looked at ways to retrofit existing HVAC systems with new high efficiency systems. The end result was the installation of distributed waterto- air heat pumps with water-to-water heat pumps installed to act as boilers/chillers for areas with a high ventilation demand such as they gymnasiums. A number of options were evaluated and the lowest total cost of ownership approach was implemented in the majority of the facilities. The facilities where the lowest total cost of ownership approaches was not selected were done to maintain consistency of the systems from facility to facility. This project had a number of other benefits to the Blaine County public. The project utilizes guaranteed energy savings to justify the levy funds expended. The project also developed an educational dashboard that can be used in the classrooms and to educate the community on the project and its performance. In addition, the majority of the installation work was performed by contractors local to Blaine County which acted as an economic stimulus to the area during a period of recession.« less
Advantages of cryopumping with liquid hydrogen instead of helium refrigerators
NASA Technical Reports Server (NTRS)
Anderson, J. W.; Tueller, J. E.
1972-01-01
Open loop hydrogen vaporizers and helium refrigerators are compared for operational complexity, installation and operating cost, and safety requirements. Data from two vacuum chambers using helium refrigerators are used to provide comparative data. In general, the use of hydrogen is attractive in the larger systems, even when extra safety precautions are taken. Emotional resistance to the use of hydrogen because of safety requirements is considered great. However, the experience gained in the handling of large quantities of cryogenics, particularly hydrogen and liquefied natural gases, should be considered in the design of open loop hydrogen cooling systems.
Take a Ride Along NIF’s Optics Recycle Loop
DOE Office of Scientific and Technical Information (OSTI.GOV)
Bouthillier, Lauren; Folta, Jim; Welday, Brian
The National Ignition Facility uses over 40,000 optics to help guide 192 laser beams onto a target the size of a pencil eraser. Check out how the optics recycle loop repairs optics, saving time and money.
77 FR 51943 - Procedures for Safety Investigations
Federal Register 2010, 2011, 2012, 2013, 2014
2012-08-28
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1708 Procedures for Safety Investigations AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Proposed rule; extension of comment period. SUMMARY: The Defense Nuclear Facilities Safety Board is extending the time for comments on its proposed...
Federal Register 2010, 2011, 2012, 2013, 2014
2013-02-21
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Public Availability of Defense Nuclear Facilities Safety Board FY 2011 Service Contract Inventory Analysis/FY 2012 Service Contract Inventory AGENCY: Defense Nuclear Facilities Safety Board (DNFSB). ACTION: Notice of Public Availability of FY 2011 Service Contract...
Federal Register 2010, 2011, 2012, 2013, 2014
2011-01-31
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Public Availability of Defense Nuclear Facilities Safety Board FY 2010 Service Contract Inventory AGENCY: Defense Nuclear Facilities Safety Board (Board). ACTION: Notice of public availability of FY 2010 Service Contract Inventories. SUMMARY: In accordance with...
Federal Register 2010, 2011, 2012, 2013, 2014
2012-02-10
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Public Availability of Defense Nuclear Facilities Safety Board; FY 2010 Service Contract Inventory Analysis/FY 2011 Service Contract Inventory AGENCY: Defense Nuclear Facilities Safety Board (DNFSB). ACTION: Notice of Public Availability of FY 2010 Service Contract...
Dual-mode capability for hardware-in-the-loop
NASA Astrophysics Data System (ADS)
Vamivakas, A. N.; Jackson, Ron L.
2000-07-01
This paper details a Hardware-in-the-Loop Facility (HIL) developed for evaluation and verification of a missile system with dual mode capability. The missile has the capability of tracking and intercepting a target using either an RF antenna or an IR sensor. The testing of a dual mode system presents a significant challenge in the development of the HIL facility. An IR and RF target environment must be presented simultaneously to the missile under test. These targets, simulated by IR and RF sources, must be presented to the missile under test without interference from each other. The location of each source is critical in the development of the HIL facility. The requirements for building a HIL facility with dual mode capability and the methodology for testing the dual mode system are defined within this paper. Methods for the verification and validation of the facility are discussed.
LOOP marine and estuarine monitoring program, 1978-95 : volume 6 : sediment quality.
DOT National Transportation Integrated Search
1998-01-01
The Louisiana Offshore Oil Port (LOOP) facilities in coastal Louisiana provide the United States with the country's only Superport for off-loading deep draft tankers. Sediment samples were collected quarterly from 1970 through 1995 at designated stat...
Trullàs, Joan Carles; Morales-Rull, José Luís; Casado, Jesús; Freitas Ramírez, Adriana; Manzano, Luís; Formiga, Francesc
2016-07-01
Fluid overload refractory to loop diuretic therapy can complicate acute or chronic heart failure (HF) management. The Safety and Efficacy of the Combination of Loop with Thiazide-type Diuretics in Patients with Decompensated Heart Failure (CLOROTIC) trial (Clinicaltrials.gov identifier NCT01647932) will test the hypothesis that blocking distal tubule sodium reabsorption with hydrochlorothiazide can antagonize the renal adaptation to chronic loop diuretic therapy and improve diuretic resistance. CLOROTIC is a randomized, placebo-controlled, double-blind, multicenter study. Three hundred and four patients with decompensated HF will be randomly assigned to receive hydrochlorothiazide or placebo in addition to a furosemide regimen. The main inclusion criteria are: age ≥18 years, history of chronic HF (irrespective of etiology and/or ejection fraction), admission for acute decompensation, and previous treatment with an oral loop diuretic for at least 1 month before randomization. The 2 coprimary endpoints are changes in body weight and changes in patient-reported dyspnea during hospital admission. Morbidity, mortality, and safety aspects will also be addressed. CLOROTIC is the first large-scale trial to evaluate whether the addition of a thiazide diuretic (hydrochlorothiazide) to a loop diuretic (furosemide) is a safe and effective strategy for improving congestive symptoms resulting from HF. This trial will provide important information and will therefore have a major impact on treatment strategies and future trials in these patients. Copyright © 2015 Elsevier Inc. All rights reserved.
Guide for Maintaining Pedestrian Facilities for Enhanced Safety.
DOT National Transportation Integrated Search
2013-10-01
A Guide for Maintaining Pedestrian Facilities for Enhanced Safety provides guidance for maintaining pedestrian facilities with the primary goal of increasing safety and mobility. The Guide addresses the needs for pedestrian facility maintenance; comm...
76 FR 26716 - Sunshine Act Meeting
Federal Register 2010, 2011, 2012, 2013, 2014
2011-05-09
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting AGENCY: Defense Nuclear Facilities... Defense Nuclear Facilities Safety Board's (Board) public meeting and hearing. FEDERAL REGISTER CITATIONS... Defense Nuclear Facilities Safety Board, Public Hearing Room, 625 Indiana Avenue, NW., Suite 300...
Review of hardware-in-the-loop simulation and its prospects in the automotive area
NASA Astrophysics Data System (ADS)
Fathy, Hosam K.; Filipi, Zoran S.; Hagena, Jonathan; Stein, Jeffrey L.
2006-05-01
Hardware-in-the-loop (HIL) simulation is rapidly evolving from a control prototyping tool to a system modeling, simulation, and synthesis paradigm synergistically combining many advantages of both physical and virtual prototyping. This paper provides a brief overview of the key enablers and numerous applications of HIL simulation, focusing on its metamorphosis from a control validation tool into a system development paradigm. It then describes a state-of-the art engine-in-the-loop (EIL) simulation facility that highlights the use of HIL simulation for the system-level experimental evaluation of powertrain interactions and development of strategies for clean and efficient propulsion. The facility comprises a real diesel engine coupled to accurate real-time driver, driveline, and vehicle models through a highly responsive dynamometer. This enables the verification of both performance and fuel economy predictions of different conventional and hybrid powertrains. Furthermore, the facility can both replicate the highly dynamic interactions occurring within a real powertrain and measure their influence on transient emissions and visual signature through state-of-the-art instruments. The viability of this facility for integrated powertrain system development is demonstrated through a case study exploring the development of advanced High Mobility Multipurpose Wheeled Vehicle (HMMWV) powertrains.
2004-01-01
Defense Nuclear Facilities Safety Board 1 0.2 Export-Import Bank 1 0.2 National Archives and Records Administration 1 0.2 Supreme Court of the United...Agency Commodity Futures Trading Commission Consumer Product Safety Commission Defense Nuclear Facilities Safety Board Environmental Protection Agency...Intelligence www.cia.gov Defense Nuclear Facilities Safety Board Defense Nuclear Facilities Safety Board www.dnfsb.gov Department of
LOOP marine and estuarine monitoring program, 1978-95 : volume 4 : zooplankton and ichthyoplankton.
DOT National Transportation Integrated Search
1998-01-01
The Louisiana Offshore Oil Port (LOOP) facilities in coastal Louisiana provide the United States with the country's only Superport for off-loading deep draft tankers. The three single-point mooring (SPM) structures connected by pipelines to a platfor...
Hypersonic Threats to the Homeland
2017-03-28
facilities. This defensive grid initiative can help stimulate R&D for hyper loop transportation and high speed railways for the aging infrastructure...Observe, Orient, Decide, Act (OODA) loop . In a tactical situation a warfighter makes decisions as he or she observes the environment; then the
NaK loop testing of thermoelectric converter modules (SNAP program)
NASA Technical Reports Server (NTRS)
Johnson, J. L.
1973-01-01
The history of testing of compact tubular modules in flowing NaK loops is summarized. Test procedures, data handling, and instrument calibration are discussed. Also included is descriptive information of the test facilities, operational problems encountered, and some recommendations for testing.
Federal Register 2010, 2011, 2012, 2013, 2014
2010-11-30
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD [Recommendation 2010-1] Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers AGENCY: Defense Nuclear Facilities Safety Board... Nuclear Facilities Safety Board has made a recommendation to the Secretary of Energy requesting an...
75 FR 56080 - Sunshine Act Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2010-09-15
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... Facilities Safety Board's public hearing and meeting. FEDERAL REGISTER CITATION OF PREVIOUS ANNOUNCEMENT: 75... INFORMATION: Brian Grosner, General Manager, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...
78 FR 4393 - Sunshine Act Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2013-01-22
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... given of the Defense Nuclear Facilities Safety Board's (Board) public meeting and hearing described... Session II, the Board will receive testimony concerning safety at Pantex defense nuclear facilities. The...
The Prevalence and Use of Walking Loops in Neighborhood Parks: A National Study.
Cohen, Deborah A; Han, Bing; Evenson, Kelly R; Nagel, Catherine; McKenzie, Thomas L; Marsh, Terry; Williamson, Stephanie; Harnik, Peter
2017-02-01
Previous studies indicate that the design of streets and sidewalks can influence physical activity among residents. Park features also influence park use and park-based physical activity. Although individuals can walk on streets and sidewalks, walking loops in parks offer a setting to walk in nature and to avoid interruptions from traffic. Here we describe the use of walking loops in parks and compare the number of park users and their physical activity in urban neighborhood parks with and without walking loops. We analyzed data from the National Study of Neighborhood Parks in which a representative sample of neighborhood parks (n = 174) from 25 U.S. cities with > 100,000 population were observed systematically to document facilities and park users by age group and sex. We compared the number of people and their physical activity in parks with and without walking loops, controlling for multiple factors, including park size, facilities, and population density. Overall, compared with parks without walking loops, on average during an hourly observation, parks with walking loops had 80% more users (95% CI: 42, 139%), and levels of moderate-to-vigorous physical activity were 90% higher (95% CI: 49, 145%). The additional park use and park-based physical activity occurred not only on the walking loops but throughout the park. Walking loops may be a promising means of increasing population level physical activity. Further studies are needed to confirm a causal relationship. Citation: Cohen DA, Han B, Evenson KR, Nagel C, McKenzie TL, Marsh T, Williamson S, Harnik P. 2017. The prevalence and use of walking loops in neighborhood parks: a national study. Environ Health Perspect 125:170-174; http://dx.doi.org/10.1289/EHP293.
The Prevalence and Use of Walking Loops in Neighborhood Parks: A National Study
Cohen, Deborah A.; Han, Bing; Evenson, Kelly R.; Nagel, Catherine; McKenzie, Thomas L.; Marsh, Terry; Williamson, Stephanie; Harnik, Peter
2016-01-01
Background: Previous studies indicate that the design of streets and sidewalks can influence physical activity among residents. Park features also influence park use and park-based physical activity. Although individuals can walk on streets and sidewalks, walking loops in parks offer a setting to walk in nature and to avoid interruptions from traffic. Objectives: Here we describe the use of walking loops in parks and compare the number of park users and their physical activity in urban neighborhood parks with and without walking loops. Methods: We analyzed data from the National Study of Neighborhood Parks in which a representative sample of neighborhood parks (n = 174) from 25 U.S. cities with > 100,000 population were observed systematically to document facilities and park users by age group and sex. We compared the number of people and their physical activity in parks with and without walking loops, controlling for multiple factors, including park size, facilities, and population density. Results: Overall, compared with parks without walking loops, on average during an hourly observation, parks with walking loops had 80% more users (95% CI: 42, 139%), and levels of moderate-to-vigorous physical activity were 90% higher (95% CI: 49, 145%). The additional park use and park-based physical activity occurred not only on the walking loops but throughout the park. Conclusions: Walking loops may be a promising means of increasing population level physical activity. Further studies are needed to confirm a causal relationship. Citation: Cohen DA, Han B, Evenson KR, Nagel C, McKenzie TL, Marsh T, Williamson S, Harnik P. 2017. The prevalence and use of walking loops in neighborhood parks: a national study. Environ Health Perspect 125:170–174; http://dx.doi.org/10.1289/EHP293 PMID:27517530
NASA Technical Reports Server (NTRS)
1979-01-01
The safety of NASA's in house microelectronics facility is addressed. Industrial health standards, facility emission control requirements, operation and safety checklists, and the disposal of epitaxial vent gas are considered.
Multiphase Flow Technology Impacts on Thermal Control Systems for Exploration
NASA Technical Reports Server (NTRS)
McQuillen, John; Sankovic, John; Lekan, Jack
2006-01-01
The Two-Phase Flow Facility (TPHIFFy) Project focused on bridging the critical knowledge gap by developing and demonstrating critical multiphase fluid products for advanced life support, thermal management and power conversion systems that are required to enable the Vision for Space Exploration. Safety and reliability of future systems will be enhanced by addressing critical microgravity fluid physics issues associated with flow boiling, condensation, phase separation, and system stability. The project included concept development, normal gravity testing, and reduced gravity aircraft flight campaigns, in preparation for the development of a space flight experiment implementation. Data will be utilized to develop predictive models that could be used for system design and operation. A single fluid, two-phase closed thermodynamic loop test bed was designed, assembled and tested. The major components in this test bed include: a boiler, a condenser, a phase separator and a circulating pump. The test loop was instrumented with flow meters, thermocouples, pressure transducers and both high speed and normal speed video cameras. A low boiling point surrogate fluid, FC-72, was selected based on scaling analyses using preliminary designs for operational systems. Preliminary results are presented which include flow regime transitions and some observations regarding system stability.
The Modern Integrated Anaesthesia Workstation
Patil, Vijaya P; Shetmahajan, Madhavi G; Divatia, Jigeeshu V
2013-01-01
Over the years, the conventional anaesthesia machine has evolved into an advanced carestation. The new machines use advanced electronics, software and technology to offer extensive capabilities for ventilation, monitoring, inhaled agent delivery, low-flow anaesthesia and closed-loop anaesthesia. They offer integrated monitoring and recording facilities and seamless integration with anaesthesia information systems. It is possible to deliver tidal volumes accurately and eliminate several hazards associated with the low pressure system and oxygen flush. Appropriate use can result in enhanced safety and ergonomy of anaesthetic delivery and monitoring. However, these workstations have brought in a new set of limitations and potential drawbacks. There are differences in technology and operational principles amongst the new workstations. Understand the principles of operation of these workstations and have a thorough knowledge of the operating manual of the individual machines. PMID:24249877
77 FR 479 - Sunshine Act Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2012-01-05
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... of the Defense Nuclear Facilities Safety Board's (Board) public hearing and meeting described below... Nuclear Facilities Safety Board, 625 Indiana Avenue NW., Suite 700, Washington, DC 20004-2901, (800) 788...
77 FR 48970 - Sunshine Act Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2012-08-15
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... given of the Defense Nuclear Facilities Safety Board's (Board) public meeting and hearing described... (NNSA) efforts to mitigate risks to public and worker safety posed by aging defense nuclear facilities...
Real-time range generation for ladar hardware-in-the-loop testing
NASA Astrophysics Data System (ADS)
Olson, Eric M.; Coker, Charles F.
1996-05-01
Real-time closed loop simulation of LADAR seekers in a hardware-in-the-loop facility can reduce program risk and cost. This paper discusses an implementation of real-time range imagery generated in a synthetic environment at the Kinetic Kill Vehicle Hardware-in-the Loop facility at Eglin AFB, for the stimulation of LADAR seekers and algorithms. The computer hardware platform used was a Silicon Graphics Incorporated Onyx Reality Engine. This computer contains graphics hardware, and is optimized for generating visible or infrared imagery in real-time. A by-produce of the rendering process, in the form of a depth buffer, is generated from all objects in view during its rendering process. The depth buffer is an array of integer values that contributes to the proper rendering of overlapping objects and can be converted to range values using a mathematical formula. This paper presents an optimized software approach to the generation of the scenes, calculation of the range values, and outputting the range data for a LADAR seeker.
Federal Register 2010, 2011, 2012, 2013, 2014
2013-02-12
... DEPARTMENT OF ENERGY DOE Response to Recommendation 2012-2 of the Defense Nuclear Facilities Safety Board, Hanford Tank Farms Flammable Gas Safety Strategy; Correction AGENCY: Department of Energy... Facilities Safety Board, Hanford Tank Farms Flammable Gas Safety Strategy. This document corrects an error in...
Federal Register 2010, 2011, 2012, 2013, 2014
2010-11-15
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD [Recommendation 2010-1] Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers AGENCY: Defense Nuclear Facilities Safety Board... Facilities Safety Board has made a recommendation to the Secretary of Energy requesting an amendment to the...
DOE Office of Scientific and Technical Information (OSTI.GOV)
Villanueva, J. F.; Carlos, S.; Martorell, S.
The loss of the residual heat removal system in mid-loop conditions may occur with a non-negligible contribution to the plant risk, so the analysis of the accidental sequences and the actions to mitigate the accident are of great interest in shutdown conditions. In order to plan the appropriate measures to mitigate the accident is necessary to understand the thermal-hydraulic processes following the loss of the residual heat removal system during shutdown. Thus, transients of this kind have been simulated using best-estimate codes in different integral test facilities and compared with experimental data obtained in different facilities. In PKL (Primaerkreislauf-Versuchsanlage, primarymore » coolant loop test facility) test facility different series of experiments have been undertaken to analyze the plant response in shutdown. In this context, the E3 and F2 series consist of analyzing the loss of the residual heat removal system with a reduced inventory in the primary system. In particular, the experiments were developed to investigate the influence of the steam generators secondary side configuration on the plant response, what involves the consideration of different number of steam generators filled with water and ready for activation, on the heat transfer mechanisms inside the steam generators U-tubes. This work presents the results of such experiments calculated using, RELAP5/Mod 3.3. (authors)« less
78 FR 48029 - Improving Chemical Facility Safety and Security
Federal Register 2010, 2011, 2012, 2013, 2014
2013-08-07
... responding to risks in chemical facilities (including during pre-inspection, inspection execution, post.... Sec. 2. Establishment of the Chemical Facility Safety and Security Working Group. (a) There is established a Chemical Facility Safety and Security Working Group (Working Group) co-chaired by the Secretary...
NASA Astrophysics Data System (ADS)
Bertani, C.; Falcone, N.; Bersano, A.; Caramello, M.; Matsushita, T.; De Salve, M.; Panella, B.
2017-11-01
High safety and reliability of advanced nuclear reactors, Generation IV and Small Modular Reactors (SMR), have a crucial role in the acceptance of these new plants design. Among all the possible safety systems, particular efforts are dedicated to the study of passive systems because they rely on simple physical principles like natural circulation, without the need of external energy source to operate. Taking inspiration from the second Decay Heat Removal system (DHR2) of ALFRED, the European Generation IV demonstrator of the fast lead cooled reactor, an experimental facility has been built at the Energy Department of Politecnico di Torino (PROPHET facility) to study single and two-phase flow natural circulation. The facility behavior is simulated using the thermal-hydraulic system code RELAP5-3D, which is widely used in nuclear applications. In this paper, the effect of the initial water inventory on natural circulation is analyzed. The experimental time behaviors of temperatures and pressures are analyzed. The experimental matrix ranges between 69 % and 93%; the influence of the opposite effects related to the increase of the volume available for the expansion and the pressure raise due to phase change is discussed. Simulations of the experimental tests are carried out by using a 1D model at constant heat power and fixed liquid and air mass; the code predictions are compared with experimental results. Two typical responses are observed: subcooled or two phase saturated circulation. The steady state pressure is a strong function of liquid and air mass inventory. The numerical results show that, at low initial liquid mass inventory, the natural circulation is not stable but pulsated.
75 FR 13433 - Safety Zone; Invista Inc Facility Docks, Victoria Barge Canal, Victoria, TX
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-22
...-AA00 Safety Zone; Invista Inc Facility Docks, Victoria Barge Canal, Victoria, TX AGENCY: Coast Guard... safety zone for a partial blockage of the Victoria Barge Canal when the Invista Inc facility is... channel will be substantially reduced. The safety zone is necessary to help ensure the safety of the...
Health and Safety Management for Small-scale Methane Fermentation Facilities
NASA Astrophysics Data System (ADS)
Yamaoka, Masaru; Yuyama, Yoshito; Nakamura, Masato; Oritate, Fumiko
In this study, we considered health and safety management for small-scale methane fermentation facilities that treat 2-5 ton of biomass daily based on several years operation experience with an approximate capacity of 5 t·d-1. We also took account of existing knowledge, related laws and regulations. There are no qualifications or licenses required for management and operation of small-scale methane fermentation facilities, even though rural sewerage facilities with a relative similar function are required to obtain a legitimate license. Therefore, there are wide variations in health and safety consciousness of the operators of small-scale methane fermentation facilities. The industrial safety and health laws are not applied to the operation of small-scale methane fermentation facilities. However, in order to safely operate a small-scale methane fermentation facility, the occupational safety and health management system that the law recommends should be applied. The aims of this paper are to clarify the risk factors in small-scale methane fermentation facilities and encourage planning, design and operation of facilities based on health and safety management.
NASA Astrophysics Data System (ADS)
Bocanegra-Bahamón, T. M.; Molera Calvés, G.; Gurvits, L. I.; Duev, D. A.; Pogrebenko, S. V.; Cimò, G.; Dirkx, D.; Rosenblatt, P.
2018-01-01
Context. Closed-loop Doppler data obtained by deep space tracking networks, such as the NASA Deep Space Network (DSN) and the ESA tracking station network (Estrack), are routinely used for navigation and science applications. By shadow tracking the spacecraft signal, Earth-based radio telescopes involved in the Planetary Radio Interferometry and Doppler Experiment (PRIDE) can provide open-loop Doppler tracking data only when the dedicated deep space tracking facilities are operating in closed-loop mode. Aims: We explain the data processing pipeline in detail and discuss the capabilities of the technique and its potential applications in planetary science. Methods: We provide the formulation of the observed and computed values of the Doppler data in PRIDE tracking of spacecraft and demonstrate the quality of the results using an experiment with the ESA Mars Express spacecraft as a test case. Results: We find that the Doppler residuals and the corresponding noise budget of the open-loop Doppler detections obtained with the PRIDE stations compare to the closed-loop Doppler detections obtained with dedicated deep space tracking facilities.
Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-27
... 1625-AA00 Safety Zones; Pacific Northwest Grain Handlers Association Facilities; Columbia and... establishing temporary safety zones around the following Pacific Northwest Grain Handlers Association... Commodities facility on the Willamette River in Portland, OR. These safety zones extend approximately between...
Overview of Energy Systems` safety analysis report programs. Safety Analysis Report Update Program
DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
1992-03-01
The primary purpose of an Safety Analysis Report (SAR) is to provide a basis for judging the adequacy of a facility`s safety. The SAR documents the safety analyses that systematically identify the hazards posed by the facility, analyze the consequences and risk of potential accidents, and describe hazard control measures that protect the health and safety of the public and employees. In addition, some SARs document, as Technical Safety Requirements (TSRs, which include Technical Specifications and Operational Safety Requirements), technical and administrative requirements that ensure the facility is operated within prescribed safety limits. SARs also provide conveniently summarized information thatmore » may be used to support procedure development, training, inspections, and other activities necessary to facility operation. This ``Overview of Energy Systems Safety Analysis Report Programs`` Provides an introduction to the programs and processes used in the development and maintenance of the SARs. It also summarizes some of the uses of the SARs within Energy Systems and DOE.« less
Make safety awareness a priority: Use a login software in your research facility
Camino, Fernando E.
2017-01-21
We report on a facility login software, whose objective is to improve safety in multi-user research facilities. Its most important safety features are: 1) blocks users from entering the lab after being absent for more than a predetermined number of days; 2) gives users a random safety quiz question, which they need to answer satisfactorily in order to use the facility; 3) blocks unauthorized users from using the facility afterhours; and 4) displays the current users in the facility. Besides restricting access to unauthorized users, the software keeps users mindful of key safety concepts. In addition, integration of the softwaremore » with a door controller system can convert it into an effective physical safety mechanism. Depending on DOE approval, the code may be available as open source.« less
Make safety awareness a priority: Use a login software in your research facility
DOE Office of Scientific and Technical Information (OSTI.GOV)
Camino, Fernando E.
We report on a facility login software, whose objective is to improve safety in multi-user research facilities. Its most important safety features are: 1) blocks users from entering the lab after being absent for more than a predetermined number of days; 2) gives users a random safety quiz question, which they need to answer satisfactorily in order to use the facility; 3) blocks unauthorized users from using the facility afterhours; and 4) displays the current users in the facility. Besides restricting access to unauthorized users, the software keeps users mindful of key safety concepts. In addition, integration of the softwaremore » with a door controller system can convert it into an effective physical safety mechanism. Depending on DOE approval, the code may be available as open source.« less
Functional safety for the Advanced Technology Solar Telescope
NASA Astrophysics Data System (ADS)
Bulau, Scott; Williams, Timothy R.
2012-09-01
Since inception, the Advanced Technology Solar Telescope (ATST) has planned to implement a facility-wide functional safety system to protect personnel from harm and prevent damage to the facility or environment. The ATST will deploy an integrated safety-related control system (SRCS) to achieve functional safety throughout the facility rather than relying on individual facility subsystems to provide safety functions on an ad hoc basis. The Global Interlock System (GIS) is an independent, distributed, facility-wide, safety-related control system, comprised of commercial off-the-shelf (COTS) programmable controllers that monitor, evaluate, and control hazardous energy and conditions throughout the facility that arise during operation and maintenance. The GIS has been designed to utilize recent advances in technology for functional safety plus revised national and international standards that allow for a distributed architecture using programmable controllers over a local area network instead of traditional hard-wired safety functions, while providing an equivalent or even greater level of safety. Programmable controllers provide an ideal platform for controlling the often complex interrelationships between subsystems in a modern astronomical facility, such as the ATST. A large, complex hard-wired relay control system is no longer needed. This type of system also offers greater flexibility during development and integration in addition to providing for expanded capability into the future. The GIS features fault detection, self-diagnostics, and redundant communications that will lead to decreased maintenance time and increased availability of the facility.
Federal Register 2010, 2011, 2012, 2013, 2014
2013-01-22
... DEPARTMENT OF ENERGY DOE Response to Recommendation 2012-2 of the Defense Nuclear Facilities Safety Board, Hanford Tank Farms Flammable Gas Safety Strategy AGENCY: Department of Energy. ACTION: Notice. SUMMARY: On September 28, 2012 the Defense Nuclear Facilities Safety Board submitted...
The Organization and Management of the Nuclear Weapons Program.
1997-03-01
over operations include the Defense Nuclear Facilities Safety Board, the Environmental Protection Agency, the Occupational Safety and Health...Safety, and Health. Still more guidance is received from the Defense Nuclear Facilities Safety Board and other external bodies such as the...state regulatory agencies, and the Defense Nuclear Facilities Safety Board. This chapter briefly reviews the most recent decade of this history, describes
Thermal Distribution System | Energy Systems Integration Facility | NREL
Thermal Distribution System Thermal Distribution System The Energy Systems Integration Facility's integrated thermal distribution system consists of a thermal water loop connected to a research boiler and . Photo of the roof of the Energy Systems Integration Facility. The thermal distribution bus allows
Stavropoulou, Charitini; Doherty, Carole; Tosey, Paul
2015-01-01
Context Incident-reporting systems (IRSs) are used to gather information about patient safety incidents. Despite the financial burden they imply, however, little is known about their effectiveness. This article systematically reviews the effectiveness of IRSs as a method of improving patient safety through organizational learning. Methods Our systematic literature review identified 2 groups of studies: (1) those comparing the effectiveness of IRSs with other methods of error reporting and (2) those examining the effectiveness of IRSs on settings, structures, and outcomes in regard to improving patient safety. We used thematic analysis to compare the effectiveness of IRSs with other methods and to synthesize what was effective, where, and why. Then, to assess the evidence concerning the ability of IRSs to facilitate organizational learning, we analyzed studies using the concepts of single-loop and double-loop learning. Findings In total, we identified 43 studies, 8 that compared IRSs with other methods and 35 that explored the effectiveness of IRSs on settings, structures, and outcomes. We did not find strong evidence that IRSs performed better than other methods. We did find some evidence of single-loop learning, that is, changes to clinical settings or processes as a consequence of learning from IRSs, but little evidence of either improvements in outcomes or changes in the latent managerial factors involved in error production. In addition, there was insubstantial evidence of IRSs enabling double-loop learning, that is, a cultural change or a change in mind-set. Conclusions The results indicate that IRSs could be more effective if the criteria for what counts as an incident were explicit, they were owned and led by clinical teams rather than centralized hospital departments, and they were embedded within organizations as part of wider safety programs. PMID:26626987
Launch Services Safety Overview
NASA Technical Reports Server (NTRS)
Loftin, Charles E.
2008-01-01
NASA/KSC Launch Services Division Safety (SA-D) services include: (1) Assessing the safety of the launch vehicle (2) Assessing the safety of NASA ELV spacecraft (S/C) / launch vehicle (LV) interfaces (3) Assessing the safety of spacecraft processing to ensure resource protection of: - KSC facilities - KSC VAFB facilities - KSC controlled property - Other NASA assets (4) NASA personnel safety (5) Interfacing with payload organizations to review spacecraft for adequate safety implementation and compliance for integrated activities (6) Assisting in the integration of safety activities between the payload, launch vehicle, and processing facilities
Safety and environmental aspects of organic coolants for fusion facilities
NASA Astrophysics Data System (ADS)
Natalizio, A.; Hollies, R. E.; Gierszewski, P.
1993-06-01
Organic coolants, such as OS-84, offer unique advantages for fusion reactor applications. These advantages are with respect to both reactor operation and safety. The key operational advantage is a coolant that can provide high temperature (350-400°C) at modest pressure (2-4 MPa). These temperatures are needed for conditioning the plasma-facing components and, in reactors, for achieving high thermodynamic conversion efficiencies (>40%). The key safety advantage of organic coolants is the low vapor pressure, which significantly reduces the containment pressurization transient (relative to water) following a loss of coolant event. Also, from an occupational dose viewpoint, organic coolants significantly reduce corrosion and erosion inside the cooling system and consequently reduce the quantity of activation products deposited in cooling system equipment. On the negative side, organic coolants undergo both pyrolytic and radiolytic decomposition, and are flammable. While the decomposition rate can be minimized by coolant system design (by reducing coolant inventories exposed to neutron flux and to high temperatures), decomposition products are formed and these degrade the coolant properties. Both heavy compounds and light gases are produced from the decomposition process, and both must be removed to maintain adequate coolant properties. As these hydrocarbons may become tritiated by permeation, or activated through impurities, their disposal could create an environmental concern. Because of this potential waste disposal problem, consideration has been given to the recycling of both the light and heavy products, thereby reducing the quantity of waste to be disposed. Preliminary assessments made for various fusion reactor designs, including ITER, suggest that it is feasible to use organic coolants for several applications. These applications range from first wall and blanket coolant (the most demanding with respect to decomposition), to shield and vacuum vessel cooling, to an intermediate cooling loop removing heat from a liquid metal loop and transferring it to a steam generator or heat exchanger.
Plant model of KIPT neutron source facility simulator
DOE Office of Scientific and Technical Information (OSTI.GOV)
Cao, Yan; Wei, Thomas Y.; Grelle, Austin L.
2016-02-01
Argonne National Laboratory (ANL) of the United States and Kharkov Institute of Physics and Technology (KIPT) of Ukraine are collaborating on constructing a neutron source facility at KIPT, Kharkov, Ukraine. The facility has 100-kW electron beam driving a subcritical assembly (SCA). The electron beam interacts with a natural uranium target or a tungsten target to generate neutrons, and deposits its power in the target zone. The total fission power generated in SCA is about 300 kW. Two primary cooling loops are designed to remove 100-kW and 300-kW from the target zone and the SCA, respectively. A secondary cooling system ismore » coupled with the primary cooling system to dispose of the generated heat outside the facility buildings to the atmosphere. In addition, the electron accelerator has a low efficiency for generating the electron beam, which uses another secondary cooling loop to remove the generated heat from the accelerator primary cooling loop. One of the main functions the KIPT neutron source facility is to train young nuclear specialists; therefore, ANL has developed the KIPT Neutron Source Facility Simulator for this function. In this simulator, a Plant Control System and a Plant Protection System were developed to perform proper control and to provide automatic protection against unsafe and improper operation of the facility during the steady-state and the transient states using a facility plant model. This report focuses on describing the physics of the plant model and provides several test cases to demonstrate its capabilities. The plant facility model uses the PYTHON script language. It is consistent with the computer language of the plant control system. It is easy to integrate with the simulator without an additional interface, and it is able to simulate the transients of the cooling systems with system control variables changing on real-time.« less
Commissioning of cryogenic system for China Spallation Neutron Source
NASA Astrophysics Data System (ADS)
Ye, Bin; He, Chongchao; Li, Na; Ding, Meiying; Wang, Yaqiong; Yu, Zhang; He, Kun
2017-12-01
China Spallation Neutron Source(CSNS) cryogenic system provides supercritical cryogenic hydrogen to neutron moderators, including a helium refrigerator, hydrogen loop and hydrogen safety equipment. The helium refrigerator is provided by Linde with cooling capacity of 2200 W at 20 K. Hydrogen loop system mainly includes cryogenic hydrogen pipes, hydrogen circulator cold-box and accumulator cold-box. Cryogenic hydrogen pump, ortho-para convertor, helium-hydrogen heat-exchanger, hydrogen heater and accumulator are integrated in hydrogen circulation cold-box, and accumulator cold-box. Hydrogen safety equipment includes safety valves, rupture disk, hydrogen sensor, flame detector and other equipment to ensure that cryogenic system in dangerous situations will go down, vents, or takes other measures. The cryogenic system commissioning work includes four steps. First, in order to test the refrigerating capacity of refrigerator, when acceptance testing, refrigerator internal heater was used as thermal load. Second, using simulation load as heat load of moderator, hydrogen loop use helium instead of hydrogen, and cooled down to 20 K, then re-warming and test the leak detection of hydrogen loop system. Third, base on the step 2, using hydrogen as working medium, and optimized the control logic. Forth, cryogenic system with the moderators joint commissioning. Now, cryogenic system is connected with the moderators, and the forth step will be carried out in the near future.
NREL Provides First-of-its-Kind Guidance Promoting Safety Standards for
Promoting Safety Standards for Natural Gas Vehicle Maintenance Facilities NREL Provides First-of-its-Kind Guidance Promoting Safety Standards for Natural Gas Vehicle Maintenance Facilities December 1, 2017 The U.S vehicle maintenance facilities with a new handbook and webinar that outline safety factors and standards
Federal Register 2010, 2011, 2012, 2013, 2014
2012-07-25
... DEPARTMENT OF ENERGY DOE Response to Recommendation 2012-1 of the Defense Nuclear Facilities Safety Board, Savannah River Site Building 235-F Safety AGENCY: Department of Energy. ACTION: Notice. SUMMARY: On May 8, 2012, the Defense Nuclear Facilities Safety Board submitted Recommendation 2012-1...
Nuclear Warheads: The Reliable Replacement Warhead Program and the Life Extension Program
2007-07-16
The Defense Nuclear Facilities Safety Board was created by Congress 1988 “as an independent oversight organization within the Executive Branch charged... nuclear facilities .” U.S. Defense Nuclear Facilities Safety Board. “Who We Are,” at [http://www.dnfsb.gov/about/index.html]. beginning, addressed safety...approach, if successful, would “reduce or eliminate the need for ESD controls.”55 Kent Fortenberry, Technical Director of the Defense Nuclear Facilities Safety
Smart Home Hardware-in-the-Loop Testing
DOE Office of Scientific and Technical Information (OSTI.GOV)
Pratt, Annabelle
This presentation provides a high-level overview of NREL's smart home hardware-in-the-loop testing. It was presented at the Fourth International Workshop on Grid Simulator Testing of Energy Systems and Wind Turbine Powertrains, held April 25-26, 2017, hosted by NREL and Clemson University at the Energy Systems Integration Facility in Golden, Colorado.
Linder, Deborah E; Siebens, Hannah C; Mueller, Megan K; Gibbs, Debra M; Freeman, Lisa M
2017-08-01
Animal-assisted intervention (AAI) programs are increasing in popularity, but it is unknown to what extent therapy animal organizations that provide AAI and the hospitals and eldercare facilities they work with implement effective animal health and safety policies to ensure safety of both animals and humans. Our study objective was to survey hospitals, eldercare facilities, and therapy animal organizations on their AAI policies and procedures. A survey of United States hospitals, eldercare facilities, and therapy animal organizations was administered to assess existing health and safety policies related to AAI programs. Forty-five eldercare facilities, 45 hospitals, and 27 therapy animal organizations were surveyed. Health and safety policies varied widely and potentially compromised human and animal safety. For example, 70% of therapy animal organizations potentially put patients at risk by allowing therapy animals eating raw meat diets to visit facilities. In general, hospitals had stricter requirements than eldercare facilities. This information suggests that there are gaps between the policies of facilities and therapy animal organizations compared with recent guidelines for animal visitation in hospitals. Facilities with AAI programs need to review their policies to address recent AAI guidelines to ensure the safety of animals and humans involved. Copyright © 2017 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Elsevier Inc. All rights reserved.
Mohammadpour, Atefeh; Anumba, Chimay J; Messner, John I
2016-07-01
There is a growing focus on enhancing energy efficiency in healthcare facilities, many of which are decades old. Since replacement of all aging healthcare facilities is not economically feasible, the retrofitting of these facilities is an appropriate path, which also provides an opportunity to incorporate energy efficiency measures. In undertaking energy efficiency retrofits, it is vital that the safety of the patients in these facilities is maintained or enhanced. However, the interactions between patient safety and energy efficiency have not been adequately addressed to realize the full benefits of retrofitting healthcare facilities. To address this, an innovative integrated framework, the Patient Safety and Energy Efficiency (PATSiE) framework, was developed to simultaneously enhance patient safety and energy efficiency. The framework includes a step -: by -: step procedure for enhancing both patient safety and energy efficiency. It provides a structured overview of the different stages involved in retrofitting healthcare facilities and improves understanding of the intricacies associated with integrating patient safety improvements with energy efficiency enhancements. Evaluation of the PATSiE framework was conducted through focus groups with the key stakeholders in two case study healthcare facilities. The feedback from these stakeholders was generally positive, as they considered the framework useful and applicable to retrofit projects in the healthcare industry. © The Author(s) 2016.
PIV Uncertainty Methodologies for CFD Code Validation at the MIR Facility
DOE Office of Scientific and Technical Information (OSTI.GOV)
Sabharwall, Piyush; Skifton, Richard; Stoots, Carl
2013-12-01
Currently, computational fluid dynamics (CFD) is widely used in the nuclear thermal hydraulics field for design and safety analyses. To validate CFD codes, high quality multi dimensional flow field data are essential. The Matched Index of Refraction (MIR) Flow Facility at Idaho National Laboratory has a unique capability to contribute to the development of validated CFD codes through the use of Particle Image Velocimetry (PIV). The significance of the MIR facility is that it permits non intrusive velocity measurement techniques, such as PIV, through complex models without requiring probes and other instrumentation that disturb the flow. At the heart ofmore » any PIV calculation is the cross-correlation, which is used to estimate the displacement of particles in some small part of the image over the time span between two images. This image displacement is indicated by the location of the largest peak. In the MIR facility, uncertainty quantification is a challenging task due to the use of optical measurement techniques. Currently, this study is developing a reliable method to analyze uncertainty and sensitivity of the measured data and develop a computer code to automatically analyze the uncertainty/sensitivity of the measured data. The main objective of this study is to develop a well established uncertainty quantification method for the MIR Flow Facility, which consists of many complicated uncertainty factors. In this study, the uncertainty sources are resolved in depth by categorizing them into uncertainties from the MIR flow loop and PIV system (including particle motion, image distortion, and data processing). Then, each uncertainty source is mathematically modeled or adequately defined. Finally, this study will provide a method and procedure to quantify the experimental uncertainty in the MIR Flow Facility with sample test results.« less
Safe design of healthcare facilities
Reiling, J
2006-01-01
The physical environment has a significant impact on health and safety; however, hospitals have not been designed with the explicit goal of enhancing patient safety through facility design. In April 2002, St Joseph's Community Hospital of West Bend, a member of SynergyHealth, brought together leaders in healthcare and systems engineering to develop a set of safety‐driven facility design recommendations and principles that would guide the design of a new hospital facility focused on patient safety. By introducing safety‐driven innovations into the facility design process, environmental designers and healthcare leaders will be able to make significant contributions to patient safety. PMID:17142606
76 FR 17627 - Sunshine Act Meeting Postponed
Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-30
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting Postponed AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice of public meeting postponement. SUMMARY: The Defense Nuclear Facilities Safety Board (Board) published a document in the Federal Register of March 3, 2011 (76 FR 11764...
77 FR 14007 - Sunshine Act Meeting Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2012-03-08
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting Notice Federal Register CITATION OF... THE MEETING: The Defense Nuclear Facilities Safety Board (Board) is expanding the matters to be.../ resolution of safety and technical issues across the defense nuclear facilities complex. Since this panel...
Improvements To Progressive Wave Tube Performance Through Closed-Loop Control
NASA Technical Reports Server (NTRS)
Rizzi, Stephen A.
2000-01-01
This report documents recent improvements to the acoustic and thermal control systems of the Thermal Acoustic Fatigue Apparatus (TAFA), a progressive wave tube test facility at the NASA Langley Research Center, Hampton, Virginia. A brief summary of past acoustic performance is given first to serve as a basis for comparison with the new performance data using a multiple-input, closed-loop, narrow-band controller. Performance data in the form of test section acoustic power spectral densities and coherence are presented in three of six facility configurations for a variety of input spectra. Tested spectra include uniform, two cases of pink noise, three cases of narrow-band random, a simulated launch payload bay environment for an expendable launch vehicle, and a simulated external acoustic load for the aft section of a reusable launch vehicle. In addition, a new closed-loop temperature controller and thermocouple data acquisition system are described.
Confinement of Radioactive Materials at Defense Nuclear Facilities
2004-10-01
The design of defense nuclear facilities includes systems whose reliable operation is vital to the protection of the public, workers, and the...final safety-class barrier to the release of hazardous materials with potentially serious public consequences. The Defense Nuclear Facilities Safety...the public at certain defense nuclear facilities . This change has resulted in downgrading of the functional safety classification of confinement
Fire safety of ground-based space facilities on the spaceport ;Vostochny;
NASA Astrophysics Data System (ADS)
Artamonov, Vladimir S.; Gordienko, Denis M.; Melikhov, Anatoly S.
2017-06-01
The facilities of the spaceport ;Vostochny; and the innovative technologies for fire safety to be implemented are considered. The planned approaches and prospects for fire safety ensuring at the facilities of the spaceport ;Vostochny; are presented herein, based on the study of emergency situations having resulted in fire accidents and explosion cases at the facilities supporting space vehicles operation.
A CLOSED-LOOP BIODIESEL PRODUCTION AND RESEARCH FACILITY IN KEENE, NH
The main objectives during Phase I were to continue a Biodiesel Working Group, formalize the organizational structure of the Monadnock Biodiesel Collaborative, identify a possible facility location, secure funding, provide novel curriculum for Keene State College students, and...
75 FR 27228 - Proposed FOIA Fee Schedule Update
Federal Register 2010, 2011, 2012, 2013, 2014
2010-05-14
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 Proposed FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice of proposed rulemaking. SUMMARY: Pursuant to 10 CFR 1703.107(b)(6) of the Board's regulations, the Defense Nuclear Facilities Safety Board is...
77 FR 41258 - FOIA Fee Schedule Update
Federal Register 2010, 2011, 2012, 2013, 2014
2012-07-13
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Establishment of FOIA Fee Schedule. SUMMARY: The Defense Nuclear Facilities Safety Board is publishing its Freedom of Information Act (FOIA) Fee Schedule Update pursuant to...
76 FR 28194 - Proposed FOIA Fee Schedule Update
Federal Register 2010, 2011, 2012, 2013, 2014
2011-05-16
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 Proposed FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice of proposed rulemaking. SUMMARY: Pursuant to 10 CFR 1703.107(b)(6) of the Board's regulations, the Defense Nuclear Facilities Safety Board is...
76 FR 43819 - FOIA Fee Schedule Update
Federal Register 2010, 2011, 2012, 2013, 2014
2011-07-22
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Establishment of FOIA Fee Schedule. SUMMARY: The Defense Nuclear Facilities Safety Board is publishing its Freedom of Information Act (FOIA) Fee Schedule Update pursuant to...
78 FR 20625 - Extension of Hearing Record Closure Date
Federal Register 2010, 2011, 2012, 2013, 2014
2013-04-05
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Extension of Hearing Record Closure Date AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Extension of hearing record closure date. SUMMARY: The Defense Nuclear Facilities Safety Board (Board) published a document in the Federal Register on January 22, 2013...
77 FR 65871 - Extension of Hearing Record Closure Date
Federal Register 2010, 2011, 2012, 2013, 2014
2012-10-31
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Extension of Hearing Record Closure Date AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Extension of hearing record closure date. SUMMARY: The Defense Nuclear Facilities Safety Board (Board) published a document in the Federal Register on August 15, 2012...
78 FR 1206 - Second Extension of Hearing Record Closure Date
Federal Register 2010, 2011, 2012, 2013, 2014
2013-01-08
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Second Extension of Hearing Record Closure Date AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Second extension of hearing record closure date. SUMMARY: The Defense Nuclear Facilities Safety Board (Board) published a document in the Federal Register on...
RELAP5 Analysis of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors
DOE Office of Scientific and Technical Information (OSTI.GOV)
Hongbin Zhang; Haihua Zhao; Cliff Davis
2008-06-01
An innovative hybrid loop-pool design for sodium cooled fast reactors (SFR-Hybrid) has been recently proposed. This design takes advantage of the inherent safety of a pool design and the compactness of a loop design to improve economics and safety of SFRs. In the hybrid loop-pool design, primary loops are formed by connecting the reactor outlet plenum (hot pool), intermediate heat exchangers (IHX), primary pumps and the reactor inlet plenum with pipes. The primary loops are immersed in the cold pool (buffer pool). Passive safety systems -- modular Pool Reactor Auxiliary Cooling Systems (PRACS) – are added to transfer decay heatmore » from the primary system to the buffer pool during loss of forced circulation (LOFC) transients. The primary systems and the buffer pool are thermally coupled by the PRACS, which is composed of PRACS heat exchangers (PHX), fluidic diodes and connecting pipes. Fluidic diodes are simple, passive devices that provide large flow resistance in one direction and small flow resistance in reverse direction. Direct reactor auxiliary cooling system (DRACS) heat exchangers (DHX) are immersed in the cold pool to transfer decay heat to the environment by natural circulation. To prove the design concepts, especially how the passive safety systems behave during transients such as LOFC with scram, a RELAP5-3D model for the hybrid loop-pool design was developed. The simulations were done for both steady-state and transient conditions. This paper presents the details of RELAP5-3D analysis as well as the calculated thermal response during LOFC with scram. The 250 MW thermal power conventional pool type design of GNEP’s Advanced Burner Test Reactor (ABTR) developed by Argonne National Laboratory was used as the reference reactor core and primary loop design. The reactor inlet temperature is 355 °C and the outlet temperature is 510 °C. The core design is the same as that for ABTR. The steady state buffer pool temperature is the same as the reactor inlet temperature. The peak cladding, hot pool, cold pool and reactor inlet temperatures were calculated during LOFC. The results indicate that there are two phases during LOFC transient – the initial thermal equilibration phase and the long term decay heat removal phase. The initial thermal equilibration phase occurs over a few hundred seconds, as the system adjusts from forced circulation to natural circulation flow. Subsequently, during long-term heat removal phase all temperatures evolve very slowly due to the large thermal inertia of the primary and buffer pool systems. The results clearly show that passive safety PRACS can effectively transfer decay heat from the primary system to the buffer pool by natural circulation. The DRACS system in turn can effectively transfer the decay heat to the environment.« less
Dynamics of safety performance and culture: a group model building approach.
Goh, Yang Miang; Love, Peter E D; Stagbouer, Greg; Annesley, Chris
2012-09-01
The management of occupational health and safety (OHS) including safety culture interventions is comprised of complex problems that are often hard to scope and define. Due to the dynamic nature and complexity of OHS management, the concept of system dynamics (SD) is used to analyze accident prevention. In this paper, a system dynamics group model building (GMB) approach is used to create a causal loop diagram of the underlying factors influencing the OHS performance of a major drilling and mining contractor in Australia. While the organization has invested considerable resources into OHS their disabling injury frequency rate (DIFR) has not been decreasing. With this in mind, rich individualistic knowledge about the dynamics influencing the DIFR was acquired from experienced employees with operations, health and safety and training background using a GMB workshop. Findings derived from the workshop were used to develop a series of causal loop diagrams that includes a wide range of dynamics that can assist in better understanding the causal influences OHS performance. The causal loop diagram provides a tool for organizations to hypothesize the dynamics influencing effectiveness of OHS management, particularly the impact on DIFR. In addition the paper demonstrates that the SD GMB approach has significant potential in understanding and improving OHS management. Copyright © 2011 Elsevier Ltd. All rights reserved.
78 FR 65978 - Draft Revised Strategic Plan for FY 2014-2018
Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-04
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Draft Revised Strategic Plan for FY 2014-2018 AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice. SUMMARY: In accordance with Office of Management and Budget Circular No. A-11, the Defense Nuclear Facilities Safety Board (DNFSB) is soliciting...
75 FR 4794 - Draft Revised Strategic Plan for FY 2010-2015
Federal Register 2010, 2011, 2012, 2013, 2014
2010-01-29
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Draft Revised Strategic Plan for FY 2010-2015 AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice. SUMMARY: In accordance with OMB Circular No. A-11, the Defense Nuclear Facilities Safety Board is soliciting comments from all interested and potentially...
NASA Technical Reports Server (NTRS)
Mccllough, J. R.; Sharpe, A.; Doetsch, K. H.
1980-01-01
The SIMFAC has played a vital role in the design, development, and performance verification of the shuttle remote manipulator system (SRMS) to be installed in the space shuttle orbiter. The facility provides for realistic man-in-the-loop operation of the SRMS by an operator in the operator complex, a flightlike crew station patterned after the orbiter aft flight deck with all necessary man machine interface elements, including SRMS displays and controls and simulated out-of-the-window and CCTV scenes. The characteristics of the manipulator system, including arm and joint servo dynamics and control algorithms, are simulated by a comprehensive mathematical model within the simulation subsystem of the facility. Major studies carried out using SIMFAC include: SRMS parameter sensitivity evaluations; the development, evaluation, and verification of operating procedures; and malfunction simulation and analysis of malfunction performance. Among the most important and comprehensive man-in-the-loop simulations carried out to date on SIMFAC are those which support SRMS performance verification and certification when the SRMS is part of the integrated orbiter-manipulator system.
Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-19
...-diameter Diamond Valley Ranch Loop pipeline; (2) an approximately 22-foot-wide by 35-foot-long powerhouse... the 18-inch-diameter Diamond Valley Ranch Loop; and (4) appurtenant facilities. The proposed project..., canal, Y pipeline, aqueduct, flume, ditch, or similar manmade water conveyance that is operated for the...
DOE Office of Scientific and Technical Information (OSTI.GOV)
None, None
2004-02-28
The Department of Energy (Department) submits an Annual Report to Congress each year detailing the Department’s activities relating to the Defense Nuclear Facilities Safety Board (Board), which provides advice and recommendations to the Secretary of Energy (Secretary) regarding public health and safety issues at the Department’s defense nuclear facilities. In 2003, the Department continued ongoing activities to resolve issues identified by the Board in formal recommendations and correspondence, staff issue reports pertaining to Department facilities, and public meetings and briefings. Additionally, the Department is implementing several key safety initiatives to address and prevent safety issues: safety culture and review ofmore » the Columbia accident investigation; risk reduction through stabilization of excess nuclear materials; the Facility Representative Program; independent oversight and performance assurance; the Federal Technical Capability Program (FTCP); executive safety initiatives; and quality assurance activities. The following summarizes the key activities addressed in this Annual Report.« less
Federal Register 2010, 2011, 2012, 2013, 2014
2010-10-29
... operation of facilities, infrastructure, and equipment for use by DoD military or civilian should be...-7004, Safety of Facilities, Infrastructure, and Equipment for Military Operations. DFARS 246.270-1... operation of facilities. This includes contracts for facilities, infrastructure, and equipment configured...
48 CFR 252.246-7004 - Safety of Facilities, Infrastructure, and Equipment for Military Operations.
Code of Federal Regulations, 2011 CFR
2011-10-01
...: SAFETY OF FACILITIES, INFRASTRUCTURE, AND EQUIPMENT FOR MILITARY OPERATIONS (OCT 2010) (a) Definition... 48 Federal Acquisition Regulations System 3 2011-10-01 2011-10-01 false Safety of Facilities, Infrastructure, and Equipment for Military Operations. 252.246-7004 Section 252.246-7004 Federal Acquisition...
48 CFR 246.270 - Safety of facilities, infrastructure, and equipment for military operations.
Code of Federal Regulations, 2011 CFR
2011-10-01
... ASSURANCE Contract Quality Requirements 246.270 Safety of facilities, infrastructure, and equipment for... 48 Federal Acquisition Regulations System 3 2011-10-01 2011-10-01 false Safety of facilities, infrastructure, and equipment for military operations. 246.270 Section 246.270 Federal Acquisition Regulations...
Safety Information, Transportation & Public Facilities, State of Alaska
Department of Transportation & Public Facilities/ Safety Information Search DOT&PF State of Alaska DOT&PF> Safety Information DOT&PF Safety Information link to 511 511.alaska.gov - Traveler Information link to AHSO Alaska Highway Safety Office link to HSIP Highway Safety Improvement Program link to
Safety analysis, 200 Area, Savannah River Plant: Separations area operations
DOE Office of Scientific and Technical Information (OSTI.GOV)
Perkins, W.C.; Lee, R.; Allen, P.M.
1991-07-01
The nev HB-Line, located on the fifth and sixth levels of Building 221-H, is designed to replace the aging existing HB-Line production facility. The nev HB-Line consists of three separate facilities: the Scrap Recovery Facility, the Neptunium Oxide Facility, and the Plutonium Oxide Facility. There are three separate safety analyses for the nev HB-Line, one for each of the three facilities. These are issued as supplements to the 200-Area Safety Analysis (DPSTSA-200-10). These supplements are numbered as Sup 2A, Scrap Recovery Facility, Sup 2B, Neptunium Oxide Facility, Sup 2C, Plutonium Oxide Facility. The subject of this safety analysis, the, Plutoniummore » Oxide Facility, will convert nitrate solutions of {sup 238}Pu to plutonium oxide (PuO{sub 2}) powder. All these new facilities incorporate improvements in: (1) engineered barriers to contain contamination, (2) barriers to minimize personnel exposure to airborne contamination, (3) shielding and remote operations to decrease radiation exposure, and (4) equipment and ventilation design to provide flexibility and improved process performance.« less
DOE Office of Scientific and Technical Information (OSTI.GOV)
Perkins, M P; Ong, M M; Crull, E W
2009-07-21
During lightning strikes buildings and other structures can act as imperfect Faraday Cages, enabling electromagnetic fields to be developed inside the facilities. Some equipment stored inside these facilities may unfortunately act as antenna systems. It is important to have techniques developed to analyze how much voltage, current, or energy dissipation may be developed over valuable components. In this discussion we will demonstrate the modeling techniques used to accurately analyze a generic missile type weapons system as it goes through different stages of assembly. As work is performed on weapons systems detonator cables can become exposed. These cables will form differentmore » monopole and loop type antenna systems that must be analyzed to determine the voltages developed over the detonator regions. Due to the low frequencies of lightning pulses, a lumped element circuit model can be developed to help analyze the different antenna configurations. We will show an example of how numerical modeling can be used to develop the lumped element circuit models used to calculate voltage, current, or energy dissipated over the detonator region of a generic missile type weapons system.« less
Overview of Energy Systems' safety analysis report programs
DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
1992-03-01
The primary purpose of an Safety Analysis Report (SAR) is to provide a basis for judging the adequacy of a facility's safety. The SAR documents the safety analyses that systematically identify the hazards posed by the facility, analyze the consequences and risk of potential accidents, and describe hazard control measures that protect the health and safety of the public and employees. In addition, some SARs document, as Technical Safety Requirements (TSRs, which include Technical Specifications and Operational Safety Requirements), technical and administrative requirements that ensure the facility is operated within prescribed safety limits. SARs also provide conveniently summarized information thatmore » may be used to support procedure development, training, inspections, and other activities necessary to facility operation. This Overview of Energy Systems Safety Analysis Report Programs'' Provides an introduction to the programs and processes used in the development and maintenance of the SARs. It also summarizes some of the uses of the SARs within Energy Systems and DOE.« less
2016-05-04
This final rule will amend the fire safety standards for Medicare and Medicaid participating hospitals, critical access hospitals (CAHs), long-term care facilities, intermediate care facilities for individuals with intellectual disabilities (ICF-IID), ambulatory surgery centers (ASCs), hospices which provide inpatient services, religious non-medical health care institutions (RNHCIs), and programs of all-inclusive care for the elderly (PACE) facilities. Further, this final rule will adopt the 2012 edition of the Life Safety Code (LSC) and eliminate references in our regulations to all earlier editions of the Life Safety Code. It will also adopt the 2012 edition of the Health Care Facilities Code, with some exceptions.
33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.
Code of Federal Regulations, 2012 CFR
2012-07-01
... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false ExxonMobil Hoover Floating OCS... HOMELAND SECURITY (CONTINUED) OUTER CONTINENTAL SHELF ACTIVITIES SAFETY ZONES § 147.815 ExxonMobil Hoover Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos...
33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.
Code of Federal Regulations, 2011 CFR
2011-07-01
... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false ExxonMobil Hoover Floating OCS... HOMELAND SECURITY (CONTINUED) OUTER CONTINENTAL SHELF ACTIVITIES SAFETY ZONES § 147.815 ExxonMobil Hoover Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos...
33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.
Code of Federal Regulations, 2014 CFR
2014-07-01
... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false ExxonMobil Hoover Floating OCS... HOMELAND SECURITY (CONTINUED) OUTER CONTINENTAL SHELF ACTIVITIES SAFETY ZONES § 147.815 ExxonMobil Hoover Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos...
33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.
Code of Federal Regulations, 2013 CFR
2013-07-01
... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false ExxonMobil Hoover Floating OCS... HOMELAND SECURITY (CONTINUED) OUTER CONTINENTAL SHELF ACTIVITIES SAFETY ZONES § 147.815 ExxonMobil Hoover Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos...
Federal Register 2010, 2011, 2012, 2013, 2014
2011-04-13
.... FDA-2011-N-0251] FDA Food Safety Modernization Act: Focus on Preventive Controls for Facilities... comment. SUMMARY: The Food and Drug Administration (FDA) is announcing a public meeting entitled ``FDA... controls for facilities provisions of the recently enacted FDA Food Safety Modernization Act (FSMA). FDA is...
Open-Loop HIRF Experiments Performed on a Fault Tolerant Flight Control Computer
NASA Technical Reports Server (NTRS)
Koppen, Daniel M.
1997-01-01
During the third quarter of 1996, the Closed-Loop Systems Laboratory was established at the NASA Langley Research Center (LaRC) to study the effects of High Intensity Radiated Fields on complex avionic systems and control system components. This new facility provided a link and expanded upon the existing capabilities of the High Intensity Radiated Fields Laboratory at LaRC that were constructed and certified during 1995-96. The scope of the Closed-Loop Systems Laboratory is to place highly integrated avionics instrumentation into a high intensity radiated field environment, interface the avionics to a real-time flight simulation that incorporates aircraft dynamics, engines, sensors, actuators and atmospheric turbulence, and collect, analyze, and model aircraft performance. This paper describes the layout and functionality of the Closed-Loop Systems Laboratory, and the open-loop calibration experiments that led up to the commencement of closed-loop real-time flight experiments.
Distributed Simulation Testing for Weapons System Performance of the F/A-18 and AIM-120 AMRAAM
1998-01-01
Support Facility (WSSF) at China Lake, CA and the AIM-120 Hardware in the Loop (HWIL) laboratory at Point Mugu, CA. The link was established in response to...ROCKET MOTOR TARGET DETECTION (FUZE) SEEKERIASSEMBLYWAH D . ANTENN ’ A TRA-kN.SiV, ITfrER’I" ACTUATOR ELECTRONICS DATA LIX -K PARAMETERS ADIMI20AI AIMI...test series. 3.2 Hardware in the Loop : The AMRAAM Hardware-In-the- Loop (HWIL) lab located at the Naval Air Warfare Center in Point Mugu, CA provides
75 FR 43495 - Sunshine Act Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2010-07-26
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities..., structures, and components, and (5) safety-related design aspects of new facilities or modifications of existing facilities needed to deliver high-level waste feed. The Board will be prepared to accept any other...
Federal Register 2010, 2011, 2012, 2013, 2014
2010-12-10
... loop \\1\\ in Miami-Dade County, Florida. The project would also include the installation of a pig... loop allows more gas to be moved through the system. \\2\\ A ``pig'' is a tool that is inserted into and... purposes. A pig launcher is an aboveground facility where pigs are inserted into the pipeline. The general...
Effectiveness and safety of remote monitoring of patients with an implantable loop recorder.
Drak-Hernández, Yasmín; Toquero-Ramos, Jorge; Fernández, José M; Pérez-Pereira, Elena; Castro-Urda, Víctor; Fernández-Lozano, Ignacio
2013-12-01
Implantable loop recorders have proven efficacy in the study of patients with syncope and palpitations. Remote monitoring of patients with pacemakers and implantable cardioverter-defibrillators has been shown to be safe and effective. The purpose of this study was to analyze the safety and effectiveness of remote monitoring in patients with an implantable loop recorder. Retrospective observational study in which 109 patients with an implantable loop recorder were analyzed and 2 population groups were compared: 1 receiving conventional follow-up consisting of 3-monthly office visits (41 patients) and 1 with remote monitoring via monthly telephone transmissions and yearly visits (68 patients). The mean follow-up was 64 weeks (range, 0.57-164.57 weeks). The study analyzed diagnosis of a significant event, defined as any event that led to a therapeutic approach and explained the symptoms leading to the implant, as well as the mean time from implant to diagnosis and the specific treatment. A significant event was diagnosed in 82.6% of patients; of these, 54.4% had a normal electrocardiogram; 26.7%, asystole; 15.6%, tachycardia, and 3.3%, bradycardia. The mean time from implant to diagnosis was 260 days (range, 5-947 days) in conventional follow-up, compared with 56 days (range, 0-650 days) in patients with remote monitoring (P<.01), which led to targeted treatment in this group 187 days earlier, on average, with no secondary complications. Remote monitoring of patients with an implantable loop recorder can significantly shorten the time to diagnosis and targeted treatment, without adversely affecting patient safety. Copyright © 2013 Sociedad Española de Cardiología. Published by Elsevier Espana. All rights reserved.
An Overview of INEL Fusion Safety R&D Facilities
NASA Astrophysics Data System (ADS)
McCarthy, K. A.; Smolik, G. R.; Anderl, R. A.; Carmack, W. J.; Longhurst, G. R.
1997-06-01
The Fusion Safety Program at the Idaho National Engineering Laboratory has the lead for fusion safety work in the United States. Over the years, we have developed several experimental facilities to provide data for fusion reactor safety analyses. We now have four major experimental facilities that provide data for use in safety assessments. The Steam-Reactivity Measurement System measures hydrogen generation rates and tritium mobilization rates in high-temperature (up to 1200°C) fusion relevant materials exposed to steam. The Volatilization of Activation Product Oxides Reactor Facility provides information on mobilization and transport and chemical reactivity of fusion relevant materials at high temperature (up to 1200°C) in an oxidizing environment (air or steam). The Fusion Aerosol Source Test Facility is a scaled-up version of VAPOR. The ion-implanta-tion/thermal-desorption system is dedicated to research into processes and phenomena associated with the interaction of hydrogen isotopes with fusion materials. In this paper we describe the capabilities of these facilities.
Low Pressure Seeder Development for PIV in Large Scale Open Loop Wind Tunnels
NASA Astrophysics Data System (ADS)
Schmit, Ryan
2010-11-01
A low pressure seeding techniques have been developed for Particle Image Velocimetry (PIV) in large scale wind tunnel facilities was performed at the Subsonic Aerodynamic Research Laboratory (SARL) facility at Wright-Patterson Air Force Base. The SARL facility is an open loop tunnel with a 7 by 10 foot octagonal test section that has 56% optical access and the Mach number varies from 0.2 to 0.5. A low pressure seeder sprayer was designed and tested in the inlet of the wind tunnel. The seeder sprayer was designed to produce an even and uniform distribution of seed while reducing the seeders influence in the test section. ViCount Compact 5000 using Smoke Oil 180 was using as the seeding material. The results show that this low pressure seeder does produce streaky seeding but excellent PIV images are produced.
Code of Federal Regulations, 2014 CFR
2014-07-01
... 33 Navigation and Navigable Waters 2 2014-07-01 2014-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...
Code of Federal Regulations, 2013 CFR
2013-07-01
... 33 Navigation and Navigable Waters 2 2013-07-01 2013-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...
Code of Federal Regulations, 2010 CFR
2010-07-01
... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...
Code of Federal Regulations, 2012 CFR
2012-07-01
... 33 Navigation and Navigable Waters 2 2012-07-01 2012-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...
Code of Federal Regulations, 2011 CFR
2011-07-01
... 33 Navigation and Navigable Waters 2 2011-07-01 2011-07-01 false Safety Zone: Pacific Missile Range Facility (PMRF), Barking Sands, Island of Kauai, Hawaii. 165.1406 Section 165.1406 Navigation and... Areas Fourteenth Coast Guard District § 165.1406 Safety Zone: Pacific Missile Range Facility (PMRF...
33 CFR 147.815 - ExxonMobil Hoover Floating OCS Facility safety zone.
Code of Federal Regulations, 2010 CFR
2010-07-01
... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false ExxonMobil Hoover Floating OCS... Floating OCS Facility safety zone. (a) Description. The ExxonMobil Hoover Floating OCS Facility, Alaminos... (1640.4 feet) from each point on the structure's outer edge is a safety zone. (b) Regulation. No vessel...
Power Hardware-in-the-Loop (PHIL) Testing Facility for Distributed Energy Storage (Poster)
DOE Office of Scientific and Technical Information (OSTI.GOV)
Neubauer.J.; Lundstrom, B.; Simpson, M.
2014-06-01
The growing deployment of distributed, variable generation and evolving end-user load profiles presents a unique set of challenges to grid operators responsible for providing reliable and high quality electrical service. Mass deployment of distributed energy storage systems (DESS) has the potential to solve many of the associated integration issues while offering reliability and energy security benefits other solutions cannot. However, tools to develop, optimize, and validate DESS control strategies and hardware are in short supply. To fill this gap, NREL has constructed a power hardware-in-the-loop (PHIL) test facility that connects DESS, grid simulator, and load bank hardware to a distributionmore » feeder simulation.« less
Nuclear Warheads: The Reliable Replacement Warhead program and the Life Extension Program
2007-12-03
eliminate the need for ESD controls.”67 CRS-22 68 The Defense Nuclear Facilities Safety Board was created by Congress 1988 “as an independent oversight...public health and safety’ at DOE’s defense nuclear facilities .” U.S. Defense Nuclear Facilities Safety Board. “Who We Are,” at [http://www.dnfsb.gov...about/index.html]. 69 Personal communication, Kent Fortenberry, Technical Director, Defense Nuclear Facilities Safety Board, September 14, 2006. 70
Nuclear Warheads: The Reliable Replacement Warhead Program and the Life Extension Program
2007-04-04
Information provided by Pantex Plant, Sept. 19, 2006. 50 The Defense Nuclear Facilities Safety Board was created by Congress 1988 “as an independent...protection of public health and safety’ at DOE’s defense nuclear facilities .” U.S. Defense Nuclear Facilities Safety Board. “Who We Are,” at [http...www.dnfsb.gov/about/index.html]. 51 Personal communication, Kent Fortenberry, Technical Director, Defense Nuclear Facilities Safety Board, Sept. 14, 2006
2003-01-10
This final rule amends the fire safety standards for hospitals, long-term care facilities, intermediate care facilities for the mentally retarded, ambulatory surgery centers, hospices that provide inpatient services, religious nonmedical health care institutions, critical access hospitals, and Programs of All-Inclusive Care for the Elderly facilities. Further, this final rule adopts the 2000 edition of the Life Safety Code and eliminates references in our regulations to all earlier editions.
Recent Upgrades at the Safety and Tritium Applied Research Facility
DOE Office of Scientific and Technical Information (OSTI.GOV)
Cadwallader, Lee Charles; Merrill, Brad Johnson; Stewart, Dean Andrew
This paper gives a brief overview of the Safety and Tritium Applied Research (STAR) facility operated by the Fusion Safety Program (FSP) at the Idaho National Laboratory (INL). FSP researchers use the STAR facility to carry out experiments in tritium permeation and retention in various fusion materials, including wall armor tile materials. FSP researchers also perform other experimentation as well to support safety assessment in fusion development. This lab, in its present two-building configuration, has been in operation for over ten years. The main experiments at STAR are briefly described. This paper discusses recent work to enhance personnel safety atmore » the facility. The STAR facility is a Department of Energy less than hazard category 3 facility; the personnel safety approach calls for ventilation and tritium monitoring for radiation protection. The tritium areas of STAR have about 4 to 12 air changes per hour, with air flow being once through and then routed to the facility vent stack. Additional radiation monitoring has been installed to read the laboratory room air where experiments with tritium are conducted. These ion chambers and bubblers are used to verify that no significant tritium concentrations are present in the experiment rooms. Standby electrical power has been added to the facility exhaust blower so that proper ventilation will now operate during commercial power outages as well as the real-time tritium air monitors.« less
29 CFR 1926.959 - Lineman's body belts, safety straps, and lanyards.
Code of Federal Regulations, 2010 CFR
2010-07-01
... tool pockets. On shifting D belts, this measurement for pocket tabs shall be taken when the D ring section is centered. (3) A maximum of four (4) tool loops shall be so situated on the body belt that four... of tool loops, and any other attachments. (4) Suitable copper, steel, or equivalent liners shall be...
Health and safety programs for art and theater schools.
McCann, M
2001-01-01
A wide variety of health and safety hazards exist in schools and colleges of art and theater due to a lack of formal health and safety programs and a failure to include health and safety concerns during planning of new facilities and renovation of existing facilities. This chapter discusses the elements of a health and safety program as well as safety-related structural and equipment needs that should be in the plans for any school of art or theater. These elements include curriculum content, ventilation, storage, housekeeping, waste management, fire and explosion prevention, machine and tool safety, electrical safety, noise, heat stress, and life safety and emergency procedures and equipment. Ideally, these elements should be incorporated into the plans for any new facilities, but ongoing programs can also benefit from a review of existing health and safety programs.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Wichman, K.; Tsao, J.; Mayfield, M.
The regulatory application of leak before break (LBB) for operating and advanced reactors in the U.S. is described. The U.S. Nuclear Regulatory Commission (NRC) has approved the application of LBB for six piping systems in operating reactors: reactor coolant system primary loop piping, pressurizer surge, safety injection accumulator, residual heat removal, safety injection, and reactor coolant loop bypass. The LBB concept has also been applied in the design of advanced light water reactors. LBB applications, and regulatory considerations, for pressurized water reactors and advanced light water reactors are summarized in this paper. Technology development for LBB performed by the NRCmore » and the International Piping Integrity Research Group is also briefly summarized.« less
78 FR 49262 - Sunshine Act Meeting
Federal Register 2010, 2011, 2012, 2013, 2014
2013-08-13
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting AGENCY: Defense Nuclear Facilities... given of the Defense Nuclear Facilities Safety Board's (Board) public meeting and hearing described... associated with continued operation of aging defense nuclear [[Page 49263
76 FR 11339 - Update to NFPA 101, Life Safety Code, for State Home Facilities
Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-02
... DEPARTMENT OF VETERANS AFFAIRS 38 CFR Part 51 RIN 2900-AN59 Update to NFPA 101, Life Safety Code..., Life Safety Code. The change is designed to assure that State Home facilities meet current industry- wide standards regarding life safety and fire safety. DATES: Effective Date: This final rule is...
NASA Astrophysics Data System (ADS)
Arbeiter, Frederik; Baluc, Nadine; Favuzza, Paolo; Gröschel, Friedrich; Heidinger, Roland; Ibarra, Angel; Knaster, Juan; Kanemura, Takuji; Kondo, Hiroo; Massaut, Vincent; Saverio Nitti, Francesco; Miccichè, Gioacchino; O'hira, Shigeru; Rapisarda, David; Sugimoto, Masayoshi; Wakai, Eiichi; Yokomine, Takehiko
2018-01-01
As part of the engineering validation and engineering design activities (EVEDA) phase for the international fusion materials irradiation facility IFMIF, major elements of a lithium target facility and the test facility were designed, prototyped and validated. For the lithium target facility, the EVEDA lithium test loop was built at JAEA and used to test the stability (waves and long term) of the lithium flow in the target, work out the startup procedures, and test lithium purification and analysis. It was confirmed by experiments in the Lifus 6 plant at ENEA that lithium corrosion on ferritic martensitic steels is acceptably low. Furthermore, complex remote handling procedures for the remote maintenance of the target in the test cell environment were successfully practiced. For the test facility, two variants of a high flux test module were prototyped and tested in helium loops, demonstrating their good capabilities of maintaining the material specimens at the desired temperature with a low temperature spread. Irradiation tests were performed for heated specimen capsules and irradiation instrumentation in the BR2 reactor at SCK-CEN. The small specimen test technique, essential for obtaining material test results with limited irradiation volume, was advanced by evaluating specimen shape and test technique influences.
IFMIF: overview of the validation activities
NASA Astrophysics Data System (ADS)
Knaster, J.; Arbeiter, F.; Cara, P.; Favuzza, P.; Furukawa, T.; Groeschel, F.; Heidinger, R.; Ibarra, A.; Matsumoto, H.; Mosnier, A.; Serizawa, H.; Sugimoto, M.; Suzuki, H.; Wakai, E.
2013-11-01
The Engineering Validation and Engineering Design Activities (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF), an international collaboration under the Broader Approach Agreement between Japan Government and EURATOM, aims at allowing a rapid construction phase of IFMIF in due time with an understanding of the cost involved. The three main facilities of IFMIF (1) the Accelerator Facility, (2) the Target Facility and (3) the Test Facility are the subject of validation activities that include the construction of either full scale prototypes or smartly devised scaled down facilities that will allow a straightforward extrapolation to IFMIF needs. By July 2013, the engineering design activities of IFMIF matured with the delivery of an Intermediate IFMIF Engineering Design Report (IIEDR) supported by experimental results. The installation of a Linac of 1.125 MW (125 mA and 9 MeV) of deuterons started in March 2013 in Rokkasho (Japan). The world's largest liquid Li test loop is running in Oarai (Japan) with an ambitious experimental programme for the years ahead. A full scale high flux test module that will house ∼1000 small specimens developed jointly in Europe and Japan for the Fusion programme has been constructed by KIT (Karlsruhe) together with its He gas cooling loop. A full scale medium flux test module to carry out on-line creep measurement has been validated by CRPP (Villigen).
Suggestions for Layout and Functional Behavior of Software-Based Voice Switch Keysets
NASA Technical Reports Server (NTRS)
Scott, David W.
2010-01-01
Marshall Space Flight Center (MSFC) provides communication services for a number of real time environments, including Space Shuttle Propulsion support and International Space Station (ISS) payload operations. In such settings, control team members speak with each other via multiple voice circuits or loops. Each loop has a particular purpose and constituency, and users are assigned listen and/or talk capabilities for a given loop based on their role in fulfilling the purpose. A voice switch is a given facility's hardware and software that supports such communication, and may be interconnected with other facilities switches to create a large network that, from an end user perspective, acts like a single system. Since users typically monitor and/or respond to several voice loops concurrently for hours on end and real time operations can be very dynamic and intense, it s vital that a control panel or keyset for interfacing with the voice switch be a servant that reduces stress, not a master that adds it. Implementing the visual interface on a computer screen provides tremendous flexibility and configurability, but there s a very real risk of overcomplication. (Remember how office automation made life easier, which led to a deluge of documents that made life harder?) This paper a) discusses some basic human factors considerations related to keysets implemented as application software windows, b) suggests what to standardize at the facility level and what to leave to the user's preference, and c) provides screen shot mockups for a robust but reasonably simple user experience. Concepts apply to keyset needs in almost any type of operations control or support center.
30 CFR 75.1712-2 - Location of surface facilities.
Code of Federal Regulations, 2014 CFR
2014-07-01
... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Location of surface facilities. 75.1712-2...
30 CFR 75.1712-2 - Location of surface facilities.
Code of Federal Regulations, 2012 CFR
2012-07-01
... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Location of surface facilities. 75.1712-2...
30 CFR 75.1712-2 - Location of surface facilities.
Code of Federal Regulations, 2011 CFR
2011-07-01
... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Location of surface facilities. 75.1712-2...
30 CFR 75.1712-2 - Location of surface facilities.
Code of Federal Regulations, 2013 CFR
2013-07-01
... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Location of surface facilities. 75.1712-2...
30 CFR 75.1712-2 - Location of surface facilities.
Code of Federal Regulations, 2010 CFR
2010-07-01
... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Location of surface facilities. 75.1712-2... SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-2 Location of surface facilities. Bathhouses, change rooms, and sanitary toilet facilities shall be in a location...
Highway Safety Manual applied in Missouri - freeway/software.
DOT National Transportation Integrated Search
2016-06-01
AASHTOs Highway Safety Manual (HSM) facilitates the quantitative safety analysis of highway facilities. In a 2014 : supplement, freeway facilities were added to the original HSM manual which allows the modeling of highway : interchanges. This repo...
DOE Office of Scientific and Technical Information (OSTI.GOV)
Yoder Jr, Graydon L; Aaron, Adam M; Cunningham, Richard Burns
2014-01-01
The need for high-temperature (greater than 600 C) energy exchange and delivery systems is significantly increasing as the world strives to improve energy efficiency and develop alternatives to petroleum-based fuels. Liquid fluoride salts are one of the few energy transport fluids that have the capability of operating at high temperatures in combination with low system pressures. The Fluoride Salt-Cooled High-Temperature Reactor design uses fluoride salt to remove core heat and interface with a power conversion system. Although a significant amount of experimentation has been performed with these salts, specific aspects of this reactor concept will require experimental confirmation during themore » development process. The experimental facility described here has been constructed to support the development of the Fluoride Salt Cooled High Temperature Reactor concept. The facility is capable of operating at up to 700 C and incorporates a centrifugal pump to circulate FLiNaK salt through a removable test section. A unique inductive heating technique is used to apply heat to the test section, allowing heat transfer testing to be performed. An air-cooled heat exchanger removes added heat. Supporting loop infrastructure includes a pressure control system; trace heating system; and a complement of instrumentation to measure salt flow, temperatures, and pressures around the loop. The initial experiment is aimed at measuring fluoride salt heat transfer inside a heated pebble bed similar to that used for the core of the pebble bed advanced high-temperature reactor. This document describes the details of the loop design, auxiliary systems used to support the facility, the inductive heating system, and facility capabilities.« less
Surgeon Training in Telerobotic Surgery via a Hardware-in-the-Loop Simulator
Alemzadeh, Homa; Chen, Daniel; Kalbarczyk, Zbigniew; Iyer, Ravishankar K.; Kesavadas, Thenkurussi
2017-01-01
This work presents a software and hardware framework for a telerobotic surgery safety and motor skill training simulator. The aims are at providing trainees a comprehensive simulator for acquiring essential skills to perform telerobotic surgery. Existing commercial robotic surgery simulators lack features for safety training and optimal motion planning, which are critical factors in ensuring patient safety and efficiency in operation. In this work, we propose a hardware-in-the-loop simulator directly introducing these two features. The proposed simulator is built upon the Raven-II™ open source surgical robot, integrated with a physics engine and a safety hazard injection engine. Also, a Fast Marching Tree-based motion planning algorithm is used to help trainee learn the optimal instrument motion patterns. The main contributions of this work are (1) reproducing safety hazards events, related to da Vinci™ system, reported to the FDA MAUDE database, with a novel haptic feedback strategy to provide feedback to the operator when the underlying dynamics differ from the real robot's states so that the operator will be aware and can mitigate the negative impact of the safety-critical events, and (2) using motion planner to generate semioptimal path in an interactive robotic surgery training environment. PMID:29065635
SU-F-T-223: Radiotherapy Incident Reporting and Analysis System (RIRAS):Early Experience
DOE Office of Scientific and Technical Information (OSTI.GOV)
Kapoor, R; Palta, J; Hagan, M
Background & Purpose: RIRAS is a web-based information system deployed on the Veterans Health Administration intranet in early 2014 to collect adverse events and good catch data; analyze the causes and contributing factors; and find ways to prevent future occurrences. Material and Methods: Incident learning consists of a feedback loop which starts with reporting an event, followed by analysis of contributing factors, and culminates in the development of a patient safety work product (PSWP) to prevent recurrence. RIRAS permits both anonymous and non-anonymous reporting. Each report is analyzed by a team of medical physicists who are independent of the reportingmore » facility. The analysts usually contact the reporting facilities for additional information. We analyzed all reports and held telephonic interviews (when necessary) with the reporters. We then generated PSWPs with corrective/preventive and learning actions. Anonymous reporting is handled in the same manner, except without the ability to further interview the reporter. Results: In a significant number of reports, the causes and recommended preventive actions were considerably altered by the independent analysis and additional information from the facility. 130 reports have been entered in RIRAS; 9 misadministrations, 83 good catches, 3 anonymous good catches, and 35 earlier reported incidents from FY2005-14. 45% of the reported incidents occurred in the treatment delivery stages, 19% in on-treatment management, and 16% in pre-treatment verification. 80% of the good catches were found in the treatment delivery workflow. Majority of these incidents were due to inconsistent patient setup instructions or documentation, nonadherence to policies and procedures, lax time-out policy, distracted RTTs, and inadequate RTT staffing. Conclusion: RIRAS has identified many areas for improvement and elevated the quality and safety of radiation treatments in the VHA. We found that the ability to learn is significantly diminished when the analysts do not have the ability to request additional information.« less
Investigation of the factors responsible for burns during MRI.
Dempsey, M F; Condon, B; Hadley, D M
2001-04-01
Numerous reported burn injuries have been sustained during clinical MRI procedures. The aim of this study was to investigate the possible factors that may be responsible for such burns. Experiments were performed to investigate three possible mechanisms for causing heating in copper wire during MRI: direct electromagnetic induction in a conductive loop, induction in a resonant conducting loop, and electric field resonant coupling with a wire (the antenna effect). Maximum recorded temperature rises were 0.6 degrees C for the loop, 61.1 degrees C for the resonant loop, and 63.5 degrees C for the resonant antenna. These experimental findings suggest that, contrary to common belief, it is unlikely that direct induction in a conductive loop will result in thermal injury. Burn incidents are more likely to occur due to the formation of resonant conducting loops and from extended wires forming resonant antenna. The characteristics of resonance should be considered when formulating safety guidelines.
Safety analysis report for the Waste Storage Facility. Revision 2
DOE Office of Scientific and Technical Information (OSTI.GOV)
Bengston, S.J.
1994-05-01
This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.
The Phillips Laboratory capillary pumped loop test facility
NASA Astrophysics Data System (ADS)
Gluck, Donald F.; Kaylor, Marc C.
1996-03-01
An ammonia capillary pumped loop (CPL) test facility has been designed, fabricated, subject to acceptance tests, and assembled at Phillips Laboratory. Its intent is to support a wide range of Air Force programs, bringing CPL technology to flight readiness for operational systems. The facility provides a high degree of modularity and flexibility with several heating and cooling options, and capability for elevation (+/- 15 in.), tilt (+/-60°) and transport length variation. It has a 182 by 44 by 84 inch envelope, an expected heat load capability of 2500 W, and a temperature range of 0 to 50 °C. The evaporator section has two plates with four capillary pumps (CPs) each, with a starter pump on one plate. The CPs are 5/8 in., with TAG aluminum 6063-T6 casing and UHMW polyethylene wicks. The active lengths are 15 and 30 inch with both 10 and 15 micron wicks. The individual CPs have thermal and hydraulic isolation capability, and are removable. The transport section consists of stainless steel lines in a serpentine configuration, a 216 in3 free volume reservoir, and a mechanical pump. The vapor transport line contains a capillary device (which can be bypassed) for vapor blockage during startup. The condenser consists of two separately valved, parallel cold plates each with a downstream noncondensible gas trap. Cooling of up to 1500 W at -50 °C is provided by an FTS Systems chiller using Flourinert FC-72. An enclosure/exhaust system is provided for safety and emergency venting of ammonia. An ammonia charge station performs or supports the functions of proof pressure, flushing with ammonia, purging with gaseous nitrogen, evacuation of all or part of the CPL to 20 microns, and charging. Instrumentation consists of over 116 thermocouples, five of which are internal; one absolute and six differential pressure transducers; eleven watt transducers, and a reservoir load cell. The data acquisition system consists of a temperature scanner, Bernoulli drive, and two Macintosh computers using LabView software. Data scanning and storage as rapid as once every three seconds for thermocouples and once per 0.6 seconds for transducers is supported.
Federal Register 2010, 2011, 2012, 2013, 2014
2010-07-29
... Uranium Enrichment Fuel Cycle Facility Inspection Reports Regarding Louisiana Energy Services, National... Enrichment Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and... Enrichment Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and...
DOE Office of Scientific and Technical Information (OSTI.GOV)
Roussel, G.
Leak-Before-Break (LBB) technology has not been applied in the first design of the seven Pressurized Water Reactors the Belgian utility is currently operating. The design basis of these plants required to consider the dynamic effects associated with the ruptures to be postulated in the high energy piping. The application of the LBB technology to the existing plants has been recently approved by the Belgian Safety Authorities but with a limitation to the primary coolant loop. LBB analysis has been initiated for the Doel 3 and Tihange 2 plants to allow the withdrawal of some of the reactor coolant pump snubbersmore » at both plants and not reinstall some of the restraints after steam generator replacement at Doel 3. LBB analysis was also found beneficial to demonstrate the acceptability of the primary components and piping to the new conditions resulting from power uprating and stretch-out operation. LBB analysis has been subsequently performed on the primary coolant loop of the Tihange I plant and is currently being performed for the Doel 4 plant. Application of the LBB to the primary coolant loop is based in Belgium on the U.S. Nuclear Regulatory Commission requirements. However the Belgian Safety Authorities required some additional analyses and put some restrictions on the benefits of the LBB analysis to maintain the global safety of the plant at a sufficient level. This paper develops the main steps of the safety evaluation performed by the Belgian Safety Authorities for accepting the application of the LBB technology to existing plants and summarizes the requirements asked for in addition to the U.S. Nuclear Regulatory Commission rules.« less
Hendrieckx, Christel; Poole, Lucinda A; Sharifi, Amin; Jayawardene, Dilshani; Loh, Margaret M; Horsburgh, Jodie C; Bach, Leon A; Colman, Peter G; Kumareswaran, Kavita; Jenkins, Alicia J; MacIsaac, Richard J; Ward, Glenn M; Grosman, Benyamin; Roy, Anirban; O'Neal, David N; Speight, Jane
2017-07-01
This qualitative study explored trial participants' experiences of four nights of in-home closed loop. Sixteen adults with type 1 diabetes, who completed a randomized crossover trial, were interviewed after four consecutive nights of closed-loop. Interviews were audio recorded, transcribed, and analyzed with a coding framework developed to identify the main themes. Participants had a mean age of 42 ± 10 years, nine were women; mean diabetes duration was 27 ± 7 years, and all were using insulin pumps. Overall, first impressions were positive. Participants found closed-loop easy to use and understand. Most experienced more stable overnight glucose levels, although for some these were similar to usual care or higher than they expected. Compared with their usual treatment, they noticed the proactive nature of the closed-loop, being able to predict trends and deliver micro amounts of insulin. Most reported technical glitches or inconveniences during one or more nights, such as transmission problems, problematic connectivity between devices, ongoing alarms despite addressing low glucose levels, and sensor inaccuracy. Remote monitoring by the trial team and their own hypoglycemic awareness contributed to feelings of trust and safety. Although rare, safety concerns were raised, related to feeling unsure whether the system would respond in time to falling glucose levels. This study provides relevant insights for implementation of closed-loop in the real world. For people with diabetes who are less familiar with technology, remote monitoring for the first few days may provide reassurance, strengthen their trust/skills, and make closed-loop an acceptable option for more people with type 1 diabetes.
Many recent pilot tests have demonstrated the benefits and cost effectiveness of point-of-use treatment technologies as opposed to centralized wastewater treatment for all sizes of plating facilities. A 9-month case study at a small plating facility in Cincinnati, OH utilizing po...
Preliminary hazards analysis -- vitrification process
DOE Office of Scientific and Technical Information (OSTI.GOV)
Coordes, D.; Ruggieri, M.; Russell, J.
1994-06-01
This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility`s constructionmore » and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment.« less
30 CFR 71.400 - Bathing facilities; change rooms; sanitary flush toilet facilities.
Code of Federal Regulations, 2010 CFR
2010-07-01
... flush toilet facilities. 71.400 Section 71.400 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND SURFACE... installations and at the surface worksites of such mine. (Note: Sanitary facilities at surface work areas of...
49 CFR 193.2001 - Scope of part.
Code of Federal Regulations, 2010 CFR
2010-10-01
... Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES... LNG facilities used in the transportation of gas by pipeline that is subject to the pipeline safety...
Postirradiation Testing Laboratory (327 Building)
DOE Office of Scientific and Technical Information (OSTI.GOV)
Kammenzind, D.E.
A Standards/Requirements Identification Document (S/RID) is the total list of the Environment, Safety and Health (ES and H) requirements to be implemented by a site, facility, or activity. These requirements are appropriate to the life cycle phase to achieve an adequate level of protection for worker and public health and safety, and the environment during design, construction, operation, decontamination and decommissioning, and environmental restoration. S/RlDs are living documents, to be revised appropriately based on change in the site`s or facility`s mission or configuration, a change in the facility`s life cycle phase, or a change to the applicable standards/requirements. S/RIDs encompassmore » health and safety, environmental, and safety related safeguards and security (S and S) standards/requirements related to the functional areas listed in the US Department of Energy (DOE) Environment, Safety and Health Configuration Guide. The Fluor Daniel Hanford (FDH) Contract S/RID contains standards/requirements, applicable to FDH and FDH subcontractors, necessary for safe operation of Project Hanford Management Contract (PHMC) facilities, that are not the direct responsibility of the facility manager (e.g., a site-wide fire department). Facility S/RIDs contain standards/requirements applicable to a specific facility that are the direct responsibility of the facility manager. S/RlDs are prepared by those responsible for managing the operation of facilities or the conduct of activities that present a potential threat to the health and safety of workers, public, or the environment, including: Hazard Category 1 and 2 nuclear facilities and activities, as defined in DOE 5480.23. Selected Hazard Category 3 nuclear, and Low Hazard non-nuclear facilities and activities, as agreed upon by RL. The Postirradiation Testing Laboratory (PTL) S/RID contains standards/ requirements that are necessary for safe operation of the PTL facility, and other building/areas that are the direct responsibility of the specific facility manager. The specific DOE Orders, regulations, industry codes/standards, guidance documents and good industry practices that serve as the basis for each element/subelement are identified and aligned with each subelement.« less
Code of Federal Regulations, 2012 CFR
2012-04-01
... and public health and safety documentation regarding any gaming place, facility, or location where... environmental and public health and safety documentation regarding any gaming place, facility, or location where gaming will occur? A tribe shall provide Indian lands or environmental and public health and safety...
Code of Federal Regulations, 2010 CFR
2010-04-01
... and public health and safety documentation regarding any gaming place, facility, or location where... environmental and public health and safety documentation regarding any gaming place, facility, or location where gaming will occur? A tribe shall provide Indian lands or environmental and public health and safety...
Code of Federal Regulations, 2011 CFR
2011-04-01
... and public health and safety documentation regarding any gaming place, facility, or location where... environmental and public health and safety documentation regarding any gaming place, facility, or location where gaming will occur? A tribe shall provide Indian lands or environmental and public health and safety...
TREAT Neutronics Analysis of Water-Loop Concept Accommodating LWR 9-rod Bundle
DOE Office of Scientific and Technical Information (OSTI.GOV)
Hill, Connie M.; Woolstenhulme, Nicolas E.; Parry, James R.
Abstract. Simulation of a variety of transient conditions has been successfully achieved in the Transient Reactor Test (TREAT) facility during operation between 1959 and 1994 to support characterization and safety analysis of nuclear fuels and materials. A majority of previously conducted tests were focused on supporting sodium-cooled fast reactor (SFR) designs. Experiments evolved in complexity. Simulation of thermal-hydraulic conditions expected to be encountered by fuels and materials in a reactor environment was realized in the development of TREAT sodium loop experiment vehicles. These loops accommodated up to 7-pin fuel bundles and served to simulate more closely the reactor environment whilemore » safely delivering large quantities of energy into the test specimen. Some of the immediate TREAT restart operations will be focused on testing light water reactor (LWR) accident tolerant fuels (ATF). Similar to the sodium loop objectives, a water loop concept, developed and analyzed in the 1990’s, aimed at achieving thermal-hydraulic conditions encountered in commercial power reactors. The historic water loop concept has been analyzed in the context of a reactivity insertion accident (RIA) simulation for high burnup LWR 2-pin and 3-pin fuel bundles. Findings showed sufficient energy could be deposited into the specimens for evaluation. Similar results of experimental feasibility for the water loop concept (past and present) have recently been obtained using MCNP6.1 with ENDF/B-VII.1 nuclear data libraries. The old water loop concept required only two central TREAT core grid spaces. Preparation for future experiments has resulted in a modified water loop conceptual design designated the TREAT water environment recirculating loop (TWERL). The current TWERL design requires nine TREAT core grid spaces in order to place the water recirculating pump under the TREAT core. Due to the effectiveness of water moderation, neutronics analysis shows that removal of seven additional TREAT fuel elements to facilitate the experiment will not inhibit the ability to successfully simulate a RIA for the 2-pin or 3-pin bundle. This new water loop design leaves room for accommodating a larger fuel pin bundle than previously analyzed. The 7-pin fuel bundle in a hexagonal array with similar spacing of fuel pins in a SFR fuel assembly was considered the minimum needed for one central fuel pin to encounter the most correct thermal conditions. The 9-rod fuel bundle in a square array similar in spacing to pins in a LWR fuel assembly would be considered the LWR equivalent. MCNP analysis conducted on a preliminary LWR 9-rod bundle design shows that sufficient energy deposition into the central pin can be achieved well within range to investigate fuel and cladding performance in a simulated RIA. This is achieved by surrounding the flow channel with an additional annulus of water. Findings also show that a highly significant increase in TREAT to specimen power coupling factor (PCF) within the central pin can be achieved by surrounding the experiment with one to two rings of TREAT upgrade fuel assemblies. The experiment design holds promise for the performance evaluation of PWR fuel at extremely high burnup under similar reactor environment conditions.« less
Baccei, Steven J; Chinai, Sneha A; Reznek, Martin; Henderson, Scott; Reynolds, Kevin; Brush, D Eric
2018-04-01
The appropriate communication and management of incidental findings on emergency department (ED) radiology studies is an important component of patient safety. Guidelines have been issued by the ACR and other medical associations that best define incidental findings across various modalities and imaging studies. However, there are few examples of health care facilities designing ways to manage incidental findings. Our institution aimed to improve communication and follow-up of incidental radiology findings in ED patients through the collaborative development and implementation of system-level process changes including a standardized loop-closure method. We assembled a multidisciplinary team to address the nature of these incidental findings and designed new workflows and operational pathways for both radiology and ED staff to properly communicate incidental findings. Our results are based on all incidental findings received and acknowledged between November 1, 2016, and May 30, 2017. The total number of incidental findings discovered was 1,409. Our systematic compliance fluctuated between 45% and 95% initially after implementation. However, after overcoming various challenges through optimization, our system reached a compliance rate of 93% to 95%. Through the implementation of our new, standardized communication system, a high degree of compliance with loop closure for ED incidental radiology findings was achieved at our institution. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.
3S (Safeguards, Security, Safety) based pyroprocessing facility safety evaluation plan
DOE Office of Scientific and Technical Information (OSTI.GOV)
Ku, J.H.; Choung, W.M.; You, G.S.
The big advantage of pyroprocessing for the management of spent fuels against the conventional reprocessing technologies lies in its proliferation resistance since the pure plutonium cannot be separated from the spent fuel. The extracted materials can be directly used as metal fuel in a fast reactor, and pyroprocessing reduces drastically the volume and heat load of the spent fuel. KAERI has implemented the SBD (Safeguards-By-Design) concept in nuclear fuel cycle facilities. The goal of SBD is to integrate international safeguards into the entire facility design process since the very beginning of the design phase. This paper presents a safety evaluationmore » plan using a conceptual design of a reference pyroprocessing facility, in which 3S (Safeguards, Security, Safety)-By-Design (3SBD) concept is integrated from early conceptual design phase. The purpose of this paper is to establish an advanced pyroprocessing hot cell facility design concept based on 3SBD for the successful realization of pyroprocessing technology with enhanced safety and proliferation resistance.« less
Goddard Space Flight Center Spacecraft Magnetic Test Facility Restoration Project
NASA Technical Reports Server (NTRS)
Vernier, Robert; Bonalksy, Todd; Slavin, James
2004-01-01
The Goddard Space Flight Center Spacecraft Magnetic Test Facility (SMTF) was constructed in the 1960's for the purpose of simulating geomagnetic and interplanetary magnetic field environments. The facility includes a three axis Braunbek coil system consisting of 12 loops, 4 loops on each of the three orthogonal axes; a remote Earth field sensing magnetometer and servo controller; and a remote power control and instrumentation building. The inner coils of the Braunbek system are 42-foot in diameter with a 10-foot by 10-foot opening through the outer coils to accommodate spacecraft access into the test volume. The physical size and precision of the facility are matched by only two other such facilities in the world. The facility was used extensively from the late 1960's until the early 1990's when the requirement for spacecraft level testing diminished. New NASA missions planned under the Living with a Star, Solar Terrestrial Probes, Explorer, and New Millennium Programs include precision, high-resolution magnetometers to obtain magnetic field data that is critical to fulfilling their scientific mission. It is highly likely that future Lunar and Martian exploration missions will also use precision magnetometers to conduct geophysical magnetic surveys. To ensure the success of these missions, ground-testing using a magnetic test facility such as the GSFC SMTF will be required. This paper describes the history of the facility, the future mission requirements that have renewed the need for spacecraft level magnetic testing, and the plans for restoring the facility to be capable of performing to its original design specifications.
Goddard Space Flight Center Spacecraft Magnetic Test Facility Restoration Project
NASA Technical Reports Server (NTRS)
Vernier, Robert; Bonalosky, Todd; Slavin, James
2004-01-01
The Goddard Space Flight Center Spacecraft Magnetic Test Facility (SMTF) was constructed in the 1960's for the purpose of simulating geomagnetic and interplanetary magnetic field environments. The facility includes a three axis Braunbek coil system consisting of 12 loops, 4 loops on each of the three orthogonal axes; a remote Earth field sensing magnetometer and servo controller; and a remote power control and instrumentation building. The inner coils of the Braunbek system are 42-foot in diameter with a 10-foot by 10-foot opening through the outer coils to accommodate spacecraft access into the test volume. The physical size and precision of the facility are matched by only two other such facilities in the world. The facility was used extensively from the late 1960's until the early 1990's when the requirement for spacecraft level testing diminished. New NASA missions planned under the Living with a Star, Solar Terrestrial Probes, Explorer, and New Millennium Programs include precision, high-resolution magnetometers to obtain magnetic field data that is critical to fulfilling their scientific mission. It is highly likely that future Lunar and Martian exploration missions will also use precision magnetometers to conduct geophysical magnetic surveys. To ensure the success of these missions, ground testing using a magnetic test facility such as the GSFC SMTF will be required. This paper describes the history of the facility, the future mission requirements that have renewed the need for spacecraft level magnetic testing, and the plans for restoring the facility to be capable of performing to its original design specifications.
Authorization basis supporting documentation for plutonium finishing plant
DOE Office of Scientific and Technical Information (OSTI.GOV)
King, J.P., Fluor Daniel Hanford
1997-03-05
The identification and definition of the authorization basis for the Plutonium Finishing Plant (PFP) facility and operations are essential for compliance to DOE Order 5480.21, Unreviewed Safety Questions. The authorization basis, as defined in the Order, consists of those aspects of the facility design basis, i.e., the structures, systems and components (SSCS) and the operational requirements that are considered to be important to the safety of operations and are relied upon by DOE to authorize operation of the facility. These facility design features and their function in various accident scenarios are described in WHC-SD-CP-SAR-021, Plutonium Finishing Plant Final Safety Analysismore » Report (FSAR), Chapter 9, `Accident Analysis.` Figure 1 depicts the relationship of the Authorization Basis to its components and other information contained in safety documentation supporting the Authorization Basis. The PFP SSCs that are important to safety, collectively referred to as the `Safety Envelope` are discussed in various chapters of the FSAR and in WHC-SD-CP-OSR-010, Plutonium Finishing Plant Operational Safety Requirements. Other documents such as Criticality Safety Evaluation Reports (CSERS) address and support some portions of the Authorization Basis and Safety Envelope.« less
Federal Register 2010, 2011, 2012, 2013, 2014
2010-06-15
... Construction & Facilities Management (00CFM1A), Department of Veterans Affairs, 810 Vermont Avenue, NW... Affairs Facilities; Notice of Meeting The Department of Veterans Affairs (VA) gives notice under Public... Safety of Department of Veterans Affairs Facilities will be held on June 24-25, 2010, in Room 442, Export...
Federal Register 2010, 2011, 2012, 2013, 2014
2011-04-14
... Quality Service, Office of Construction and Facilities Management (00CFM1A), Department of Veterans... Affairs Facilities; Notice of Meeting The Department of Veterans Affairs (VA) gives notice under Public... Safety of Department of Veterans Affairs Facilities will be held on May 12-13, 2011, in Room 442, at the...
DOT National Transportation Integrated Search
2017-05-01
This research collected information on the frequency and impact of safety and security incidents (threats) at selected facilities and identified priority incidents at each facility. A customized all hazards approach was used to determine the ha...
Safety Management for Water Play Facilities.
ERIC Educational Resources Information Center
Thompson, Claude
1986-01-01
Modern aquatic facilities, which include wave pools, water slides, and shallow water activity play pools, have a greater potential for injuries and lawsuits than conventional swimming pools. This article outlines comprehensive safety management for such facilities, including potential accident identification and injury control planning. (MT)
76 FR 11764 - Sunshine Act Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-03
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... Defense Nuclear Facilities Safety Board's public hearing and meeting described below. Interested persons... the matters to be considered. TIME AND DATE OF MEETING: 9 a.m., March 31, 2011. PLACE: Defense Nuclear...
Code of Federal Regulations, 2014 CFR
2014-01-01
... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...
Code of Federal Regulations, 2013 CFR
2013-01-01
... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...
Code of Federal Regulations, 2012 CFR
2012-01-01
... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...
Code of Federal Regulations, 2010 CFR
2010-01-01
... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...
Code of Federal Regulations, 2011 CFR
2011-01-01
... public reading room (FOIA requests). 1703.105 Section 1703.105 Energy DEFENSE NUCLEAR FACILITIES SAFETY... address for such requests is: Designated FOIA Officer, Defense Nuclear Facilities Safety Board, 625... pertain to an immediate source of risk to the public health and safety or worker safety at a defense...
Designing Effective Safety Signs, Based on a Study of Recall for Safety Signs.
ERIC Educational Resources Information Center
Berry, Dennis W.
Aside from direct supervision at a recreational facility, safety signs, if designed properly, are the most effective approach to facility safety. This study was conducted to investigate the effectiveness of various sign designs: (l) multiple concepts with text; (2) single concept with text; and (3) single concept with graphics. A discussion of…
30 CFR 57.6160 - Main facilities.
Code of Federal Regulations, 2010 CFR
2010-07-01
... Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Explosives Storage... facilities will not prevent escape from the mine, or cause detonation of the contents of another storage...
Limited-scope probabilistic safety analysis for the Los Alamos Meson Physics Facility (LAMPF)
DOE Office of Scientific and Technical Information (OSTI.GOV)
Sharirli, M.; Rand, J.L.; Sasser, M.K.
1992-01-01
The reliability of instrumentation and safety systems is a major issue in the operation of accelerator facilities. A probabilistic safety analysis was performed or the key safety and instrumentation systems at the Los Alamos Meson Physics Facility (LAMPF). in Phase I of this unique study, the Personnel Safety System (PSS) and the Current Limiters (XLs) were analyzed through the use of the fault tree analyses, failure modes and effects analysis, and criticality analysis. Phase II of the program was done to update and reevaluate the safety systems after the Phase I recommendations were implemented. This paper provides a brief reviewmore » of the studies involved in Phases I and II of the program.« less
Limited-scope probabilistic safety analysis for the Los Alamos Meson Physics Facility (LAMPF)
DOE Office of Scientific and Technical Information (OSTI.GOV)
Sharirli, M.; Rand, J.L.; Sasser, M.K.
1992-12-01
The reliability of instrumentation and safety systems is a major issue in the operation of accelerator facilities. A probabilistic safety analysis was performed or the key safety and instrumentation systems at the Los Alamos Meson Physics Facility (LAMPF). in Phase I of this unique study, the Personnel Safety System (PSS) and the Current Limiters (XLs) were analyzed through the use of the fault tree analyses, failure modes and effects analysis, and criticality analysis. Phase II of the program was done to update and reevaluate the safety systems after the Phase I recommendations were implemented. This paper provides a brief reviewmore » of the studies involved in Phases I and II of the program.« less
Kassa, Hailu; Silverman, Gary S.; Baroudi, Karim
2010-01-01
Food safety is an important public health issue in the U.S. Eating at restaurants and other food service facilities increasingly has been associated with food borne disease outbreaks. Food safety training and certification of food mangers has been used as a method for reducing food safety violations at food service facilities. However, the literature is inconclusive about the effectiveness of such training programs for improving food safety and protecting consumer health. The purpose of this study was to examine the effect of food manger training on reducing food safety violations. We examined food inspection reports from the Toledo/Lucas County Health Department (Ohio) from March 2005 through February 2006 and compared food hygiene violations between food service facilities with certified and without certified food managers. We also examined the impact on food safety of a food service facility being part of a larger group of facilities. Restaurants with trained and certified food managers had significantly fewer critical food safety violations but more non-critical violations than restaurants without certified personnel. Institutional food service facilities had significantly fewer violations than restaurants, and the number of violations did not differ as a function of certification. Similarly, restaurants with many outlets had significantly fewer violations than restaurants with fewer outlets, and training was not associated with lower numbers of violations from restaurants with many outlets. The value of having certified personnel was only observed in independent restaurants and those with few branches. This information may be useful in indicating where food safety problems are most likely to occur. Furthermore, we recommend that those characteristics of institutional and chain restaurants that result in fewer violations should be identified in future research, and efforts made to apply this knowledge at the level of individual restaurants. PMID:20523880
Kassa, Hailu; Silverman, Gary S; Baroudi, Karim
2010-05-06
Food safety is an important public health issue in the U.S. Eating at restaurants and other food service facilities increasingly has been associated with food borne disease outbreaks. Food safety training and certification of food mangers has been used as a method for reducing food safety violations at food service facilities. However, the literature is inconclusive about the effectiveness of such training programs for improving food safety and protecting consumer health. The purpose of this study was to examine the effect of food manger training on reducing food safety violations. We examined food inspection reports from the Toledo/Lucas County Health Department (Ohio) from March 2005 through February 2006 and compared food hygiene violations between food service facilities with certified and without certified food managers. We also examined the impact on food safety of a food service facility being part of a larger group of facilities.Restaurants with trained and certified food managers had significantly fewer critical food safety violations but more non-critical violations than restaurants without certified personnel. Institutional food service facilities had significantly fewer violations than restaurants, and the number of violations did not differ as a function of certification. Similarly, restaurants with many outlets had significantly fewer violations than restaurants with fewer outlets, and training was not associated with lower numbers of violations from restaurants with many outlets. The value of having certified personnel was only observed in independent restaurants and those with few branches. This information may be useful in indicating where food safety problems are most likely to occur. Furthermore, we recommend that those characteristics of institutional and chain restaurants that result in fewer violations should be identified in future research, and efforts made to apply this knowledge at the level of individual restaurants.
Tracking data in the office environment.
Erickson, Ty B
2010-09-01
Data tracking in the office setting focuses on a narrow spectrum of the entire patient safety arena; however, when properly executed, data tracking increases staff members' awareness of the importance of patient safety. Data tracking is also a high-volume event and thereby continues to loop back on the consciousness of providers in all aspects of their practice. Improvement in date tracking will improve the collateral areas of patient safety such as proper medication usage, legibility of written communication, effective delegation of patient safety initiatives, and a collegial effort at developing teams for safety design processes.
30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.
Code of Federal Regulations, 2014 CFR
2014-07-01
... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...
30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.
Code of Federal Regulations, 2011 CFR
2011-07-01
... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...
30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.
Code of Federal Regulations, 2013 CFR
2013-07-01
... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...
30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.
Code of Federal Regulations, 2010 CFR
2010-07-01
... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...
30 CFR 75.1712-10 - Underground sanitary facilities; maintenance.
Code of Federal Regulations, 2012 CFR
2012-07-01
... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Underground sanitary facilities; maintenance... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712-10 Underground sanitary facilities; maintenance. Sanitary toilets shall be regularly maintained in...
75 FR 21605 - Sunshine Act Notice
Federal Register 2010, 2011, 2012, 2013, 2014
2010-04-26
... depth federal safety management and oversight policies being developed by DOE and NNSA for defense... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Notice AGENCY: Defense Nuclear Facilities... in the Sunshine Act'' (5 U.S.C. 552b), notice is hereby given of the Defense Nuclear Facilities...
DOE Office of Scientific and Technical Information (OSTI.GOV)
Boyer, M. D.; Andre, R.; Gates, D. A.
The high-performance operational goals of NSTX-U will require development of advanced feedback control algorithms, including control of ßN and the safety factor profile. In this work, a novel approach to simultaneously controlling ßN and the value of the safety factor on the magnetic axis, q0, through manipulation of the plasma boundary shape and total beam power, is proposed. Simulations of the proposed scheme show promising results and motivate future experimental implementation and eventual integration into a more complex current profile control scheme planned to include actuation of individual beam powers, density, and loop voltage. As part of this work, amore » flexible framework for closed loop simulations within the high-fidelity code TRANSP was developed. The framework, used here to identify control-design-oriented models and to tune and test the proposed controller, exploits many of the predictive capabilities of TRANSP and provides a means for performing control calculations based on user-supplied data (controller matrices, target waveforms, etc.). The flexible framework should enable high-fidelity testing of a variety of control algorithms, thereby reducing the amount of expensive experimental time needed to implement new control algorithms on NSTX-U and other devices.« less
NASA Astrophysics Data System (ADS)
Boyer, M. D.; Andre, R.; Gates, D. A.; Gerhardt, S.; Goumiri, I. R.; Menard, J.
2015-05-01
The high-performance operational goals of NSTX-U will require development of advanced feedback control algorithms, including control of βN and the safety factor profile. In this work, a novel approach to simultaneously controlling βN and the value of the safety factor on the magnetic axis, q0, through manipulation of the plasma boundary shape and total beam power, is proposed. Simulations of the proposed scheme show promising results and motivate future experimental implementation and eventual integration into a more complex current profile control scheme planned to include actuation of individual beam powers, density, and loop voltage. As part of this work, a flexible framework for closed loop simulations within the high-fidelity code TRANSP was developed. The framework, used here to identify control-design-oriented models and to tune and test the proposed controller, exploits many of the predictive capabilities of TRANSP and provides a means for performing control calculations based on user-supplied data (controller matrices, target waveforms, etc). The flexible framework should enable high-fidelity testing of a variety of control algorithms, thereby reducing the amount of expensive experimental time needed to implement new control algorithms on NSTX-U and other devices.
The Future of U.S. Nuclear Forces: Boom or Bust
2007-03-30
materials, and nuclear waste.45 The Defense Nuclear Facilities Safety Board (DNFSB) was established by Congress in 1988 as an independent federal...adequate protection of public health and safety" at DOE’s defense nuclear facilities .46 This 100- person agency looks at four areas of the nuclear weapons...47 A.J. Eggenberger, Sixteenth Annual Report to Congress (Washington DC: Defense Nuclear Facilities Safety Board, February 2006), 13; available
77 FR 40891 - Towing Safety Advisory Committee
Federal Register 2010, 2011, 2012, 2013, 2014
2012-07-11
... ``Recommendations for Safety Standards of Portable Facility Vapor Control Systems.'' (4) Period for public comment... teleconference to review and discuss a new Task Statement titled ``Recommendations for Safety Standards of Portable Facility Vapor Control Systems'' and to discuss the progress of open Task Statements. This meeting...
78 FR 41991 - Pipeline Safety: Potential for Damage to Pipeline Facilities Caused by Flooding
Federal Register 2010, 2011, 2012, 2013, 2014
2013-07-12
... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION: Notice; Issuance of Advisory... Gas and Hazardous Liquid Pipeline Systems. Subject: Potential for Damage to Pipeline Facilities Caused...
Federal Register 2010, 2011, 2012, 2013, 2014
2012-10-16
..., Office of Construction & Facilities Management (003C2B), Department of Veterans Affairs, 425 I Street NW... Affairs Facilities, Notice of Meeting The Department of Veterans Affairs (VA) gives notice under the... Safety of Department of Veterans Affairs Facilities will be held on October 29-30, 2012, in Room 6W405...
Federal Register 2010, 2011, 2012, 2013, 2014
2013-04-09
... Construction and Facilities Management (003C2B), Department of Veterans Affairs, 810 Vermont Avenue NW... Affairs Facilities; Notice of Meeting The Department of Veterans Affairs (VA) gives notice under the... Safety of Department of Veterans Affairs Facilities will be held on April 25-26, 2013, in Room 6W405, 425...
30 CFR 57.20008 - Toilet facilities.
Code of Federal Regulations, 2011 CFR
2011-07-01
... kept clean and sanitary. Separate toilet facilities shall be provided for each sex except where toilet... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Toilet facilities. 57.20008 Section 57.20008... SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Miscellaneous § 57...
30 CFR 57.20008 - Toilet facilities.
Code of Federal Regulations, 2013 CFR
2013-07-01
... kept clean and sanitary. Separate toilet facilities shall be provided for each sex except where toilet... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Toilet facilities. 57.20008 Section 57.20008... SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Miscellaneous § 57...
30 CFR 57.20008 - Toilet facilities.
Code of Federal Regulations, 2014 CFR
2014-07-01
... kept clean and sanitary. Separate toilet facilities shall be provided for each sex except where toilet... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Toilet facilities. 57.20008 Section 57.20008... SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Miscellaneous § 57...
30 CFR 57.20008 - Toilet facilities.
Code of Federal Regulations, 2012 CFR
2012-07-01
... kept clean and sanitary. Separate toilet facilities shall be provided for each sex except where toilet... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Toilet facilities. 57.20008 Section 57.20008... SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Miscellaneous § 57...
30 CFR 77.1608 - Dumping facilities.
Code of Federal Regulations, 2010 CFR
2010-07-01
... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Dumping facilities. 77.1608 Section 77.1608 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH... Haulage § 77.1608 Dumping facilities. (a) Dumping locations and haulage roads shall be kept reasonably...
Leveraging Safety Programs to Improve and Support Security Programs
DOE Office of Scientific and Technical Information (OSTI.GOV)
Leach, Janice; Snell, Mark K.; Pratt, R.
2015-10-01
There has been a long history of considering Safety, Security, and Safeguards (3S) as three functions of nuclear security design and operations that need to be properly and collectively integrated with operations. This paper specifically considers how safety programmes can be extended directly to benefit security as part of an integrated facility management programme. The discussion will draw on experiences implementing such a programme at Sandia National Laboratories’ Annular Research Reactor Facility. While the paper focuses on nuclear facilities, similar ideas could be used to support security programmes at other types of high-consequence facilities and transportation activities.
NASA Astrophysics Data System (ADS)
Shi, J. T.; Han, X. T.; Xie, J. F.; Yao, L.; Huang, L. T.; Li, L.
2013-03-01
A Pulsed High Magnetic Field Facility (PHMFF) has been established in Wuhan National High Magnetic Field Center (WHMFC) and various protection measures are applied in its control system. In order to improve the reliability and robustness of the control system, the safety analysis of the PHMFF is carried out based on Fault Tree Analysis (FTA) technique. The function and realization of 5 protection systems, which include sequence experiment operation system, safety assistant system, emergency stop system, fault detecting and processing system and accident isolating protection system, are given. The tests and operation indicate that these measures improve the safety of the facility and ensure the safety of people.
Safety in Elevators and Grain Handling Facilities. Module SH-27. Safety and Health.
ERIC Educational Resources Information Center
Center for Occupational Research and Development, Inc., Waco, TX.
This student module on safety in elevators and grain handling facilities is one of 50 modules concerned with job safety and health. Following the introduction, 15 objectives (each keyed to a page in the text) the student is expected to accomplish are listed (e.g., Explain how explosion suppression works). Then each objective is taught in detail,…
Recent Developments in Hardware-in-the-Loop Formation Navigation and Control
NASA Technical Reports Server (NTRS)
Mitchell, Jason W.; Luquette, Richard J.
2005-01-01
The Formation Flying Test-Bed (FFTB) at NASA Goddard Space Flight Center (GSFC) provides a hardware-in-the-loop test environment for formation navigation and control. The facility is evolving as a modular, hybrid, dynamic simulation facility for end-tc-end guidance, navigation, and control (GN&C) design and analysis of formation flying spacecraft. The core capabilities of the FFTB, as a platform for testing critical hardware and software algorithms in-the-loop, are reviewed with a focus on many recent improvements. Two significant upgrades to the FFTB are a message-oriented middleware (MOM) architecture, and a software crosslink for inter-spacecraft ranging. The MOM architecture provides a common messaging bus for software agents, easing integration, arid supporting the GSFC Mission Services Evolution Center (GMSEC) architecture via software bridge. Additionally, the FFTB s hardware capabilities are expanding. Recently, two Low-Power Transceivers (LPTs) with ranging capability have been introduced into the FFTB. The LPT crosslinks will be connected to a modified Crosslink Channel Simulator (CCS), which applies realistic space-environment effects to the Radio Frequency (RF) signals produced by the LPTs.
A hybrid solution approach for a multi-objective closed-loop logistics network under uncertainty
NASA Astrophysics Data System (ADS)
Mehrbod, Mehrdad; Tu, Nan; Miao, Lixin
2015-06-01
The design of closed-loop logistics (forward and reverse logistics) has attracted growing attention with the stringent pressures of customer expectations, environmental concerns and economic factors. This paper considers a multi-product, multi-period and multi-objective closed-loop logistics network model with regard to facility expansion as a facility location-allocation problem, which more closely approximates real-world conditions. A multi-objective mixed integer nonlinear programming formulation is linearized by defining new variables and adding new constraints to the model. By considering the aforementioned model under uncertainty, this paper develops a hybrid solution approach by combining an interactive fuzzy goal programming approach and robust counterpart optimization based on three well-known robust counterpart optimization formulations. Finally, this paper compares the results of the three formulations using different test scenarios and parameter-sensitive analysis in terms of the quality of the final solution, CPU time, the level of conservatism, the degree of closeness to the ideal solution, the degree of balance involved in developing a compromise solution, and satisfaction degree.
NASA Technical Reports Server (NTRS)
Mitchell, Jason W.; Barbee, Brent W.; Baldwin, Philip J.; Luquette, Richard J.
2007-01-01
The Formation Flying Testbed (FFTB) at the National Aeronautics and Space Administration (NASA) Goddard Space Flight Center (GSFC) provides a hardware-in-the-loop test environment for formation navigation and control. The facility continues to evolve as a modular, hybrid, dynamic simulation facility for end-to-end guidance, navigation, and control (GN&C) design and analysis of formation flying spacecraft. The core capabilities of the FFTB, as a platform for testing critical hardware and software algorithms in-the-loop, are reviewed with a focus on recent improvements. With the most recent improvement, in support of Technology Readiness Level (TRL) 6 testing of the Inter-spacecraft Ranging and Alarm System (IRAS) for the Magnetospheric Multiscale (MMS) mission, the FFTB has significantly expanded its ability to perform realistic simulations that require Radio Frequency (RF) ranging sensors for relative navigation with the Path Emulator for RF Signals (PERFS). The PERFS, currently under development at NASA GSFC, modulates RF signals exchanged between spacecraft. The RF signals are modified to accurately reflect the dynamic environment through which they travel, including the effects of medium, moving platforms, and radiated power.
Lin, Shu-Yuan; Tseng, Wei Ting; Hsu, Miao-Ju; Chiang, Hui-Ying; Tseng, Hui-Chen
2017-12-01
To test the psychometric properties of the Chinese version of the Nursing Home Survey on Patient Safety Culture scale among staff in long-term care facilities. The Nursing Home Survey on Patient Safety Culture scale is a standard tool for safety culture assessment in nursing homes. Extending its application to different types of long-term care facilities and varied ethnic populations is worth pursuing. A national random survey. A total of 306 managers and staff completed the Chinese version of the Nursing Home Survey on Patient Safety Culture scale among 30 long-term care facilities in Taiwan. Content validity and construct validity were tested by content validity index (CVI) and principal axis factor analysis (PAF) with Promax rotation. Concurrent validity was tested through correlations between the scale and two overall rating items. Reliability was computed by intraclass correlation coefficient and Cronbach's α coefficients. Statistical analyses such as descriptive, Pearson's and Spearman's rho correlations and PAF were completed. Scale-level and item-level CVIs (0.91-0.98) of the Chinese version of the Nursing Home Survey on Patient Safety Culture scale were satisfactory. Four-factor construct and merged item composition differed from the Nursing Home Survey on Patient Safety Culture scale, and it accounted for 53% of variance. Concurrent validity was evident by existing positive correlations between the scale and two overall ratings of resident safety. Cronbach's α coefficients of the subscales and the Chinese version of the Nursing Home Survey on Patient Safety Culture scale ranged from .76-.94. The Chinese version of the Nursing Home Survey on Patient Safety Culture scale identified essential dimensions to reflect the important features of a patient safety culture in long-term care facilities. The researchers introduced the Chinese version of the Nursing Home Survey on Patient Safety Culture for safety culture assessment in long-term care facilities, but further testing of the reliability of the scale in a large Chinese sample and in different long-term care facilities was recommended. The Chinese version of the Nursing Home Survey on Patient Safety Culture scale was developed to increase the users' intention towards safety culture assessment. It can identify areas for improvement, understand safety culture changes over time and evaluate the effectiveness of interventions. © 2017 John Wiley & Sons Ltd.
49 CFR 192.171 - Compressor stations: Additional safety equipment.
Code of Federal Regulations, 2011 CFR
2011-10-01
... 49 Transportation 3 2011-10-01 2011-10-01 false Compressor stations: Additional safety equipment... Pipeline Components § 192.171 Compressor stations: Additional safety equipment. (a) Each compressor station must have adequate fire protection facilities. If fire pumps are a part of these facilities, their...
2002-05-14
Defense Nuclear Facilities Safety Board has balance-sheet-only audits every 3 to 5 years, most recently for fiscal year 1997. It did not prepare fiscal...associated with the agency’s operations were the most important factors to Have had financial statements audits Defense Nuclear Facilities Safety...audits, the International Trade Commission and the Defense Nuclear Facilities Safety Board, did not have financial statements audits for fiscal year
75 FR 45678 - Notice of Availability of Interim Staff Guidance Document for Fuel Cycle Facilities
Federal Register 2010, 2011, 2012, 2013, 2014
2010-08-03
... Document for Fuel Cycle Facilities AGENCY: Nuclear Regulatory Commission. ACTION: Notice of availability..., Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S... Commission (NRC) prepares and issues Interim Staff Guidance (ISG) documents for fuel cycle facilities. These...
30 CFR 71.404 - Application for waiver of surface facilities requirements.
Code of Federal Regulations, 2010 CFR
2010-07-01
... requirements. 71.404 Section 71.404 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND SURFACE WORK AREAS... Facilities at Surface Coal Mines § 71.404 Application for waiver of surface facilities requirements. (a...
HSE's safety assessment principles for criticality safety.
Simister, D N; Finnerty, M D; Warburton, S J; Thomas, E A; Macphail, M R
2008-06-01
The Health and Safety Executive (HSE) published its revised Safety Assessment Principles for Nuclear Facilities (SAPs) in December 2006. The SAPs are primarily intended for use by HSE's inspectors when judging the adequacy of safety cases for nuclear facilities. The revised SAPs relate to all aspects of safety in nuclear facilities including the technical discipline of criticality safety. The purpose of this paper is to set out for the benefit of a wider audience some of the thinking behind the final published words and to provide an insight into the development of UK regulatory guidance. The paper notes that it is HSE's intention that the Safety Assessment Principles should be viewed as a reflection of good practice in the context of interpreting primary legislation such as the requirements under site licence conditions for arrangements for producing an adequate safety case and for producing a suitable and sufficient risk assessment under the Ionising Radiations Regulations 1999 (SI1999/3232 www.opsi.gov.uk/si/si1999/uksi_19993232_en.pdf).
Design progress of cryogenic hydrogen system for China Spallation Neutron Source
DOE Office of Scientific and Technical Information (OSTI.GOV)
Wang, G. P.; Zhang, Y.; Xiao, J.
2014-01-29
China Spallation Neutron Source (CSNS) is a large proton accelerator research facility with 100 kW beam power. Construction started in October 2011 and is expected to last 6.5 years. The cryogenic hydrogen circulation is cooled by a helium refrigerator with cooling capacity of 2200 W at 20 K and provides supercritical hydrogen to neutron moderating system. Important progresses of CSNS cryogenic system were concluded as follows. Firstly, process design of cryogenic system has been completed including helium refrigerator, hydrogen loop, gas distribution, and safety interlock. Secondly, an accumulator prototype was designed to mitigate pressure fluctuation caused by dynamic heat loadmore » from neutron moderation. Performance test of the accumulator has been carried out at room and liquid nitrogen temperature. Results show the accumulator with welding bellows regulates hydrogen pressure well. Parameters of key equipment have been identified. The contract for the helium refrigerator has been signed. Mechanical design of the hydrogen cold box has been completed, and the hydrogen pump, ortho-para hydrogen convertor, helium-hydrogen heat exchanger, hydrogen heater, and cryogenic valves are in procurement. Finally, Hydrogen safety interlock has been finished as well, including the logic of gas distribution, vacuum, hydrogen leakage and ventilation. Generally, design and construction of CSNS cryogenic system is conducted as expected.« less
Singh, Thokchom Dewan; Jayaraman, T; Arunkumar Sharma, B
2017-03-01
This study aims to assess the adequacy level of radiological protection systems available in the diagnostic radiology facilities located in three capital cities of North East (NE) India. It further attempts to understand, using a multi-disciplinary approach, how the safety codes/standards in diagnostic radiology framed by the Atomic Energy Regulatory Board (AERB) and the International Atomic Energy Agency (IAEA) to achieve adequate radiological protection in facilities, have been perceived, conceptualized, and applied accordingly in these facilities. About 30 diagnostic radiology facilities were randomly selected from three capitals of states in NE India; namely Imphal (Manipur), Shillong (Meghalaya) and Guwahati (Assam). A semi-structured questionnaire developed based on a multi-disciplinary approach was used for this study. It was observed that radiological practices undertaken in these facilities were not exactly in line with safety codes/standards in diagnostic radiology of the AERB and the IAEA. About 50% of the facilities had registered/licensed x-ray equipment with the AERB. More than 80% of the workers did not use radiation protective devices, although these devices were available in the facilities. About 85% of facilities had no institutional risk management system. About 70% of the facilities did not carry out periodic quality assurance testing of their x-ray equipment or surveys of radiation leakage around the x-ray room, and did not display radiation safety indicators in the x-ray rooms. Workers in these facilities exhibited low risk perception about the risks associated with these practices. The majority of diagnostic radiology facilities in NE India did not comply with the radiological safety codes/standards framed by the AERB and IAEA. The study found inadequate levels of radiological protection systems in the majority of facilities. This study suggests a need to establish firm measures that comply with the radiological safety codes/standards of the AERB and IAEA to protect patients, workers and the public of this region.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Guillen, Donna Post; Zia, Jalal
2013-09-01
This research and development (R&D) project exemplifies a shared public private commitment to advance the development of energy efficient industrial technologies that will reduce the U.S. dependence upon foreign oil, provide energy savings and reduce greenhouse gas emissions. The purpose of this project was to develop and demonstrate a Direct Evaporator for the Organic Rankine Cycle (ORC) for the conversion of waste heat from gas turbine exhaust to electricity. In conventional ORCs, the heat from the exhaust stream is transferred indirectly to a hydrocarbon based working fluid by means of an intermediate thermal oil loop. The Direct Evaporator accomplishes preheating,more » evaporation and superheating of the working fluid by a heat exchanger placed within the exhaust gas stream. Direct Evaporation is simpler and up to 15% less expensive than conventional ORCs, since the secondary oil loop and associated equipment can be eliminated. However, in the past, Direct Evaporation has been avoided due to technical challenges imposed by decomposition and flammability of the working fluid. The purpose of this project was to retire key risks and overcome the technical barriers to implementing an ORC with Direct Evaporation. R&D was conducted through a partnership between the Idaho National Laboratory (INL) and General Electric (GE) Global Research Center (GRC). The project consisted of four research tasks: (1) Detailed Design & Modeling of the ORC Direct Evaporator, (2) Design and Construction of Partial Prototype Direct Evaporator Test Facility, (3) Working Fluid Decomposition Chemical Analyses, and (4) Prototype Evaluation. Issues pertinent to the selection of an ORC working fluid, along with thermodynamic and design considerations of the direct evaporator, were identified. The FMEA (Failure modes and effects analysis) and HAZOP (Hazards and operability analysis) safety studies performed to mitigate risks are described, followed by a discussion of the flammability analysis of the direct evaporator. A testbed was constructed and the prototype demonstrated at the GE GRC Niskayuna facility.« less
49 CFR 192.171 - Compressor stations: Additional safety equipment.
Code of Federal Regulations, 2010 CFR
2010-10-01
... SAFETY TRANSPORTATION OF NATURAL AND OTHER GAS BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Design of... must have adequate fire protection facilities. If fire pumps are a part of these facilities, their... event of inadequate cooling or lubrication of the unit. (d) Each compressor station gas engine that...
30 CFR 75.1712 - Bath houses and toilet facilities.
Code of Federal Regulations, 2010 CFR
2010-07-01
... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Bath houses and toilet facilities. 75.1712 Section 75.1712 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712 Bath houses...
Federal Register 2010, 2011, 2012, 2013, 2014
2011-11-02
... Uranium Enrichment Fuel Cycle Facility's Inspection Reports Regarding Louisiana Energy Services, National..., Uranium Enrichment Branch, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety... Commission. Brian W. Smith, Chief, Uranium Enrichment Branch, Division of Fuel Cycle Safety and Safeguards...
30 CFR 75.1712 - Bath houses and toilet facilities.
Code of Federal Regulations, 2011 CFR
2011-07-01
... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Bath houses and toilet facilities. 75.1712 Section 75.1712 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Miscellaneous § 75.1712 Bath houses...
The Freon loop double containment design for Spacelab refrigerator/freezer to protect environment
NASA Technical Reports Server (NTRS)
Hye, A.
1985-01-01
General Electric is building a vapor compression refrigerator/freezer for NASA-Johnson Space Center for the Spacelab mission SLS-1 for life sciences experiments. Freon R502 is used as refrigerant. As R502 is considered toxic, the whole Freon loop is enclosed in a second containment to avoid exposure to crewmen. A detailed description of the design and construction of the safety enclosure is presented.
Assessment of a simple, novel endoluminal method for gastrotomy closure in NOTES.
Lee, Sang Soo; Oelschlager, Brant K; Wright, Andrew S; Soares, Renato V; Sinan, Huseyin; Montenovo, Martin I; Hwang, Joo Ha
2011-10-01
A reliable method for gastrotomy closure in NOTES will be essential for NOTES to become viable clinically. However, methods using existing and widely available endoscopic accessories have been ineffective. The objective of this study was to evaluate the feasibility and safety of a new simple method for gastric closure (retracted clip-assisted loop closure) that uses existing endoscopic accessories with minor modifications. The retracted clip-assisted loop closure technique involves deploying 3-4 Resolution(®) clips (modified by attaching a 90-cm length of suture to the end of each clip) along the margin of the gastrotomy with one jaw on the serosal surface and the other jaw on the mucosal surface. The suture strings are threaded through an endoloop. Traction is then applied to the strings causing the gastric wall to tent. The endoloop is secured below the tip of the clips, completing a full-thickness gastrotomy closure. The main outcome measures were feasibility, efficacy, and safety of the new retracted clip-assisted loop closure technique for NOTES gastrotomy closure. An air-tight seal was achieved in 100% (n = 9) of stomachs. The mean leak pressure was 116.3 (±19.4) mmHg. The retracted clip-assisted loop closure technique can be used to perform NOTES gastrotomy closure by using existing endoscopic accessories with minor modifications.
NASA Technical Reports Server (NTRS)
Kulkarni, Chetan; Teubert, Chris; Gorospe, George; Burgett, Drew; Quach, Cuong C.; Hogge, Edward
2016-01-01
The airspace is becoming more and more complicated, and will continue to do so in the future with the integration of Unmanned Aerial Vehicles (UAVs), autonomy, spacecraft, other forms of aviation technology into the airspace. The new technology and complexity increases the importance and difficulty of safety assurance. Additionally, testing new technologies on complex aviation systems & systems of systems can be very difficult, expensive, and sometimes unsafe in real life scenarios. Prognostic methodology provides an estimate of the health and risks of a component, vehicle, or airspace and knowledge of how that will change over time. That measure is especially useful in safety determination, mission planning, and maintenance scheduling. The developed testbed will be used to validate prediction algorithms for the real-time safety monitoring of the National Airspace System (NAS) and the prediction of unsafe events. The framework injects flight related anomalies related to ground systems, routing, airport congestion, etc. to test and verify algorithms for NAS safety. In our research work, we develop a live, distributed, hardware-in-the-loop testbed for aviation and airspace prognostics along with exploring further research possibilities to verify and validate future algorithms for NAS safety. The testbed integrates virtual aircraft using the X-Plane simulator and X-PlaneConnect toolbox, UAVs using onboard sensors and cellular communications, and hardware in the loop components. In addition, the testbed includes an additional research framework to support and simplify future research activities. It enables safe, accurate, and inexpensive experimentation and research into airspace and vehicle prognosis that would not have been possible otherwise. This paper describes the design, development, and testing of this system. Software reliability, safety and latency are some of the critical design considerations in development of the testbed. Integration of HITL elements in the development phases and veri cation/ validation are key elements to this report.
Laser Safety Method For Duplex Open Loop Parallel Optical Link
Baumgartner, Steven John; Hedin, Daniel Scott; Paschal, Matthew James
2003-12-02
A method and apparatus are provided to ensure that laser optical power does not exceed a "safe" level in an open loop parallel optical link in the event that a fiber optic ribbon cable is broken or otherwise severed. A duplex parallel optical link includes a transmitter and receiver pair and a fiber optic ribbon that includes a designated number of channels that cannot be split. The duplex transceiver includes a corresponding transmitter and receiver that are physically attached to each other and cannot be detached therefrom, so as to ensure safe, laser optical power in the event that the fiber optic ribbon cable is broken or severed. Safe optical power is ensured by redundant current and voltage safety checks.
33 CFR 6.14-1 - Safety measures.
Code of Federal Regulations, 2011 CFR
2011-07-01
..., may prescribe such conditions and restrictions relating to the safety of waterfront facilities and... of, and fire-prevention measures for, such vessels and waterfront facilities. [EO 10277, 16 FR 7541...
33 CFR 6.14-1 - Safety measures.
Code of Federal Regulations, 2014 CFR
2014-07-01
..., may prescribe such conditions and restrictions relating to the safety of waterfront facilities and... of, and fire-prevention measures for, such vessels and waterfront facilities. [EO 10277, 16 FR 7541...
33 CFR 6.14-1 - Safety measures.
Code of Federal Regulations, 2013 CFR
2013-07-01
..., may prescribe such conditions and restrictions relating to the safety of waterfront facilities and... of, and fire-prevention measures for, such vessels and waterfront facilities. [EO 10277, 16 FR 7541...
33 CFR 6.14-1 - Safety measures.
Code of Federal Regulations, 2012 CFR
2012-07-01
..., may prescribe such conditions and restrictions relating to the safety of waterfront facilities and... of, and fire-prevention measures for, such vessels and waterfront facilities. [EO 10277, 16 FR 7541...
Assessing patient safety in Canadian ambulatory surgery facilities: A national survey
Ahmad, Jamil; Ho, Olivia A; Carman, Wayne W; Thoma, Achilles; Lalonde, Donald H; Lista, Frank
2014-01-01
BACKGROUND: There has been increased interest regarding patient safety and standards of care in Canadian ambulatory surgery facilities where surgical procedures are performed. The Canadian Association for Accreditation of Ambulatory Surgical Facilities (CAAASF) is a national organization formed to establish and maintain standards to ensure that surgical procedures conducted outside of public hospitals are performed safely. OBJECTIVE: To determine how many procedures are performed annually at CAAASF member sites, and to examine complication rates and several key patient safety practices. METHODS: All 69 facilities accredited by the CAAASF were surveyed. The survey focused on procedural data, complication rates and patient safety interventions. RESULTS: In 2010, 40,240 estimated procedures were performed. A total of 263 (0.007%) complications were reported. Sixteen (0.0004%) patients required reoperations in hospital and 19 (0.0004%) patients required transfer to hospital on the day of surgery. There were only two mortalities within 30 days of surgery reported in the past five years. With regard to patient safety practices, 93% used antimicrobial prophylaxis, 100% used strategies to maintain normothermia and 82% used measures for venous thromboembolism prevention. CONCLUSION: The present study is the first to report on the Canadian experience in ambulatory surgery facilities and provides insight into current practices at these facilities. Appropriate accreditation of ambulatory surgery facilities, well-established patient safety-related standards of care, careful patient selection and procedures performed by qualified health care professionals with appropriate certification practicing within the scope of their practice form the basis for safe and effective ambulatory surgery. PMID:25152645
Ortho stops marketing Lippes Loop; cites economic factors.
1985-11-01
Ortho Pharmaceutical Corporation has stopped marketing the Lippes Loop IUD, the only inert IUD currently available in the US. The firm cited "economic considerations" as its reason. Linda Organ, company spokeswoman, told Contraceptive Technology Update (CTU) that the number of women using IUDs has declined in the past few years and, as a result, Ortho's Lippes Loop sales dropped. Most physicians, according to Organ, currently prescribe copper-bearing IUDs. Few devices have been studied as thoroughly before marketing as the Lippes Loop, according to its developer, Dr. Jack Lippes. Lippes told CTU that the Population Council analyzed 40,000 women from 1962 to 1968 and "found no trouble with the Loop." Lippes attributes Ortho's recent decision to 2 factors: the IUD has been only "marginally profitable" and the problems of A.H. Robins with the Dalkon Shield has most likely had an effect; and the US Food and Drug Administration (FDA) published a proposed rule in August 1985 that would require any company wanting to manufacture and market IUDs like the Lippes Loop to submit a premarketing approval application to that agency. In effect, the FDA's rule would only apply to the Lippes Loop. Under the proposed rule, any company wanting to market Lippes Loops, or any nondrug IUD, would have to submit an application to the FDA with a detailed discussion and supporting clinical studies addressing the following concerns: pelvic actinomycosis; tubal infertility; duration that the IUD should remain in situ; and safety of leaving the IUD in situ when contraception is no longer indicated. According to Lillian Yin, FDA device evaluation, the clinical effectiveness and most of the safety issues regarding inert IUDs have been thoroughly covered in published data. She told CTU that "most of the information needed is straightforward, but the part that's new involves the long term use infection rate." Yin indicated that the FDA received a letter from Ortho advising the agency of the company's decision to discontinue selling the loop. That decision, according to Organ, is not based on new study information about inert versus copper bearing IUDs. The company sent a letter to physicians on April 15 advising them of revisions in Lippes Loop patient and physician information materials. The added information is cited.
NASA MSFC hardware in the loop simulations of automatic rendezvous and capture systems
NASA Technical Reports Server (NTRS)
Tobbe, Patrick A.; Naumann, Charles B.; Sutton, William; Bryan, Thomas C.
1991-01-01
Two complementary hardware-in-the-loop simulation facilities for automatic rendezvous and capture systems at MSFC are described. One, the Flight Robotics Laboratory, uses an 8 DOF overhead manipulator with a work volume of 160 by 40 by 23 feet to evaluate automatic rendezvous algorithms and range/rate sensing systems. The other, the Space Station/Station Operations Mechanism Test Bed, uses a 6 DOF hydraulic table to perform docking and berthing dynamics simulations.
Fire Safety in Nursing Facilities: Participant's Coursebook.
ERIC Educational Resources Information Center
Walker (Bonnie) and Associates, Inc., Crofton, MD.
Fewer people die in nursing facility fires than in fires occurring in other places where older people live. Fire remains, however, a significant threat in nursing facilities. This book is centered around six "modules" that present a fire safety training program for managers and staff in nursing homes. These modules present the following…
9 CFR 390.4 - Facilities for inspection and copying.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 9 Animals and Animal Products 2 2012-01-01 2012-01-01 false Facilities for inspection and copying. 390.4 Section 390.4 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE FOOD SAFETY AND INSPECTION SERVICE ADMINISTRATIVE PROVISIONS FREEDOM OF INFORMATION AND PUBLIC INFORMATION § 390.4 Facilities for...
9 CFR 390.4 - Facilities for inspection and copying.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 9 Animals and Animal Products 2 2013-01-01 2013-01-01 false Facilities for inspection and copying. 390.4 Section 390.4 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE FOOD SAFETY AND INSPECTION SERVICE ADMINISTRATIVE PROVISIONS FREEDOM OF INFORMATION AND PUBLIC INFORMATION § 390.4 Facilities for...
9 CFR 390.4 - Facilities for inspection and copying.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 9 Animals and Animal Products 2 2011-01-01 2011-01-01 false Facilities for inspection and copying. 390.4 Section 390.4 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE FOOD SAFETY AND INSPECTION SERVICE ADMINISTRATIVE PROVISIONS FREEDOM OF INFORMATION AND PUBLIC INFORMATION § 390.4 Facilities for...
9 CFR 390.4 - Facilities for inspection and copying.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 9 Animals and Animal Products 2 2014-01-01 2014-01-01 false Facilities for inspection and copying. 390.4 Section 390.4 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE FOOD SAFETY AND INSPECTION SERVICE ADMINISTRATIVE PROVISIONS FREEDOM OF INFORMATION AND PUBLIC INFORMATION § 390.4 Facilities for...
High-Explosives Applications Facility (HEAF)
NASA Astrophysics Data System (ADS)
Morse, J. L.; Weingart, R. C.
1989-03-01
This Safety Analysis Report (SAR) reviews the safety and environmental aspects of the High Explosives Applications Facility (HEAF). Topics covered include the site selected for the HEAF, safety design criteria, operations planned within the facility, and the safety and environmental analyses performed on this project to date. Provided in the Summary section is a review of hazards and the analyses, conclusions, and operating limits developed in this SAR. Appendices provide supporting documents relating to this SAR. This SAR is required by the LLNL Health and Safety Manual and DOE Order 5481.1B(2) to document the safety analysis efforts. The SAR was assembled by the Hazards Control Department, B-Division, and HEAF project personnel. This document was reviewed by B Division, the Chemistry Department, the Hazards Control Department, the Laboratory Associate Director for Administration and Operations, and the Associate Directors ultimately responsible for HEAF operations.
Costanzo, Maria Rosa; Negoianu, Daniel; Fonarow, Gregg C; Jaski, Brian E; Bart, Bradley A; Heywood, J Thomas; Nabut, Jose L; Schollmeyer, Michael P
2015-09-01
In patients hospitalized with acutely decompensated heart failure, unresolved signs and symptoms of fluid overload have been consistently associated with poor outcomes. Regardless of dosing and type of administration, intravenous loop diuretics have not reduced heart failure events or mortality in patients with acutely decompensated heart failure. The results of trials comparing intravenous loop diuretics to mechanical fluid removal by isolated venovenous ultrafiltration have yielded conflicting results. Studies evaluating early decongestive strategies have shown that ultrafiltration removed more fluid and was associated with fewer heart failure-related rehospitalization than intravenous loop diuretics. In contrast, when used in the setting of worsening renal function, ultrafiltration was associated with poorer renal outcomes and no reduction in heart failure events. The AVOID-HF trial seeks to determine if an early strategy of ultrafiltration in patients with acutely decompensated heart failure is associated with fewer heart failure events at 90 days compared with a strategy based on intravenous loop diuretics. Study subjects from 40 highly experienced institutions are randomized to either early ultrafiltration or intravenous loop diuretics. In both treatment arms, fluid removal therapies are adjusted according to the patients' hemodynamic condition and renal function. The study was unilaterally terminated by the sponsor in the absence of futility and safety concerns after the enrollment of 221 subjects, or 27% of the originally planned sample size of 810 patients. The AVOID-HF trial's principal aim is to compare the safety and efficacy of ultrafiltration vs that of intravenous loop diuretics in patients hospitalized with acutely decompensated heart failure. Because stepped treatment approaches are applied in both ultrafiltration and intravenous loop diuretics groups and the primary end point is time to first heart failure event within 90 days, it is hoped that the AVOID-HF trial, despite its untimely termination by the sponsor, will provide further insight on how to optimally decongest patients with fluid-overloaded heart failure. Copyright © 2015. Published by Elsevier Inc.
NASA Astrophysics Data System (ADS)
Park, D. K.; Bae, G. O.; Lee, K. K.
2014-12-01
The open-loop geothermal system directly uses a relatively stable temperature of groundwater for cooling and heating in buildings and thus has been known as an eco-friendly, energy-saving, and cost-efficient technique. The facility for this system was installed at a site located near Paldang-dam in Han-river, Korea. Because of the well-developed alluvium, the site might be appropriate to application of this system requiring extraction and injection of a large amount of groundwater. A simple numerical experiment assuming various hydrogeologic conditions demonstrated that regional groundwater flow direction was the most important factor for efficient operation of facility in this site having a highly permeable layer. However, a comparison of river stage data and groundwater level measurements showed that the daily and seasonal controls of water level at Paldang-dam have had a critical influence on the regional groundwater flow in the site. Moreover, nitrate concentrations measured in the monitoring wells gave indication of the effect of agricultural activities around the facility on the groundwater quality. The facility operation, such as extraction and injection of groundwater, will obviously affect transport of the agricultural contaminant and, maybe, it will even cause serious problems in the normal operation. Particularly, the high-permeable layer in this aquifer must be a preferential path for quick spreadings of thermal and contaminant plumes. The objective of this study was to find an efficient, safe and stable operation plan of the open-loop geothermal system installed in this site having the complicated conditions of highly permeable layer, variable regional groundwater flow, and agricultural contamination. Numerical simulations for groundwater flow, heat and solute transport were carried out to analyze all the changes in groundwater level and flow, temperature, and quality according to the operation, respectively. Results showed that an operation plan for only the thermal efficiency of system cannot be the best in aspect of safe and stable operation related to groundwater quality. All these results concluded that it is essential to understand various and site-specific conditions of the site in a more integrated approach for the successful application of the open-loop geothermal system.
DOE standard 3009 - a reasoned, practical approach to integrating criticality safety into SARs
DOE Office of Scientific and Technical Information (OSTI.GOV)
Vessard, S.G.
1995-12-31
In the past there have been efforts by the U.S. Department of Energy (DOE) to provide guidance on those elements that should be included in a facility`s safety analysis report (SAR). In particular, there are two DOE Orders (5480.23, {open_quotes}Nuclear Safety Analysis Reports,{close_quotes} and 5480.24, {open_quotes}Nuclear Criticality Safety{close_quotes}), an interpretive guidance document (NE-70, Interpretive Guidance for DOE Order 5480.24, {open_quotes}Nuclear Criticality Safety{close_quotes}), and DOE Standard DOE-STD-3009-94 {open_quotes}Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports.{close_quotes} Of these, the most practical and useful (pertaining to the application of criticality safety) is DOE-STD-3009-94. This paper is a reviewmore » of Chapters 3, 4, and 6 of this standard and how they provide very clear, helpful, and reasoned criticality safety guidance.« less
30 CFR 75.1709 - Accumulations of methane and coal dust on surface coal-handling facilities.
Code of Federal Regulations, 2013 CFR
2013-07-01
... 30 Mineral Resources 1 2013-07-01 2013-07-01 false Accumulations of methane and coal dust on surface coal-handling facilities. 75.1709 Section 75.1709 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES...
30 CFR 75.1709 - Accumulations of methane and coal dust on surface coal-handling facilities.
Code of Federal Regulations, 2012 CFR
2012-07-01
... 30 Mineral Resources 1 2012-07-01 2012-07-01 false Accumulations of methane and coal dust on surface coal-handling facilities. 75.1709 Section 75.1709 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES...
30 CFR 75.1709 - Accumulations of methane and coal dust on surface coal-handling facilities.
Code of Federal Regulations, 2011 CFR
2011-07-01
... 30 Mineral Resources 1 2011-07-01 2011-07-01 false Accumulations of methane and coal dust on surface coal-handling facilities. 75.1709 Section 75.1709 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES...
30 CFR 75.1709 - Accumulations of methane and coal dust on surface coal-handling facilities.
Code of Federal Regulations, 2014 CFR
2014-07-01
... 30 Mineral Resources 1 2014-07-01 2014-07-01 false Accumulations of methane and coal dust on surface coal-handling facilities. 75.1709 Section 75.1709 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES...
2008-05-01
building up to and beyond the 2013 time frame. However, in October 2007, the Defense Nuclear Facilities Safety Board, which monitors safety...manufacturing. They said that NNSA is still working through this process with the Defense Nuclear Facilities Safety Board. Processing of waste
GAO’s Views on DOE’s 1991 Budget for Addressing Problems at the Nuclear Weapons Complex
1990-03-02
management, and efforts by DOE to make its contractors more accountable. Also, the Defense Nuclear Facilities Safety Board mandated by the Congress became...and safety matters. 6 Finally, the Defense Nuclear Facilities Safety Board was established. Although not a DOE action, its establishment, nevertheless
Federal Register 2010, 2011, 2012, 2013, 2014
2011-06-28
... Safety Board, Pulse Jet Mixing at the Waste Treatment and Immobilization Plant AGENCY: Department of... their Recommendation 2010-2, concerning Pulse Jet Mixing at the Waste Treatment and Immobilization Plant... Nuclear Facilities Safety Board (Board) Recommendation 2010-2, Pulse Jet Mixing (PJM) at the Waste...
78 FR 6209 - Safety Zone; Grain-Shipment Vessels, Columbia and Willamette Rivers
Federal Register 2010, 2011, 2012, 2013, 2014
2013-01-30
... 1625-AA00 Safety Zone; Grain-Shipment Vessels, Columbia and Willamette Rivers AGENCY: Coast Guard, DHS... temporary safety zone around all inbound and outbound grain-shipment vessels involved in commerce with the Columbia Grain facility on the Willamette River in Portland, OR, the United Grain Corporation facility on...
NASA Astrophysics Data System (ADS)
Peterson, Zachary W.
Hybrid motors that employ non-toxic, non-explosive components with a liquid oxidizer and a solid hydrocarbon fuel grain have inherently safe operating characteristics. The inherent safety of hybrid rocket motors offers the potential to greatly reduce overall operating costs. Another key advantage of hybrid rocket motors is the potential for in-flight shutdown, restart, and throttle by controlling the pressure drop between the oxidizer tank and the injector. This research designed, developed, and ground tested a closed-loop throttle controller for a hybrid rocket motor using nitrous oxide and hydroxyl-terminated polybutadiene as propellants. The research simultaneously developed closed-loop throttle algorithms and lab scale motor hardware to evaluate the fidelity of the throttle simulations and algorithms. Initial open-loop motor tests were performed to better classify system parameters and to validate motor performance values. Deep-throttle open-loop tests evaluated limits of stable thrust that can be achieved on the test hardware. Open-loop tests demonstrated the ability to throttle the motor to less than 10% of maximum thrust with little reduction in effective specific impulse and acoustical stability. Following the open-loop development, closed-loop, hardware-in-the-loop tests were performed. The closed-loop controller successfully tracked prescribed step and ramp command profiles with a high degree of fidelity. Steady-state accuracy was greatly improved over uncontrolled thrust.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Neupauer, R.M.; Thurmond, S.M.
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.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Neupauer, R.M.; Thurmond, S.M.
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.
Effects of health and safety problem recognition on small business facility investment
2013-01-01
Objectives This study involved a survey of the facility investment experiences, which was designed to recognize the importance of health and safety problems, and industrial accident prevention. Ultimately, we hope that small scale industries will create effective industrial accident prevention programs and facility investments. Methods An individual survey of businesses’ present physical conditions, recognition of the importance of the health and safety problems, and facility investment experiences for preventing industrial accidents was conducted. The survey involved 1,145 business operators or management workers in small business places with fewer than 50 workers in six industrial complexes. Results Regarding the importance of occupational health and safety problems (OHS), 54.1% said it was “very important”. Received technical and financial support, and industrial accidents that occurred during the past three years were recognized as highly important for OHS. In an investigation regarding facility investment experiences for industrial accident prevention, the largest factors were business size, greater numbers of industrial accidents, greater technical and financial support received, and greater recognition of the importance of the OHS. The related variables that decided facility investment for industry accident prevention in a logistic regression analysis were the experiences of business facilities where industrial accidents occurred during the past three years, received technical and financial support, and recognition of the OHS. Those considered very important were shown to be highly significant. Conclusions Recognition of health and safety issues was higher when small businesses had experienced industrial accidents or received financial support. The investment in industrial accidents was greater when health and safety issues were recognized as important. Therefore, the goal of small business health and safety projects is to prioritize health and safety issues in terms of business management and recognition of importance. Therefore, currently various support projects are being conducted. However, there are issues regarding the limitations of the target businesses and inadequacies in maintenance and follow-up. Overall, it is necessary to provide various incentives for onsite participation that can lead to increased recognition of health and safety issues and practical investments, while perfecting maintenance and follow up measures by thoroughly revising existing operating systems. PMID:24472180
Effects of health and safety problem recognition on small business facility investment.
Park, Jisu; Jeong, Harin; Hong, Sujin; Park, Jong-Tae; Kim, Dae-Sung; Kim, Jongseo; Kim, Hae-Joon
2013-10-23
This study involved a survey of the facility investment experiences, which was designed to recognize the importance of health and safety problems, and industrial accident prevention. Ultimately, we hope that small scale industries will create effective industrial accident prevention programs and facility investments. An individual survey of businesses' present physical conditions, recognition of the importance of the health and safety problems, and facility investment experiences for preventing industrial accidents was conducted. The survey involved 1,145 business operators or management workers in small business places with fewer than 50 workers in six industrial complexes. Regarding the importance of occupational health and safety problems (OHS), 54.1% said it was "very important". Received technical and financial support, and industrial accidents that occurred during the past three years were recognized as highly important for OHS. In an investigation regarding facility investment experiences for industrial accident prevention, the largest factors were business size, greater numbers of industrial accidents, greater technical and financial support received, and greater recognition of the importance of the OHS. The related variables that decided facility investment for industry accident prevention in a logistic regression analysis were the experiences of business facilities where industrial accidents occurred during the past three years, received technical and financial support, and recognition of the OHS. Those considered very important were shown to be highly significant. Recognition of health and safety issues was higher when small businesses had experienced industrial accidents or received financial support. The investment in industrial accidents was greater when health and safety issues were recognized as important. Therefore, the goal of small business health and safety projects is to prioritize health and safety issues in terms of business management and recognition of importance. Therefore, currently various support projects are being conducted. However, there are issues regarding the limitations of the target businesses and inadequacies in maintenance and follow-up. Overall, it is necessary to provide various incentives for onsite participation that can lead to increased recognition of health and safety issues and practical investments, while perfecting maintenance and follow up measures by thoroughly revising existing operating systems.
Space Station environmental control and life support system distribution and loop closure studies
NASA Technical Reports Server (NTRS)
Humphries, William R.; Reuter, James L.; Schunk, Richard G.
1986-01-01
The NASA Space Station's environmental control and life support system (ECLSS) encompasses functional elements concerned with temperature and humidity control, atmosphere control and supply, atmosphere revitalization, fire detection and suppression, water recovery and management, waste management, and EVA support. Attention is presently given to functional and physical module distributions of the ECLSS among these elements, with a view to resource requirements and safety implications. A strategy of physical distribution coupled with functional centralization is for the air revitalization and water reclamation systems. Also discussed is the degree of loop closure desirable in the initial operational capability status Space Station's oxygen and water reclamation loops.
49 CFR 193.2005 - Applicability.
Code of Federal Regulations, 2010 CFR
2010-10-01
... Transportation Other Regulations Relating to Transportation (Continued) PIPELINE AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES..., design, installation, or construction of LNG facilities (including material incorporated by reference in...
Banaszak-Holl, Jane; Reichert, Heidi; Todd Greene, M; Mody, Lona; Wald, Heidi L; Crnich, Christopher; McNamara, Sara E; Meddings, Jennifer
2017-10-01
To identify facility- and individual-level predictors of nursing home safety culture. Cross-sectional survey of individuals within facilities. Nursing homes participating in the national Agency for Healthcare Research and Quality Safety Program for Long-Term Care: Healthcare-Associated Infections/Catheter-Associated Urinary Tract Infections Project. Responding nursing home staff (N = 14,177) from 170 (81%) of 210 participating facilities. Staff responses to the Nursing Home Survey on Patient Safety Culture (NHSOPS), focused on five domains (teamwork, training and skills, communication openness, supervisor expectations, organizational learning) and individual respondent characteristics (occupation, tenure, hours worked), were merged with data on facility characteristics (from the Certification and Survey Provider Enhanced Reporting): ownership, chain membership, percentage residents on Medicare, bed size. Data were analyzed using multivariate hierarchical models. Nursing assistants rated all domains worse than administrators did (P < .001), with the largest differences for communication openness (24.3 points), teamwork (17.4 points), and supervisor expectations (16.1 points). Clinical staff rated all domains worse than administrators. Nonprofit ownership was associated with worse training and skills (by 6.0 points, P =.04) and communication openness (7.3 points, P =.004), and nonprofit and chain ownership were associated with worse supervisor expectations (5.2 points, P =.001 and 3.2 points, P =.03, respectively) and organizational learning (5.6 points, P =.009 and 4.2 points, P = .03). The percentage of variation in safety culture attributable to facility characteristics was less than 22%, with ownership having the strongest effect. Perceptions of safety culture vary widely among nursing home staff, with administrators consistently perceiving better safety culture than clinical staff who spend more time with residents. Reporting safety culture scores according to occupation may be more important than facility-level scores alone to describe and assess barriers, facilitators, and changes in safety culture. © 2017, Copyright the Authors Journal compilation © 2017, The American Geriatrics Society.
Development of a generic GMCC simulator.
DOT National Transportation Integrated Search
2001-11-01
This document describes the development and current status of a high fidelity, human-in-the-loop simulator for Airway Facilities : Maintenance Control Centers and Operations Control Centers. Applications include Event Manager, Maintenance Automation ...
Air-Ground Integration Experiment
DOT National Transportation Integrated Search
2002-01-01
could potentially shift aircraft separation responsibility from air traffic controllers to flight crews creating a'shared-separation' : authority environment Areal-time, human-in-the-loop study was conducted using facilities at NASA Ames Research Cen...
DOE Office of Scientific and Technical Information (OSTI.GOV)
Meyer, A.F. Jr.
1980-07-02
A site visit was made in company with the DOE-OPTA-EA Safety and Health Official for the purpose of providing that official with technical assistance in evaluating the validity of an earlier DOE-OPTA recommendation exempting this facility from the Safety and Analysis and Review backfit requirements of DOE Order 5481.1. A further purpose of the visit was to assess and evaluate the occupational safety and health program at this facility, as compared with the criteria and guidelines contained in ASFE Order 5481.1. Adequate documentation regarding compliance with codes, standards, and regulations were observed at this facility. There is in existence anmore » ongoing continuous safety analysis effort for both modifications or additions to this facility. Adequate environmental safeguards and plans and procedures were observed. The SARS backfit exemption is appropriate. The occupational safety and health program is in many ways a model for the scope of work and nature of hazards involved, and is consistent with ASFE guidelines and statutory requirements.« less
Water safety in healthcare facilities. The Vieste Charter.
Bonadonna, L; Cannarozzi de Grazia, M; Capolongo, S; Casini, B; Cristina, M L; Daniele, G; D'Alessandro, D; De Giglio, O; Di Benedetto, A; Di Vittorio, G; Ferretti, E; Frascolla, B; La Rosa, G; La Sala, L; Lopuzzo, M G; Lucentini, L; Montagna, M T; Moscato, U; Pasquarella, C; Prencipe, R; Ricci, M L; Romano Spica, V; Signorelli, C; Veschetti, E
2017-01-01
The Study Group on Hospital Hygiene of the Italian Society of Hygiene, Preventive Medicine and Public Health (GISIO-SItI) and the Local Health Authority of Foggia, Apulia, Italy, after the National Convention "Safe water in healthcare facilities" held in Vieste-Pugnochiuso on 27-28 May 2016, present the "Vieste Charter", drawn up in collaboration with experts from the National Institute of Health and the Ministry of Health. This paper considers the risk factors that may affect the water safety in healthcare facilities and reports the current regulatory frameworks governing the management of installations and the quality of the water. The Authors promote a careful analysis of the risks that characterize the health facilities, for the control of which specific actions are recommended in various areas, including water safety plans; approval of treatments; healthcare facilities responsibility, installation and maintenance of facilities; multidisciplinary approach; education and research; regional and national coordination; communication.
Federal Register 2010, 2011, 2012, 2013, 2014
2010-06-28
.... PHMSA-2010-0175] Pipeline Safety: Updating Facility Response Plans in Light of the Deepwater Horizon Oil... 194. In light of the Deepwater Horizon oil spill in the Gulf of Mexico, which has resulted in the... Systems. Subject: Updating Facility Response Plans in Light of the Deepwater Horizon Oil Spill. Advisory...
Industrial Sanitation and Personal Facilities. Module SH-13. Safety and Health.
ERIC Educational Resources Information Center
Center for Occupational Research and Development, Inc., Waco, TX.
This student module on industrial sanitation and personal facilities is one of 50 modules concerned with job safety and health. This module deals wth many facets of industrial sanitation and the facilities industries should provide so that proper health procedures may be followed. Following the introduction, 14 objectives (each keyed to a page in…
Federal Register 2010, 2011, 2012, 2013, 2014
2011-06-28
... the public, workers, and the environment. For example, the Board clarified that use of the term.... Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as a safe harbor methodology..., our workers, and the environment at all of our facilities. We share your conviction that a clear set...
An approach to radiation safety department benchmarking in academic and medical facilities.
Harvey, Richard P
2015-02-01
Based on anecdotal evidence and networking with colleagues at other facilities, it has become evident that some radiation safety departments are not adequately staffed and radiation safety professionals need to increase their staffing levels. Discussions with management regarding radiation safety department staffing often lead to similar conclusions. Management acknowledges the Radiation Safety Officer (RSO) or Director of Radiation Safety's concern but asks the RSO to provide benchmarking and justification for additional full-time equivalents (FTEs). The RSO must determine a method to benchmark and justify additional staffing needs while struggling to maintain a safe and compliant radiation safety program. Benchmarking and justification are extremely important tools that are commonly used to demonstrate the need for increased staffing in other disciplines and are tools that can be used by radiation safety professionals. Parameters that most RSOs would expect to be positive predictors of radiation safety staff size generally are and can be emphasized in benchmarking and justification report summaries. Facilities with large radiation safety departments tend to have large numbers of authorized users, be broad-scope programs, be subject to increased controls regulations, have large clinical operations, have significant numbers of academic radiation-producing machines, and have laser safety responsibilities.
Tseng, Wei-Wen; Shih, Chung-Liang; Chien, Shen-Wen
2013-04-01
Taiwan's worst hospital fire in history on October 23rd, 2012 at Sinying Hospital's Bei-Men Branch resulted in 13 elderly patient deaths and over 70 injuries. The heavy casualties were due in part to the serious condition of patients. Some patients on life-support machines were unable to move or be moved. This disaster highlights the issue of fire safety in small-scale hospitals that have transformed existing hospital space into special care environments for elderly patients. Compared with medical centers and general hospitals, these small-scale health facilities are ill equipped to deal properly with fire safety management and emergency response issues due to inadequate fire protection facilities, fire safety equipment, and human resources. Small-scale facilities that offer health care and medical services to mostly immobile patients face fire risks that differ significantly from general health care facilities. This paper focuses on fire risks in small-scale facilities and suggests a strategy for fire prevention and emergency response procedures, including countermeasures for fire risk assessment, management, and emergency response, in order to improve fire safety at these institutions in Taiwan.
Sikkema, Joel K; Alleman, James E; Ong, Say Kee; Wheelock, Thomas D
2011-09-15
The USEPA's 2010 mercury rule, which would reduce emissions from non-hazardous waste burning cement manufacturing facilities by an estimated 94%, represents a substantial regulatory challenge for the industry. These regulations, based on the performance of facilities that benefit from low concentrations of mercury in their feedstock and fuel inputs (e.g., limestone concentration was less than 25 ppb at each facility), will require non-compliant facilities to develop innovative controls. Control development is difficult because each facility's emissions must be assessed and simple correlation to mercury concentrations in limestone or an assumption of 'typically observed' mercury concentrations in inputs are unsupported by available data. Furthermore, atmospheric emissions are highly variable due to an internal control mechanism that captures and loops mercury between the high-temperature kiln and low-temperature raw materials mill. Two models have been reported to predict emissions; however, they have not been benchmarked against data from the internal components that capture mercury and do not distinguish between mercury species, which have different sorption and desorption properties. Control strategies include technologies applied from other industries and technologies developed specifically for cement facilities. Reported technologies, listed from highest to lowest anticipated mercury removal, include purge of collected dust or raw meal, changes in feedstocks and fuels, wet scrubbing, cleaning of mercury enriched dust, dry sorbent injection, and dry and semi-dry scrubbing. The effectiveness of these technologies is limited by an inadequate understanding of sorption, desorption, and mercury species involved in internal loop mercury control. To comply with the mercury rule and to improve current mercury control technologies and practices, research is needed to advance fundamental knowledge regarding mercury species sorption and desorption dynamics on materials within cement facilities. Copyright © 2011 Elsevier B.V. All rights reserved.
NASA Astrophysics Data System (ADS)
Vahdani, Behnam; Tavakkoli-Moghaddam, Reza; Jolai, Fariborz; Baboli, Arman
2013-06-01
This article seeks to offer a systematic approach to establishing a reliable network of facilities in closed loop supply chains (CLSCs) under uncertainties. Facilities that are located in this article concurrently satisfy both traditional objective functions and reliability considerations in CLSC network designs. To attack this problem, a novel mathematical model is developed that integrates the network design decisions in both forward and reverse supply chain networks. The model also utilizes an effective reliability approach to find a robust network design. In order to make the results of this article more realistic, a CLSC for a case study in the iron and steel industry has been explored. The considered CLSC is multi-echelon, multi-facility, multi-product and multi-supplier. Furthermore, multiple facilities exist in the reverse logistics network leading to high complexities. Since the collection centres play an important role in this network, the reliability concept of these facilities is taken into consideration. To solve the proposed model, a novel interactive hybrid solution methodology is developed by combining a number of efficient solution approaches from the recent literature. The proposed solution methodology is a bi-objective interval fuzzy possibilistic chance-constraint mixed integer linear programming (BOIFPCCMILP). Finally, computational experiments are provided to demonstrate the applicability and suitability of the proposed model in a supply chain environment and to help decision makers facilitate their analyses.
The development of the MELiSSA Pilot Plant Facility
NASA Astrophysics Data System (ADS)
Godia, Francesc; Dussap, Claude-Gilles; Dixon, Mike; Peiro, Enrique; Fossen, Arnaud; Lamaze, Brigitte; Brunet, Jean; Demey, Dries; Mas-Albaigès, Joan L.
MELiSSA (Micro-Ecological Life Support System Alternative) is a closed artificial ecosystem intended as a tool for the development of a bio-regenerative life support system for longterm manned missions. The MELiSSA loop is formed by five interconnected compartments, organized in three different loops (solid, liquid and gas). This compartments are microbial bioreactors and higher plant chambers. The MELiSSA Pilot Plant facility has been designed to achieve the preliminary terrestrial demonstration of the MELiSSA concept at pilot scale, using animals as a model for the crew compartent. The experience gained in the operation of such a facility will be highly relevant for planning future life support systems in Space. In this communication, the latests developments in the MELiSSA Pilot Plant will be reported. Particularly, the completion of the design phase and instalation of all the different compartments will be discussed in detail. Each of the compartments had to be designed and constructed according to very specific characteristics, associated to the biological systems to be cultured, as part of the complete MELiSSA loop (anerobic, oxygenic, thermophilic, heterotrophic, autotrophic, axenic, photosynthetic, etc.). Additionally, the sizing of each reactor (ranging from 8 to 100 Liters, depending of each particular compartment) should compile with the global integration scenario proposed, and with the final goal of connection of all compartments to provide a demonstration of the MELiSSA concept, and generate data for the design and operation of future biological life support systems.
Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-11
... Safety Board, Pulse Jet Mixing at the Waste Treatment and Immobilization Plant AGENCY: Department of..., concerning Pulse Jet Mixing at the Waste Treatment and Immobilization Plant was published in the Federal... Defense Nuclear Facilities Safety Board (Board) Recommendation 2010-2, Pulse Jet Mixing at the Waste...
DOE Office of Scientific and Technical Information (OSTI.GOV)
MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.
This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood ofmore » these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR.« less
ANTARES: Spacecraft Simulation for Multiple User Communities and Facilities
NASA Technical Reports Server (NTRS)
Acevedo, Amanda; Berndt, Jon; Othon, William; Arnold, Jason; Gay, Robet
2007-01-01
The Advanced NASA Technology Architecture for Exploration Studies (ANTARES) simulation is the primary tool being used for requirements assessment of the NASA Orion spacecraft by the Guidance Navigation and Control (GN&C) teams at Johnson Space Center (JSC). ANTARES is a collection of packages and model libraries that are assembled and executed by the Trick simulation environment. Currently, ANTARES is being used for spacecraft design assessment, performance analysis, requirements validation, Hardware In the Loop (HWIL) and Human In the Loop (HIL) testing.
340 Facility secondary containment and leak detection
DOE Office of Scientific and Technical Information (OSTI.GOV)
Bendixsen, R.B.
1995-01-31
This document presents a preliminary safety evaluation for the 340 Facility Secondary Containment and Leak Containment system, Project W-302. Project W-302 will construct Building 340-C which has been designed to replace the current 340 Building and vault tank system for collection of liquid wastes from the Pacific Northwest Laboratory buildings in the 300 Area. This new nuclear facility is Hazard Category 3. The vault tank and related monitoring and control equipment are Safety Class 2 with the remainder of the structure, systems and components as Safety Class 3 or 4.
Unresolved fine-scale structure in solar coronal loop-tops
DOE Office of Scientific and Technical Information (OSTI.GOV)
Scullion, E.; Van der Voort, L. Rouppe; Wedemeyer, S.
2014-12-10
New and advanced space-based observing facilities continue to lower the resolution limit and detect solar coronal loops in greater detail. We continue to discover even finer substructures within coronal loop cross-sections, in order to understand the nature of the solar corona. Here, we push this lower limit further to search for the finest coronal loop substructures, through taking advantage of the resolving power of the Swedish 1 m Solar Telescope/CRisp Imaging Spectro-Polarimeter (CRISP), together with co-observations from the Solar Dynamics Observatory/Atmospheric Image Assembly (AIA). High-resolution imaging of the chromospheric Hα 656.28 nm spectral line core and wings can, under certainmore » circumstances, allow one to deduce the topology of the local magnetic environment of the solar atmosphere where its observed. Here, we study post-flare coronal loops, which become filled with evaporated chromosphere that rapidly condenses into chromospheric clumps of plasma (detectable in Hα) known as a coronal rain, to investigate their fine-scale structure. We identify, through analysis of three data sets, large-scale catastrophic cooling in coronal loop-tops and the existence of multi-thermal, multi-stranded substructures. Many cool strands even extend fully intact from loop-top to footpoint. We discover that coronal loop fine-scale strands can appear bunched with as many as eight parallel strands within an AIA coronal loop cross-section. The strand number density versus cross-sectional width distribution, as detected by CRISP within AIA-defined coronal loops, most likely peaks at well below 100 km, and currently, 69% of the substructure strands are statistically unresolved in AIA coronal loops.« less
Shielded dual-loop resonator for arterial spin labeling at the neck.
Hetzer, Stefan; Mildner, Toralf; Driesel, Wolfgang; Weder, Manfred; Möller, Harald E
2009-06-01
To construct a dual-loop coil for continuous arterial spin labeling (CASL) at the human neck and characterize it using computer simulations and magnetic resonance experiments. The labeling coil was designed as a perpendicular pair of shielded-loop resonators made from coaxial cable to obtain balanced circular loops with minimal electrical interaction with the lossy tissue. Three different excitation modes depending on the phase shift, Deltapsi, of the currents driving the two circular loops were investigated including a "Maxwell mode" (Deltapsi = 0 degrees ; ie, opposite current directions in both loops), a "quadrature mode" (Deltapsi = 90 degrees ), and a "Helmholtz mode" (Deltapsi = 180 degrees ; ie, identical current directions in both loops). Simulations of the radiofrequency field distribution indicated a high inversion efficiency at the locations of the carotid and vertebral arteries. With a 7-mm-thick polypropylene insulation, a sufficient distance from tissue was achieved to guarantee robust performance at a local specific absorption rate (SAR) well below legal safety limits. Application in healthy volunteers at 3 T yielded quantitative maps of gray matter perfusion with low intersubject variability. The coil permits robust labeling with low SAR and minimal sensitivity to different loading conditions.
Occupational Safety Review of High Technology Facilities
DOE Office of Scientific and Technical Information (OSTI.GOV)
Lee Cadwallader
2005-01-31
This report contains reviews of operating experiences, selected accident events, and industrial safety performance indicators that document the performance of the major US DOE magnetic fusion experiments and particle accelerators. These data are useful to form a basis for the occupational safety level at matured research facilities with known sets of safety rules and regulations. Some of the issues discussed are radiation safety, electromagnetic energy exposure events, and some of the more widespread issues of working at height, equipment fires, confined space work, electrical work, and other industrial hazards. Nuclear power plant industrial safety data are also included for comparison.
Gardner, Lea Anne; Dubeck, Deborah
2016-08-01
The Pennsylvania Patient Safety Reporting System is a confidential, statewide Internet reporting system to which all Pennsylvania hospitals, outpatient-surgery facilities, birthing centers, and abortion facilities must file information on incidents and serious events.Safety Monitor is a column from Pennsylvania's Patient Safety Authority, the authority that informs nurses on issues that can affect patient safety and presents strategies they can easily integrate into practice. For more information on the authority, visit www.patientsafetyauthority.org. For the original article discussed in this column or for other articles on patient safety, click on "Patient Safety Advisories" and then "Advisory Library" in the left-hand navigation menu.
NASA Technical Reports Server (NTRS)
Wieland, Paul; Miller, Lee; Ibarra, Tom
2003-01-01
As part of the Sustaining Engineering program for the International Space Station (ISS), a ground simulator of the Internal Thermal Control System (ITCS) in the Lab Module was designed and built at the Marshall Space Flight Center (MSFC). To support prediction and troubleshooting, this facility is operationally and functionally similar to the flight system and flight-like components were used when available. Flight software algorithms, implemented using the LabVIEW(Registered Trademark) programming language, were used for monitoring performance and controlling operation. Validation testing of the low temperature loop was completed prior to activation of the Lab module in 2001. Assembly of the moderate temperature loop was completed in 2002 and validated in 2003. The facility has been used to address flight issues with the ITCS, successfully demonstrating the ability to add silver biocide and to adjust the pH of the coolant. Upon validation of the entire facility, it will be capable not only of checking procedures, but also of evaluating payload timelining, operational modifications, physical modifications, and other aspects affecting the thermal control system.
Nuclear Warheads: The Reliable Replacement Warhead Program and the Life Extension Program
2006-12-13
Defense Nuclear Facilities Safety Board was created by Congress 1988 "as an independent oversight organization within the Executive Branch charged... nuclear facilities ." U.S. Defense Nuclear Facilities Safety Board. “Who We Are,” at [http://www.dnfsb.gov/about/index.html]. involving CHE and plutonium...approach, if successful, would “reduce or eliminate the need for ESD controls.”42 Kent Fortenberry, Technical Director of the Defense Nuclear Facilities
Scaling analysis for the direct reactor auxiliary cooling system for FHRs
DOE Office of Scientific and Technical Information (OSTI.GOV)
Lv, Q.; Kim, I. H.; Sun, X.
2015-04-01
The Direct Reactor Auxiliary Cooling System (DRACS) is a passive residual heat removal system proposed for the Fluoride-salt-cooled High-temperature Reactor (FHR) that combines the coated particle fuel and graphite moderator with a liquid fluoride salt as the coolant. The DRACS features three natural circulation/convection loops that rely on buoyancy as the driving force and are coupled via two heat exchangers, namely, the DRACS heat exchanger and the natural draft heat exchanger. A fluidic diode is employed to minimize the parasitic flow into the DRACS primary loop and correspondingly the heat loss to the DRACS during reactor normal operation, and tomore » activate the DRACS in accidents when the reactor is shut down. While the DRACS concept has been proposed, there are no actual prototypic DRACS systems for FHRs built or tested in the literature. In this paper, a detailed scaling analysis for the DRACS is performed, which will provide guidance for the design of scaled-down DRACS test facilities. Based on the Boussinesq assumption and one-dimensional flow formulation, the governing equations are non-dimensionalized by introducing appropriate dimensionless parameters. The key dimensionless numbers that characterize the DRACS system are obtained from the non-dimensional governing equations. Based on the dimensionless numbers and non-dimensional governing equations, similarity laws are proposed. In addition, a scaling methodology has been developed, which consists of a core scaling and a loop scaling. The consistency between the core and loop scaling is examined via the reference volume ratio, which can be obtained from both the core and loop scaling processes. The scaling methodology and similarity laws have been applied to obtain a scientific design of a scaled-down high-temperature DRACS test facility.« less
DOE Office of Scientific and Technical Information (OSTI.GOV)
Lagier, B.; Rousset, B.; Hoa, C.
Superconducting magnets used in tokamaks undergo periodic heat load caused by cycling plasma operations inducing AC losses, neutrons fluxes and eddy currents in magnet structures. In the cryogenic system of JT60-SA tokamak, the Auxiliary Cold Box (ACB) distributes helium from the refrigerator to the cryogenic users and in particular to the superconducting magnets. ACB comprises a saturated helium bath with immersed heat exchangers, extracting heat from independent cooling loops. The supercritical helium flow in each cooling loop is driven by a cold circulator. In order to safely operate the refrigerator during plasma pulses, the interface between the ACB and themore » refrigerator shall be as stable as possible, with well-balanced bath inlet and outlet mass flows during cycling operation. The solution presented in this paper relies on a combination of regulations to smooth pulsed heat loads and to keep a constant refrigeration power during all the cycle. Two smoothing strategies are presented, both regulating the outlet mass flow of the bath: the first one using the bath as a thermal buffer and the second one storing energy in the loop by varying the cold circulator speed. The bath outlet mass flow is also controlled by an immersed resistive heater which enables a constant evaporation rate in the bath when power coming from the loops is decreasing. The refrigeration power is controlled so that the compensating power remains within an acceptable margin. Experimental validation is achieved using the HELIOS facility. This facility running at CEA Grenoble since 2010 is a scaled down model of the ACB bath and Central Solenoid magnet cooling loop of the JT60-SA tokamak. Test results show performances and robustness of the regulations.« less
Flow and Heat Transfer Tests in New Loop at 2757 kPa (400 psi)
DOE Office of Scientific and Technical Information (OSTI.GOV)
Woloshun, Keith Albert
2016-06-13
A helium flow and heat transfer experiment has been designed for the new helium flow loop facility at LANL. This new facility is centered on an Aerzen GM 12.4 Root’s blower, selected for operation at higher pressure, up to 2757 kPa, and mass flow rate, up to 400 g/s. This replaces the previous Tuthill PD plus 3206 blower and loop limited to 2067 kPa (300 psi) and 100 g/s. The resistively heated test piece is comprised of 7 electric heaters with embedded thermocouples. The plant design for the Mo100 to Mo99 targets requires sharp bends and geometry changes in themore » helium flow tube immediately before and after the target. An idealized fully developed flow configuration with straight entry and exit will be tested and compared with an option that employs rectangular tubing to make the bend at a radius consistent with and practical for the actual plant design. The current plant design, with circular tubing and a sudden contraction to rectangular just prior to target entrance, will also be tested. This requires some modification of the test piece, as described in the report.« less
High-resolution retinal imaging through open-loop adaptive optics
NASA Astrophysics Data System (ADS)
Li, Chao; Xia, Mingliang; Li, Dayu; Mu, Quanquan; Xuan, Li
2010-07-01
Using the liquid crystal spatial light modulator (LC-SLM) as the wavefront corrector, an open-loop adaptive optics (AO) system for fundus imaging in vivo is constructed. Compared with the LC-SLM closed-loop AO system, the light energy efficiency is increased by a factor of 2, which is helpful for the safety of fundus illumination in vivo. In our experiment, the subjective accommodation method is used to precorrect the defocus aberration, and three subjects with different myopia 0, -3, and -5 D are tested. Although the residual wavefront error after correction cannot to detected, the fundus images adequately demonstrate that the imaging system reaches the resolution of a single photoreceptor cell through the open-loop correction. Without dilating and cyclopleging the eye, the continuous imaging for 8 s is recorded for one of the subjects.
DOE Office of Scientific and Technical Information (OSTI.GOV)
NONE
1999-02-01
This is the ninth Annual Report to the Congress describing Department of Energy (Department) activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of energy regarding public health and safety issues at the Department`s defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department`s defense nuclear facilities. The locations of the majormore » Department facilities are provided. During 1998, Departmental activities resulted in the proposed closure of one Board recommendation. In addition, the Department has completed all implementation plan milestones associated with four other Board recommendations. Two new Board recommendations were received and accepted by the Department in 1998, and two new implementation plans are being developed to address these recommendations. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, a renewed effort to increase the technical capabilities of the federal workforce, and a revised plan for stabilizing excess nuclear materials to achieve significant risk reduction.« less
NREL's Energy Systems Integration Facility Garners LEED® Platinum | News
U.S. Green Building Council (USGBC), a non-profit organization dedicated to sustainable building experimental laboratories and several outdoor test beds, including an interactive hardware-in-the-loop system
Federal Register 2010, 2011, 2012, 2013, 2014
2012-11-23
... MOX Services (Mixed Oxide Fuel Fabrication Facility); Notice of Atomic Safety and Licensing Board Reconstitution Pursuant to 10 CFR 2.313(c) and 2.321(b), the Atomic Safety and Licensing Board (Board) in the... Rockville, Maryland this 16th day of November 2012. E. Roy Hawkens, Chief Administrative Judge, Atomic...
DOE Office of Scientific and Technical Information (OSTI.GOV)
Mirro, G.A.
1997-02-01
This paper presents an overview of issues related to handling NORM materials, and provides a description of a facility designed for the processing of NORM contaminated equipment. With regard to handling NORM materials the author discusses sources of NORM, problems, regulations and disposal options, potential hazards, safety equipment, and issues related to personnel protection. For the facility, the author discusses: description of the permanent facility; the operations of the facility; the license it has for handling specific radioactive material; operating and safety procedures; decontamination facilities on site; NORM waste processing capabilities; and offsite NORM services which are available.
A security/safety survey of long term care facilities.
Acorn, Jonathan R
2010-01-01
What are the major security/safety problems of long term care facilities? What steps are being taken by some facilities to mitigate such problems? Answers to these questions can be found in a survey of IAHSS members involved in long term care security conducted for the IAHSS Long Term Care Security Task Force. The survey, the author points out, focuses primarily on long term care facilities operated by hospitals and health systems. However, he believes, it does accurately reflect the security problems most long term facilities face, and presents valuable information on security systems and practices which should be also considered by independent and chain operated facilities.
An Environmental for Hardware-in-the-Loop Formation Navigation and Control
NASA Technical Reports Server (NTRS)
Burns, Rich; Naasz, Bo; Gaylor, Dave; Higinbotham, John
2004-01-01
Recent interest in formation flying satellite systems has spurred a considerable amount of research in the relative navigation and control of satellites. Development in this area has included new estimation and control algorithms as well as sensor and actuator development specifically geared toward the relative control problem. This paper describes a simulation facility, the Formation Flying Test Bed (FFTB) at NASA Goddard Space Flight Center, which allows engineers to test new algorithms for the formation flying problem with relevant GN&C hardware in a closed loop simulation. The FFTB currently supports the inclusion of GPS receiver hardware in the simulation loop. Support for satellite crosslink ranging technology is at a prototype stage. This closed-loop, hardware inclusive simulation capability permits testing of navigation and control software in the presence of the actual hardware with which the algorithms must interact. This capability provides the navigation or control developer with a perspective on how the algorithms perform as part of the closed-loop system. In this paper, the overall design and evolution of the FFTB are presented. Each component of the FFTB is then described. Interfaces between the components of the FFTB are shown and the interfaces to and between navigation and control software are described. Finally, an example of closed-loop formation control with GPS receivers in the loop is presented.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Haverkamp, B.; Krone, J.; Shybetskyi, I.
The Radioactive Waste Disposal Facility (RWDF) Buryakovka was constructed in 1986 as part of the intervention measures after the accident at Chernobyl NPP (ChNPP). Today, RWDF Buryakovka is still being operated but its maximum capacity is nearly reached. Plans for enlargement of the facility exist since more than 10 years but have not been implemented yet. In the framework of an European Commission Project DBE Technology GmbH prepared a safety analysis report of the facility in its current state (SAR) and a preliminary safety analysis report (PSAR) based on the planned enlargement. Due to its history RWDF Buryakovka does notmore » fully comply with today's best international practices and the latest Ukrainian regulations in this area. The most critical aspects are its inventory of long-lived radionuclides, and the non-existent multi-barrier waste confinement system. A significant part of the project was dedicated, therefore, to the development of a methodology for the safety assessment taking into consideration the facility's special situation and to reach an agreement with all stakeholders involved in the later review and approval procedure of the safety analysis reports. Main aspect of the agreed methodology was to analyze the safety, not strictly based on regulatory requirements but on the assessment of the actual situation of the facility including its location within the Exclusion Zone. For both safety analysis reports, SAR and PSAR, the assessment of the long-term safety led to results that were either within regulatory limits or within the limits allowing for a specific situational evaluation by the regulator. (authors)« less
DOE Office of Scientific and Technical Information (OSTI.GOV)
Nero, A.V.; Quinby-Hunt, M.S.
1977-01-01
This report sets forth methodologies for review of the health and safety aspects of proposed nuclear, geothermal, and fossil-fuel sites and facilities for electric power generation. The review is divided into a Notice of Intention process and an Application for Certification process, in accordance with the structure to be used by the California Energy Resources Conservation and Development Commission, the first emphasizing site-specific considerations, the second examining the detailed facility design as well. The Notice of Intention review is divided into three possible stages: an examination of emissions and site characteristics, a basic impact analysis, and an assessment of publicmore » impacts. The Application for Certification review is divided into five possible stages: a review of the Notice of Intention treatment, review of the emission control equipment, review of the safety design, review of the general facility design, and an overall assessment of site and facility acceptability.« less
Integration of functional safety systems on the Daniel K. Inouye Solar Telescope
NASA Astrophysics Data System (ADS)
Williams, Timothy R.; Hubbard, Robert P.; Shimko, Steve
2016-07-01
The Daniel K. Inouye Solar Telescope (DKIST) was envisioned from an early stage to incorporate a functional safety system to ensure the safety of personnel and equipment within the facility. Early hazard analysis showed the need for a functional safety system. The design used a distributed approach in which each major subsystem contains a PLC-based safety controller. This PLC-based system complies with the latest international standards for functional safety. The use of a programmable controller also allows for flexibility to incorporate changes in the design of subsystems without adversely impacting safety. Various subsystems were built by different contractors and project partners but had to function as a piece of the overall control system. Using distributed controllers allows project contractors and partners to build components as standalone subsystems that then need to be integrated into the overall functional safety system. Recently factory testing was concluded on the major subsystems of the facility. Final integration of these subsystems is currently underway on the site. Building on lessons learned in early factory tests, changes to the interface between subsystems were made to improve the speed and ease of integration of the entire system. Because of the distributed design each subsystem can be brought online as it is delivered and assembled rather than waiting until the entire facility is finished. This enhances safety during the risky period of integration and testing. The DKIST has implemented a functional safety system that has allowed construction of subsystems in geographically diverse locations but that function cohesively once they are integrated into the facility currently under construction.
Finch, Caroline F; Otago, Leonie; White, Peta; Donaldson, Alex; Mahoney, Mary
2011-06-01
Multi-purpose recreation facilities (MPRFs) are a popular setting for physical activity and it is therefore important that they are safe for all patrons. However, the attitudes of MPRF users towards safety are a potential barrier to the success of injury prevention programmes implemented within MPRFs. This article reports a survey of the safety attitudes of over 700 users of four indoor MPRFs. Factor analysis of 12 five-point Likert scale statements showed that the attitudes clustered around three major dimensions - the importance of safety, the benefits of safety and the perceptions of injury risk. Together, these three dimensions accounted for 49% of the variability in the attitudes. More than 85% of respondents agreed/strongly agreed that: safety was an important aspect of physical activity participation; being injured affected enjoyment of physical activity; people should adopt appropriate safety measures for all physical activity; and individuals were responsible for their own safety. The MPRF users, particularly women and older people, were generally safety conscious, believed in adopting safety measures, and were willing to take responsibility for their own safety. Facility managers can be confident that if they provide evidence-based injury prevention interventions in these settings, then users will respond appropriately and adopt the promoted behaviours.
Recent Accomplishments and Future Directions in US Fusion Safety & Environmental Program
DOE Office of Scientific and Technical Information (OSTI.GOV)
David A. Petti; Brad J. Merrill; Phillip Sharpe
2006-07-01
The US fusion program has long recognized that the safety and environmental (S&E) potential of fusion can be attained by prudent materials selection, judicious design choices, and integration of safety requirements into the design of the facility. To achieve this goal, S&E research is focused on understanding the behavior of the largest sources of radioactive and hazardous materials in a fusion facility, understanding how energy sources in a fusion facility could mobilize those materials, developing integrated state of the art S&E computer codes and risk tools for safety assessment, and evaluating S&E issues associated with current fusion designs. In thismore » paper, recent accomplishments are reviewed and future directions outlined.« less
ERIC Educational Resources Information Center
Bell, Darnell Brushawn
2011-01-01
The purpose of the study was to understand the relationships among facility conditions, school climate, and school safety of high school tenth graders in the United States. Previous research on the quality of educational facilities influence on student achievement has varied. Recent research has suggested that the quality of educational facilities…
76 FR 57980 - Senior Executive Service Performance Review Board
Federal Register 2010, 2011, 2012, 2013, 2014
2011-09-19
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Senior Executive Service Performance Review Board AGENCY... the Defense Nuclear Facilities Safety Board (DNFSB) Senior Executive Service (SES) Performance Review... summary rating of the senior executive's performance, the executive's response, and the higher level...
78 FR 55244 - Senior Executive Service Performance Review Board; Membership
Federal Register 2010, 2011, 2012, 2013, 2014
2013-09-10
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Senior Executive Service Performance Review Board... the membership of the Defense Nuclear Facilities Safety Board (DNFSB) Senior Executive Service (SES... rating of a senior executive's performance, the executive's response, and the higher level official's...
77 FR 54570 - Senior Executive Service Performance Review Board
Federal Register 2010, 2011, 2012, 2013, 2014
2012-09-05
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Senior Executive Service Performance Review Board AGENCY... the Defense Nuclear Facilities Safety Board (DNFSB) Senior Executive Service (SES) Performance Review.... The PRB shall review and evaluate the initial summary rating of the senior executive's performance...
24 CFR 232.515 - Refund of fees.
Code of Federal Regulations, 2011 CFR
2011-04-01
... INSURANCE FOR NURSING HOMES, INTERMEDIATE CARE FACILITIES, BOARD AND CARE HOMES, AND ASSISTED LIVING FACILITIES Eligibility Requirements-Supplemental Loans To Finance Purchase and Installation of Fire Safety... that the installation of fire safety equipment for the project has been prevented because of...
34 CFR 75.683 - Health or safety standards for facilities.
Code of Federal Regulations, 2010 CFR
2010-07-01
... Conditions Must Be Met by a Grantee? Other Requirements for Certain Projects § 75.683 Health or safety... to the facilities that the grantee uses for the project. (Authority: 20 U.S.C. 1221e-3 and 3474) ...
77 FR 34457 - Pipeline Safety: Mechanical Fitting Failure Reports
Federal Register 2010, 2011, 2012, 2013, 2014
2012-06-11
... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... notice provides clarification to owners and operators of gas distribution pipeline facilities when... of a gas distribution pipeline facility to file a written report for any mechanical fitting failure...
77 FR 61826 - Pipeline Safety: Communication During Emergency Situations
Federal Register 2010, 2011, 2012, 2013, 2014
2012-10-11
... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... liquefied natural gas pipeline facilities that operators should immediately and directly notify the Public.... Background Federal regulations for gas, liquefied natural gas (LNG), and hazardous liquid pipeline facilities...
Updating fire safety standards. Final rule; affirmation.
2011-11-16
This document affirms as final, without changes, a provision included in a final rule with request for comments that amended the Department of Veterans Affairs (VA) regulations concerning community residential care facilities, contract facilities for certain outpatient and residential services, and State home facilities. That provision established a five-year period within which all covered buildings with nursing home facilities existing as of June 25, 2001, must conform to the automatic sprinkler requirement of the 2009 edition of the National Fire Protection Association (NFPA) 101. This rule helps ensure the safety of veterans in the affected facilities.
Caring for class III obese patients.
Gardner, Lea Anne
2013-11-01
The Pennsylvania Patient Safety Reporting System is a confidential, statewide Internet reporting system to which all Pennsylvania hospitals, outpatient-surgery facilities, and birthing centers, as well as some abortion facilities, must file information on medical errors.Safety Monitor is a column from Pennsylvania's Patient Safety Authority, the authority that informs nurses on issues that can affect patient safety and presents strategies they can easily integrate into practice. For more information on the authority, visit www.patientsafetyauthority.org. For the original article discussed in this column or for other articles on patient safety, click on "Patient Safety Advisories" and then "Advisory Library" in the left-hand navigation menu.
DOE Office of Scientific and Technical Information (OSTI.GOV)
G. L. Sharp; R. T. McCracken
The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The reactor also provides other irradiation services such as radioisotope production. The ATR and its support facilities are located at the Test Reactor Area of the Idaho National Engineering and Environmental Laboratory (INEEL). An audit conducted by the Department of Energy's Office of Independent Oversight and Performance Assurance (DOE OA) raised concerns that design conditions at the ATR were not adequately analyzedmore » in the safety analysis and that legacy design basis management practices had the potential to further impact safe operation of the facility.1 The concerns identified by the audit team, and issues raised during additional reviews performed by ATR safety analysts, were evaluated through the unreviewed safety question process resulting in shutdown of the ATR for more than three months while these concerns were resolved. Past management of the ATR safety basis, relative to facility design basis management and change control, led to concerns that discrepancies in the safety basis may have developed. Although not required by DOE orders or regulations, not performing design basis verification in conjunction with development of the 10 CFR 830 Subpart B upgraded safety basis allowed these potential weaknesses to be carried forward. Configuration management and a clear definition of the existing facility design basis have a direct relation to developing and maintaining a high quality safety basis which properly identifies and mitigates all hazards and postulated accident conditions. These relations and the impact of past safety basis management practices have been reviewed in order to identify lessons learned from the safety basis upgrade process and appropriate actions to resolve possible concerns with respect to the current ATR safety basis. The need for a design basis reconstitution program for the ATR has been identified along with the use of sound configuration management principles in order to support safe and efficient facility operation.« less
TRAC-PF1 code verification with data from the OTIS test facility. [Once-Through Intergral System
DOE Office of Scientific and Technical Information (OSTI.GOV)
Childerson, M.T.; Fujita, R.K.
1985-01-01
A computer code (TRAC-PF1/MOD1) developed for predicting transient thermal and hydraulic integral nuclear steam supply system (NSSS) response was benchmarked. Post-small break loss-of-coolant accident (LOCA) data from a scaled, experimental facility, designated the One-Through Integral System (OTIS), were obtained for the Babcock and Wilcox NSSS and compared to TRAC predictions. The OTIS tests provided a challenging small break LOCA data set for TRAC verification. The major phases of a small break LOCA observed in the OTIS tests included pressurizer draining and loop saturation, intermittent reactor coolant system circulation, boiler-condenser mode, and the initial stages of refill. The TRAC code wasmore » successful in predicting OTIS loop conditions (system pressures and temperatures) after modification of the steam generator model. In particular, the code predicted both pool and auxiliary-feedwater initiated boiler-condenser mode heat transfer.« less
Simulation of German PKL refill/reflood experiment K9A using RELAP4/MOD7. [PWR
DOE Office of Scientific and Technical Information (OSTI.GOV)
Hsu, M.T.; Davis, C.B.; Behling, S.R.
This paper describes a RELAP4/MOD7 simulation of West Germany's Kraftwerk Union (KWU) Primary Coolant Loop (PKL) refill/reflood experiment K9A. RELAP4/MOD7, a best-estimate computer program for the calculation of thermal and hydraulic phenomena in a nuclear reactor or related system, is the latest version in the RELAP4 code development series. This study was the first major simulation using RELAP4/MOD7 since its release by the Idaho National Engineering Laboratory (INEL). The PKL facility is a reduced scale (1:134) representation of a typical West German four-loop 1300 MW pressurized water reactor (PWR). A prototypical scale of the total volume to power ratio wasmore » maintained. The test facility was designed specifically for an experiment simulating the refill/reflood phase of a Loss-of-Coolant Accident (LOCA).« less
Corrosion detector apparatus for universal assessment of pollution in data centers
Hamann, Hendrik F.; Klein, Levente I.
2015-08-18
A compact corrosion measurement apparatus and system includes an air fan, a corrosion sensor, a temperature sensor, a humidity sensor, a heater element, and an air flow sensor all under control to monitor and maintain constant air parameters in an environment and minimize environmental fluctuations around the corrosion sensor to overcome the variation commonly encountered in corrosion rate measurement. The corrosion measurement apparatus includes a structure providing an enclosure within which are located the sensors. Constant air flow and temperature is maintained within the enclosure where the corrosion sensor is located by integrating a variable speed air fan and a heater with the corresponding feedback loop control. Temperature and air flow control loops ensure that corrosivity is measured under similar conditions in different facilities offering a general reference point that allow a one to one comparison between facilities with similar or different pollution levels.
Production Facility Prototype Blower 1000 Hour Test Results II
DOE Office of Scientific and Technical Information (OSTI.GOV)
Wass, Alexander Joseph; Woloshun, Keith Albert; Dale, Gregory E.
Long duration tests of the Aerzen GM 12.4 roots style blower in a closed loop configuration provides valuable data and lessons learned for long-term operation at the Mo-99 production facility. The blower was operated in a closed loop configuration with the flow conditions anticipated in plant operation with a Mo-100 target inline. The additional thermal energy generated from beam heating of the Mo-100 disks were not included in these tests. Five 1000 hour tests have been completed since the first test was performed in January of 2016. All five 1000 hour tests have proven successful in exposing preventable issues relatedmore » to oil and helium leaks. All blower tests to this date have resulted in stable blower performance and consistency. A summary of the results for each test, including a review of the first and second tests, are included in this report.« less
DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
The objectives of the Ingham County Solar Project include: the demonstration of a major operational supplement to fossil fuels, thereby reducing the demand for non-renewable energy sources, demonstration of the economic and technical feasibility of solar systems as an important energy supplement over the expected life of the building, and to encourage Michigan industry to produce and incorporate solar systems in their own facility. The Ingham County solar system consists of approximately 10,000 square feet of solar collectors connected in a closed configuration loop. The primary loop solution is a mixture of water and propylene glycol which flows through themore » tube side of a heat exchanger connected to the primary storage tank. The heat energy which is supplied to the primary storage tank is subsequently utilized to increase the temperature of the laundry water, kitchen water, and domestic potable water.« less
16 CFR Figures 3 and 4 to Part 1204 - High Voltage Test Facility and Antenna System Test Setup
Code of Federal Regulations, 2012 CFR
2012-01-01
... 16 Commercial Practices 2 2012-01-01 2012-01-01 false High Voltage Test Facility and Antenna System Test Setup 3 Figures 3 and 4 to Part 1204 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY STANDARD FOR OMNIDIRECTIONAL CITIZENS BAND BASE STATION ANTENNAS Pt. 1204, Figs. 3, 4 Figures 3 and 4...
ERIC Educational Resources Information Center
Smith, Ann
1982-01-01
Discusses four elements of safety programs: (1) safety training; (2) safety inspections; (3) accident investigations; and (4) protective safety equipment. Also discusses safety considerations in water/wastewater treatment facilities focusing on falls, drowning hazards, trickling filters, confined space entry, collection/distribution system safety,…
The Sepsis Early Recognition and Response Initiative (SERRI)
Jones, Stephen L.; Ashton, Carol M.; Kiehne, Lisa; Gigliotti, Elizabeth; Bell-Gordon, Charyl; Pinn, Teresa T.; Tran, Shirley K.; Nicolas, Juan C.; Rose, Alexis L.; Shirkey, Beverly A.; Disbot, Maureen; Masud, Faisal; Wray, Nelda P.
2016-01-01
Duration of Initiative 48 months and currently ongoing. Setting The Houston Methodist Hospital System and affiliated hospitals (3 facilities with 2 hospital-run skilled nursing facilities in and around Houston), St. Joseph’s Regional Health Center (1 acute care hospital and 2 skilled nursing facilities in Bryan, Texas), Hospital Corporation of America (2 acute care facilities in Houston, 1 acute care facility in McAllen, Texas [Rio Grande Valley]), Kindred Healthcare (2 long term acute care facilities in Houston), Select Medical Specialty Hospitals (2 long term acute care facilities in Houston). Whom This Should Concern Hospital administrators, quality and safety officers, performance improvement and patient safety professionals, clinic managers, infection control and prevention staff, and other physicians, nurses, and clinical staff. PMID:26892701
A Pilot Assessment of Occupational Health Hazards in the US Electronic Scrap Recycling Industry
Ceballos, Diana M.; Gong, Wei; Page, Elena
2015-01-01
The National Institute for Occupational Safety and Health (NIOSH) surveyed a randomly selected sample of electronic scrap (e-scrap) recycling facilities nationwide to characterize work processes, exposures, and controls. Despite multiple attempts to contact 278 facilities, only 47 responded (17% response rate). Surveyed facilities reported recycling a wide variety of electronics. The most common recycling processes were manual dismantling and sorting. Other processes included shredding, crushing, and automated separation. Many facilities reported that they had health and safety programs in place. However, some facilities reported the use of compressed air for cleaning, a practice that can lead to increased employee dust exposures, and some facilities allowed food and drinks in the production areas, a practice that can lead to ingestion of contaminants. Although our results may not be generalizable to all US e-scrap recycling facilities, they are informative regarding health and safety programs in the industry. We concluded that e-scrap recycling has the potential for a wide variety of occupational exposures particularly because of the frequent use of manual processes. On-site evaluations of e-scrap recyclers are needed to determine if reported work processes, practices, and controls are effective and meet current standards and guidelines. Educating the e-scrap recycling industry about health and safety best practices, specifically related to safe handling of metal dust, would help protect employees. PMID:25738822
A Pilot Assessment of Occupational Health Hazards in the US Electronic Scrap Recycling Industry.
Ceballos, Diana M; Gong, Wei; Page, Elena
2015-01-01
The National Institute for Occupational Safety and Health (NIOSH) surveyed a randomly selected sample of electronic scrap (e-scrap) recycling facilities nationwide to characterize work processes, exposures, and controls. Despite multiple attempts to contact 278 facilities, only 47 responded (17% response rate). Surveyed facilities reported recycling a wide variety of electronics. The most common recycling processes were manual dismantling and sorting. Other processes included shredding, crushing, and automated separation. Many facilities reported that they had health and safety programs in place. However, some facilities reported the use of compressed air for cleaning, a practice that can lead to increased employee dust exposures, and some facilities allowed food and drinks in the production areas, a practice that can lead to ingestion of contaminants. Although our results may not be generalizable to all US e-scrap recycling facilities, they are informative regarding health and safety programs in the industry. We concluded that e-scrap recycling has the potential for a wide variety of occupational exposures particularly because of the frequent use of manual processes. On-site evaluations of e-scrap recyclers are needed to determine if reported work processes, practices, and controls are effective and meet current standards and guidelines. Educating the e-scrap recycling industry about health and safety best practices, specifically related to safe handling of metal dust, would help protect employees.
Hardware-in-the-Loop Rendezvous Tests of a Novel Actuators Command Concept
NASA Astrophysics Data System (ADS)
Gomes dos Santos, Willer; Marconi Rocco, Evandro; Boge, Toralf; Benninghoff, Heike; Rems, Florian
2016-12-01
Integration, test and validation results, in a real-time environment, of a novel concept for spacecraft control are presented in this paper. The proposed method commands simultaneously a group of actuators optimizing a given set of objective functions based on a multiobjective optimization technique. Since close proximity maneuvers play an important role in orbital servicing missions, the entire GNC system has been integrated and tested at a hardware-in-the-loop (HIL) rendezvous and docking simulator known as European Proximity Operations Simulator (EPOS). During the test campaign at EPOS facility, a visual camera has been used to provide the necessary measurements for calculating the relative position with respect to the target satellite during closed-loop simulations. In addition, two different configurations of spacecraft control have been considered in this paper: a thruster reaction control system and a mixed actuators mode which includes thrusters, reaction wheels, and magnetic torqrods. At EPOS, results of HIL closed-loop tests have demonstrated that a safe and stable rendezvous approach can be achieved with the proposed GNC loop.
Surrogate Safety Assessment Model and Validation : Final Report
DOT National Transportation Integrated Search
2008-06-01
Safety of traffic facilities is most often measured by counting the number (and severity) of crashes that occur. It is not possible to apply such a measurement technique to traffic facility designs that have not yet been built or deployed in the real...
75 FR 56999 - Senior Executive Service Performance Review Board
Federal Register 2010, 2011, 2012, 2013, 2014
2010-09-17
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Senior Executive Service Performance Review Board AGENCY... the Defense Nuclear Facilities Safety Board (DNFSB) Senior Executive Service (SES) Performance Review... performance review boards. The PRB shall review and evaluate the initial summary rating of the senior...
The effect of motorcycle travel on the safety and operations of HOV facilities in Virginia.
DOT National Transportation Integrated Search
1995-01-01
The Intermodal Surface Transportation Efficiency Act of 1991 mandated that motorcycles be permitted to travel on federally funded high-occupancy vehicle (HOV) facilities unless they created a safety hazard or adversely affected HOV operations. Althou...
Preschool Comes to School: Design Concerns of Preschool Facilities.
ERIC Educational Resources Information Center
Passantino, Richard J.
1994-01-01
Addresses design and safety issues of which school business administrators should be aware when they become involved in integrating a preschool facility with an elementary school. Discusses building environmental factors, safety, health codes, play surfaces, energy conservation, and architectural considerations. (KDP)
A bicycle safety index for evaluating urban street facilities.
Asadi-Shekari, Zohreh; Moeinaddini, Mehdi; Zaly Shah, Muhammad
2015-01-01
The objectives of this research are to conceptualize the Bicycle Safety Index (BSI) that considers all parts of the street and to propose a universal guideline with microscale details. A point system method comparing existing safety facilities to a defined standard is proposed to estimate the BSI. Two streets in Singapore and Malaysia are chosen to examine this model. The majority of previous measurements to evaluate street conditions for cyclists usually cannot cover all parts of streets, including segments and intersections. Previous models also did not consider all safety indicators and cycling facilities at a microlevel in particular. This study introduces a new concept of a practical BSI to complete previous studies using its practical, easy-to-follow, point system-based outputs. This practical model can be used in different urban settings to estimate the level of safety for cycling and suggest some improvements based on the standards.
Real-time monitoring of CO2 storage sites: Application to Illinois Basin-Decatur Project
Picard, G.; Berard, T.; Chabora, E.; Marsteller, S.; Greenberg, S.; Finley, R.J.; Rinck, U.; Greenaway, R.; Champagnon, C.; Davard, J.
2011-01-01
Optimization of carbon dioxide (CO2) storage operations for efficiency and safety requires use of monitoring techniques and implementation of control protocols. The monitoring techniques consist of permanent sensors and tools deployed for measurement campaigns. Large amounts of data are thus generated. These data must be managed and integrated for interpretation at different time scales. A fast interpretation loop involves combining continuous measurements from permanent sensors as they are collected to enable a rapid response to detected events; a slower loop requires combining large datasets gathered over longer operational periods from all techniques. The purpose of this paper is twofold. First, it presents an analysis of the monitoring objectives to be performed in the slow and fast interpretation loops. Second, it describes the implementation of the fast interpretation loop with a real-time monitoring system at the Illinois Basin-Decatur Project (IBDP) in Illinois, USA. ?? 2011 Published by Elsevier Ltd.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Cash, R.J.; Dukelow, G.T.; Forbes, C.J.
1993-03-01
This is the seventh quarterly report on the progress of activities addressing safety issues associated with Hanford Site high-level radioactive waste tanks that contain ferrocyanide compounds. In the presence of oxidizing materials, such as nitrates or nitrites, ferrocyanide can be made to explode in the laboratory by heating it to high temperatures [above 285{degrees}C (545{degrees}F)]. In the mid 1950s approximately 140 metric tons of ferrocyanide were added to 24 underground high-level radioactive waste tanks. An implementation plan (Cash 1991) responding to the Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990) was issued in March 1991 describing the activities thatmore » were planned and underway to address each of the six parts of Recommendation 90-7. A revision to the original plan was transmitted to US Department of Energy by Westinghouse Hanford Company in December 1992. Milestones completed this quarter are described in this report. Contents of this report include: Introduction; Defense Nuclear Facilities Safety Board Implementation Plan Task Activities (Defense Nuclear Facilities Safety Board Recommendation for enhanced temperature measurement, Recommendation for continuous temperature monitoring, Recommendation for cover gas monitoring, Recommendation for ferrocyanide waste characterization, Recommendation for chemical reaction studies, and Recommendation for emergency response planning); Schedules; and References. All actions recommended by the Defense Nuclear Facilities Safety Board for emergency planning by Hanford Site emergency preparedness organizations have been completed.« less
2005-05-24
of Intent to Dispose of Soil Contaminated by Virgin Petroleum or equivalent form would be completed. The proposed Wing HQ Facility would include the...quadrant of the base. The overhead feeder, which includes some underground segments , is operated as a closed double loop system and serves the...weekends, weather, and holidays ). Using data from the National Oceanic and Atmospheric Administration, the average soil percent moisture was estimated
Fiber-To-The-Home: Current Issues And Strategies For A Bell Operating Company
NASA Astrophysics Data System (ADS)
Engel, Joel
1990-01-01
This decade has seen extensive use of fiber in the telephone network. Fiber is already pervasive in interoffice facilities, and is now being introduced into the local loop, which represents 90% of telephone circuit miles. In the feeder portion of the loop, the connection between the central office and remote terminals, fiber has already made significant inroads. In fact, Ameritech has more route miles of fiber in each of its five states than is in the entire network of the interexchange carrier whose advertisements stress their use of fiber.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Denslow, Kayte M.; Bontha, Jagannadha R.; Adkins, Harold E.
This document presents the visual and ultrasonic PulseEcho critical velocity test results obtained from the System Performance test campaign that was completed in September 2012 with the Remote Sampler Demonstration (RSD)/Waste Feed Flow Loop cold-test platform located at the Monarch test facility in Pasco, Washington. This report is intended to complement and accompany the report that will be developed by WRPS on the design of the System Performance simulant matrix, the analysis of the slurry test sample concentration and particle size distribution (PSD) data, and the design and construction of the RSD/Waste Feed Flow Loop cold-test platform.
Vermeulen, J A; Kleefstra, S M; Zijp, E M; Kool, R B
2017-07-06
In 2009, the Dutch Health Care Inspectorate (IGZ) observed several serious risks to safety involving medication within elderly care facilities. However, by 2011, high risks had been reduced in almost all the organisations we visited. And yet the IGZ analysed too the alarming increase in the number of incidents arising in the self-reported national indicator of medication safety between 2009 and 2010. The aim of this study was to understand the factors that can explain this contradiction between the increase in self-reported medication incidents and the observation of the IGZ in reducing the risks to medication safety through supervision. We interviewed health care professionals of ten care facilities, visited by the IGZ, who were involved in, or responsible for, the improvement of medication safety in their institutions. As outcome measures we used the rate of medication safety risk per facility; the perceptions of the participant with regard to the reports of medication incidents; the level of medication safety of the facility; the measures used to improve medication safety; and the supervision of medication safety. This was a mixed methods study, qualitative in that we used semi-structured interviews, and quantitative, by calculating risks for the different organisations we visited. The findings from both study methods resulted in a comprehensive view and an in-depth understanding of this contradiction. The contradiction between the increase in self-reported medication incidents and the observation of reduced risks was explained by three themes: activities designed to improve medication safety, the reporting of medication incidents, and, lastly, the impact of supervision. The focus of the IGZ on issues of medication safety stimulated most elderly care facilities to reduce medication risks. Also, a change in the culture of reporting incidents caused an increase in the number of reported incidents. Supervision contributed to an improvement in actions geared towards reducing the risks associated with the safety of medication. It also increased a willingness to report such incidents. The more incidents reported are therefore not necessarily a sign of an increase in the risks, but can also be considered as a sign of a safer culture.
41 CFR 102-80.60 - Are Federal agencies responsible for performing facility assessments?
Code of Federal Regulations, 2010 CFR
2010-07-01
... Management Federal Property Management Regulations System (Continued) FEDERAL MANAGEMENT REGULATION REAL PROPERTY 80-SAFETY AND ENVIRONMENTAL MANAGEMENT Safety and Environmental Management Facility Assessments... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Are Federal agencies...
10 CFR 1707.103 - Definitions.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...
10 CFR 1707.103 - Definitions.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...
10 CFR 1707.103 - Definitions.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...
10 CFR 1707.103 - Definitions.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 4 2011-01-01 2011-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...
10 CFR 1707.103 - Definitions.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Definitions. 1707.103 Section 1707.103 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS General Provisions § 1707.103 Definitions. DNFSB means the Defense Nuclear Facilities Safety Board...
Enhancing the traditional hospital design process: a focus on patient safety.
Reiling, John G; Knutzen, Barbara L; Wallen, Thomas K; McCullough, Susan; Miller, Ric; Chernos, Sonja
2004-03-01
In 2002 St. Joseph's Community Hospital (West Bend, WI), a member of SynergyHealth, brought together leaders in health care and systems engineering to develop a set of safety-driven facility design principles that would guide the hospital design process. DESIGNING FOR SAFETY: Hospital leadership recognized that a cross-departmental team approach would be needed and formed the 11-member Facility Design Advisory Council, which, with departmental teams and the aid of architects, was responsible for overseeing the design process and for ensuring that the safety considerations were met. The design process was a team approach, with input from national experts, patients and families, hospital staff and physicians, architects, contractors, and the community. The new facility, designed using safety-driven design principles, reflects many innovative design elements, including truly standardized patient rooms, new technology to minimize falls, and patient care alcoves for every patient room. The new hospital has been designed with maximum adaptability and flexibility in mind, to accommodate changes and provide for future growth. The architects labeled the innovative design. The Synergy Model, to describe the process of shaping the entire building and its spaces to work efficiently as a whole for the care and safety of patients. Construction began on the new facility in August 2003 and is expected to be completed in 2005.
DOE Office of Scientific and Technical Information (OSTI.GOV)
None
2000-02-01
This is the tenth Annual Report to the Congress describing Department of Energy activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of Energy regarding public health and safety issues at the Department's defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department's defense nuclear facilities. During 1999, Departmental activities resulted inmore » the closure of nine Board recommendations. In addition, the Department has completed all implementation plan milestones associated with three Board recommendations. One new Board recommendation was received and accepted by the Department in 1999, and a new implementation plan is being developed to address this recommendation. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, opening of a repository for long-term storage of transuranic wastes, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction.« less
Study of a safety margin system for powered-lift STOL aircraft
NASA Technical Reports Server (NTRS)
Heffley, R. K.; Jewell, W. F.
1978-01-01
A study was conducted to explore the feasibility of a safety margin system for powered-lift aircraft which require a backside piloting technique. The objective of the safety margin system was to present multiple safety margin criteria as a single variable which could be tracked manually or automatically and which could be monitored for the purpose of deriving safety margin status. The study involved a pilot-in-the-loop analysis of several safety margin system concepts and a simulation experiment to evaluate those concepts which showed promise of providing a good solution. A system was ultimately configured which offered reasonable compromises in controllability, status information content, and the ability to regulate the safety margin at some expense of the allowable low speed flight path envelope.
Experimental Fuels Facility Re-categorization Based on Facility Segmentation
DOE Office of Scientific and Technical Information (OSTI.GOV)
Reiss, Troy P.; Andrus, Jason
The Experimental Fuels Facility (EFF) (MFC-794) at the Materials and Fuels Complex (MFC) located on the Idaho National Laboratory (INL) Site was originally constructed to provide controlled-access, indoor storage for radiological contaminated equipment. Use of the facility was expanded to provide a controlled environment for repairing contaminated equipment and characterizing, repackaging, and treating waste. The EFF facility is also used for research and development services, including fuel fabrication. EFF was originally categorized as a LTHC-3 radiological facility based on facility operations and facility radiological inventories. Newly planned program activities identified the need to receive quantities of fissionable materials in excessmore » of the single parameter subcritical limit in ANSI/ANS-8.1, “Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors” (identified as “criticality list” quantities in DOE-STD-1027-92, “Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports,” Attachment 1, Table A.1). Since the proposed inventory of fissionable materials inside EFF may be greater than the single parameter sub-critical limit of 700 g of U-235 equivalent, the initial re-categorization is Hazard Category (HC) 2 based upon a potential criticality hazard. This paper details the facility hazard categorization performed for the EFF. The categorization was necessary to determine (a) the need for further safety analysis in accordance with LWP-10802, “INL Facility Categorization,” and (b) compliance with 10 Code of Federal Regulations (CFR) 830, Subpart B, “Safety Basis Requirements.” Based on the segmentation argument presented in this paper, the final hazard categorization for the facility is LTHC-3. Department of Energy Idaho (DOE-ID) approval of the final hazard categorization determined by this hazard assessment document (HAD) was required per the DOE-ID Supplemental Guidance for DOE-STD-1027-92 based on the proposed downgrade of the initial facility categorization of Hazard Category 2.« less
RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT
DOE Office of Scientific and Technical Information (OSTI.GOV)
KOZLOWSKI, S.D.
2007-05-30
This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditionsmore » for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below.« less
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 4 2011-01-01 2011-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Fees. 1707.301 Section 1707.301 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL RECORDS IN LEGAL PROCEEDINGS... (authentication) of copies of records. The Defense Nuclear Facilities Safety Board may certify that records are...
10 CFR 70.62 - Safety program and integrated safety analysis.
Code of Federal Regulations, 2011 CFR
2011-01-01
...) Radiological hazards related to possessing or processing licensed material at its facility; (ii) Chemical hazards of licensed material and hazardous chemicals produced from licensed material; (iii) Facility... performed by a team with expertise in engineering and process operations. The team shall include at least...
Hazardous Waste Cleanup: Safety-Kleen Corporation - Congers 2-118-01 in Congers, New York
Safety-Kleen Corporation, the Congers facility is located at 68 North Harrison Avenue, Congers, Rockland County, New York. The facility is about 2,000 feet northeast of the intersection of Congers Road and Kings Highway, situated atop a small hill located
30 CFR 71.501 - Sanitary toilet facilities; maintenance.
Code of Federal Regulations, 2010 CFR
2010-07-01
... Section 71.501 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND SURFACE WORK AREAS OF UNDERGROUND COAL MINES Sanitary Toilet Facilities at Surface Worksites of Surface Coal Mines § 71.501 Sanitary...
An Environment for Hardware-in-the-Loop Formation Navigation and Control Simulation
NASA Technical Reports Server (NTRS)
Burns, Rich
2004-01-01
Recent interest in formation flying satellite systems has spurred a considerable amount of research in the relative navigation and control of satellites. Development in this area has included new estimation and control algorithms as well as sensor and actuator development specifically geared toward the relative control problem. This paper describes a simulation facility, the Formation Flying Testbed (FFTB) at NASA's Goddard Space Flight Center, which allows engineers to test new algorithms for the formation flying problem with relevant GN&C hardware in a closed loop simulation. The FFTB currently supports the injection of GPS receiver hardware into the simulation loop, and support for satellite crosslink ranging technology is at a prototype stage. This closed-loop, hardware inclusive simulation capability permits testing of navigation and control software in the presence of the actual hardware with which the algorithms must interact. This capability provides the navigation or control developer with a perspective on how the algorithms perform as part of the closed-loop system. In this paper, the overall design and evolution of the FFTB are presented. Each component of the FFTB is then described in detail. Interfaces between the components of the FFTB are shown and the interfaces to and between navigation and control software are described in detail. Finally, an example of closed-loop formation control with GPS receivers in the loop is presented and results are analyzed.
Safety Evaluation Report for the Claiborne Enrichment Center, Homer, Louisiana (Docket No. 70-3070)
DOE Office of Scientific and Technical Information (OSTI.GOV)
Not Available
1994-01-01
This report documents the US Nuclear Regulatory Commission (NRC) staff review and safety evaluation of the Louisiana Energy Services, L.P. (LES, the applicant) application for a license to possess and use byproduct, source, and special nuclear material and to enrich natural uranium to a maximum of 5 percent U-235 by the gas centrifuge process. The plant, to be known as the Claiborne Enrichment Center (CEC), would be constructed near the town of Homer in Claiborne Parish, Louisiana. At full production in a given year, the plant will receive approximately 4,700 tonnes of feed UF{sub 6} and produce 870 tonnes ofmore » low-enriched UF{sub 6}, and 3,830 tonnes of depleted UF{sub 6} tails. Facility construction, operation, and decommissioning are expected to last 5, 30, and 7 years, respectively. The objective of the review is to evaluate the potential adverse impacts of operation of the facility on worker and public health and safety under both normal operating and accident conditions. The review also considers the management organization, administrative programs, and financial qualifications provided to assure safe design and operation of the facility. The NRC staff concludes that the applicant`s descriptions, specifications, and analyses provide an adequate basis for safety review of facility operations and that construction and operation of the facility does not pose an undue risk to public health and safety.« less
Ray, Wayne A; Taylor, Jo A; Brown, Anne K; Gideon, Patricia; Hall, Kathi; Arbogast, Patrick; Meredith, Sarah
2005-10-24
Fall-related injuries, a major public health problem in long-term care, may be reduced by interventions that improve safety practices. Previous studies have shown that safety practice interventions can reduce falls; however, in long-term care these have relied heavily on external funding and staff. The aim of this study was to test whether a training program in safety practices for staff could reduce fall-related injuries in long-term care facilities. A cluster randomization clinical trial with 112 qualifying facilities and 10,558 study residents 65 years or older and not bedridden. The intervention was an intensive 2-day safety training program with 12-month follow-up. The training program targeted living space and personal safety; wheelchairs, canes, and walkers; psychotropic medication use; and transferring and ambulation. The main outcome measure was serious fall-related injuries during the follow-up period. There was no difference in injury occurrence between the intervention and control facilities (adjusted rate ratio, 0.98; 95% confidence interval, 0.83-1.16). For residents with a prior fall in facilities with the best program compliance, there was a nonsignificant trend toward fewer injuries in the intervention group (adjusted rate ratio, 0.79; 95% confidence interval, 0.57-1.10). More intensive interventions are required to prevent fall-related injuries in long-term care facilities.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Schanfein, Mark J.; Mladineo, Stephen V.
2015-07-07
Over the last few years, significant attention has been paid to both encourage application and provide domestic and international guidance for designing in safeguards and security in new facilities.1,2,3 However, once a facility is operational, safeguards, security, and safety often operate as separate entities that support facility operations. This separation is potentially a serious weakness should insider or outsider threats become a reality.Situations may arise where safeguards detects a possible loss of material in a facility. Will they notify security so they can, for example, check perimeter doors for tampering? Not doing so might give the advantage to an insidermore » who has already, or is about to, move nuclear material outside the facility building. If outsiders break into a facility, the availability of any information to coordinate the facility’s response through segregated alarm stations or a failure to include all available radiation sensors, such as safety’s criticality monitors can give the advantage to the adversary who might know to disable camera systems, but would most likely be unaware of other highly relevant sensors in a nuclear facility.This paper will briefly explore operational safeguards, safety, and security by design (3S) at a high level for domestic and State facilities, identify possible weaknesses, and propose future administrative and technical methods, to strengthen the facility system’s response to threats.« less
DOE’s Management and Oversight of the Nuclear Weapons Complex
1990-03-22
and Economic Development Division Before the Department of Energy Defense Nuclear Facilities Panel Committee on Armed Services House of Representatives...and newly created DOE offices. The Defense Nuclear Facilities Safety Board, whose board members were appointed this past year, was created to provide 6...mandated Defense Nuclear Facilities Safety Board. Continuing dialogue between DOE and the Board can also serve to enhance DOE’s ability to respond more
NASA Astrophysics Data System (ADS)
Eun, Youngho; Park, Sang-Young; Kim, Geuk-Nam
2018-06-01
This paper presents a new state-of-the-art ground-based hardware-in-the-loop test facility, which was developed to verify and demonstrate autonomous guidance, navigation, and control algorithms for space proximity operations and formation flying maneuvers. The test facility consists of two complete spaceflight simulators, an aluminum-based operational arena, and a set of infrared motion tracking cameras; thus, the testbed is capable of representing space activities under circumstances prevailing on the ground. The spaceflight simulators have a maximum of five-degree-of-freedom in a quasi-momentum-free environment, which is produced by a set of linear/hemispherical air-bearings and a horizontally leveled operational arena. The tracking system measures the real-time three-dimensional position and attitude to provide state variables to the agents. The design of the testbed is illustrated in detail for every element throughout the paper. The practical hardware characteristics of the active/passive measurement units and internal actuators are identified in detail from various perspectives. These experimental results support the successful development of the entire facility and enable us to implement and verify the spacecraft proximity operation strategy in the near future.
Post-Test Analysis of 11% Break at PSB-VVER Experimental Facility using Cathare 2 Code
NASA Astrophysics Data System (ADS)
Sabotinov, Luben; Chevrier, Patrick
The best estimate French thermal-hydraulic computer code CATHARE 2 Version 2.5_1 was used for post-test analysis of the experiment “11% upper plenum break”, conducted at the large-scale test facility PSB-VVER in Russia. The PSB rig is 1:300 scaled model of VVER-1000 NPP. A computer model has been developed for CATHARE 2 V2.5_1, taking into account all important components of the PSB facility: reactor model (lower plenum, core, bypass, upper plenum, downcomer), 4 separated loops, pressurizer, horizontal multitube steam generators, break section. The secondary side is represented by recirculation model. A large number of sensitivity calculations has been performed regarding break modeling, reactor pressure vessel modeling, counter current flow modeling, hydraulic losses, heat losses. The comparison between calculated and experimental results shows good prediction of the basic thermal-hydraulic phenomena and parameters such as pressures, temperatures, void fractions, loop seal clearance, etc. The experimental and calculation results are very sensitive regarding the fuel cladding temperature, which show a periodical nature. With the applied CATHARE 1D modeling, the global thermal-hydraulic parameters and the core heat up have been reasonably predicted.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Yu, X. G.; Kim, Y. S.; Choi, K. Y.
2012-07-01
A SBO (station blackout) experiment named SBO-01 was performed at full-pressure IET (Integral Effect Test) facility ATLAS (Advanced Test Loop for Accident Simulation) which is scaled down from the APR1400 (Advanced Power Reactor 1400 MWe). In this study, the transient of SBO-01 is discussed and is subdivided into three phases: the SG fluid loss phase, the RCS fluid loss phase, and the core coolant depletion and core heatup phase. In addition, the typical phenomena in SBO-01 test - SG dryout, natural circulation, core coolant boiling, the PRZ full, core heat-up - are identified. Furthermore, the SBO-01 test is reproduced bymore » the MARS code calculation with the ATLAS model which represents the ATLAS test facility. The experimental and calculated transients are then compared and discussed. The comparison reveals there was malfunction of equipments: the SG leakage through SG MSSV and the measurement error of loop flow meter. As the ATLAS model is validated against the experimental results, it can be further employed to investigate the other possible SBO scenarios and to study the scaling distortions in the ATLAS. (authors)« less
Pugliese, F; Albini, E; Serio, O; Apostoli, P
2011-01-01
The 81/2008 Act has defined a model of a health and safety management system that can contribute to prevent the occupational health and safety risks. We have developed the structure of a health and safety management system model and the necessary tools for its implementation in health care facilities. The realization of a model is structured in various phases: initial review, safety policy, planning, implementation, monitoring, management review and continuous improvement. Such a model, in continuous evolution, is based on the responsibilities of the different corporate characters and on an accurate analysis of risks and involved norms.
LOOP marine and estuarine monitoring program, 1978-95 : volume 2 : water chemistry.
DOT National Transportation Integrated Search
1998-01-01
The proposed construction and use of facilities in an environmentally sensitive area led to questions about various consequential environmental impacts arising from the following activities: 1) oil storage caverns were created by leaching out a salt ...
1999-09-27
facility in Alang , India, where ship scrapping typically is performed on beach front property, allowing toxins, oils, PCBs, asbestos, and chromates...in Alang are operated in a manner that endanger the health and safety of their laborers and that government enforcement of...Id. According to the Baltimore Sun, none of the men who work at the Alang facility wear hard hats, safety harnesses, or respirators even though each
ASME code considerations for the compact heat exchanger
DOE Office of Scientific and Technical Information (OSTI.GOV)
Nestell, James; Sham, Sam
2015-08-31
The mission of the U.S. Department of Energy (DOE), Office of Nuclear Energy is to advance nuclear power in order to meet the nation's energy, environmental, and energy security needs. Advanced high temperature reactor systems such as sodium fast reactors and high and very high temperature gas-cooled reactors are being considered for the next generation of nuclear reactor plant designs. The coolants for these high temperature reactor systems include liquid sodium and helium gas. Supercritical carbon dioxide (sCO₂), a fluid at a temperature and pressure above the supercritical point of CO₂, is currently being investigated by DOE as a workingmore » fluid for a nuclear or fossil-heated recompression closed Brayton cycle energy conversion system that operates at 550°C (1022°F) at 200 bar (2900 psi). Higher operating temperatures are envisioned in future developments. All of these design concepts require a highly effective heat exchanger that transfers heat from the nuclear or chemical reactor to the chemical process fluid or the to the power cycle. In the nuclear designs described above, heat is transferred from the primary to the secondary loop via an intermediate heat exchanger (IHX) and then from the intermediate loop to either a working process or a power cycle via a secondary heat exchanger (SHX). The IHX is a component in the primary coolant loop which will be classified as "safety related." The intermediate loop will likely be classified as "not safety related but important to safety." These safety classifications have a direct bearing on heat exchanger design approaches for the IHX and SHX. The very high temperatures being considered for the VHTR will require the use of very high temperature alloys for the IHX and SHX. Material cost considerations alone will dictate that the IHX and SHX be highly effective; that is, provide high heat transfer area in a small volume. This feature must be accompanied by low pressure drop and mechanical reliability and robustness. Classic shell and tube designs will be large and costly, and may only be appropriate in steam generator service in the SHX where boiling inside the tubes occurs. For other energy conversion systems, all of these features can be met in a compact heat exchanger design. This report will examine some of the ASME Code issues that will need to be addressed to allow use of a Code-qualified compact heat exchanger in IHX or SHX nuclear service. Most effort will focus on the IHX, since the safety-related (Class A) design rules are more extensive than those for important-to-safety (Class B) or commercial rules that are relevant to the SHX.« less
The flight robotics laboratory
NASA Technical Reports Server (NTRS)
Tobbe, Patrick A.; Williamson, Marlin J.; Glaese, John R.
1988-01-01
The Flight Robotics Laboratory of the Marshall Space Flight Center is described in detail. This facility, containing an eight degree of freedom manipulator, precision air bearing floor, teleoperated motion base, reconfigurable operator's console, and VAX 11/750 computer system, provides simulation capability to study human/system interactions of remote systems. The facility hardware, software and subsequent integration of these components into a real time man-in-the-loop simulation for the evaluation of spacecraft contact proximity and dynamics are described.
Diagonal dominance for the multivariable Nyquist array using function minimization
NASA Technical Reports Server (NTRS)
Leininger, G. G.
1977-01-01
A new technique for the design of multivariable control systems using the multivariable Nyquist array method was developed. A conjugate direction function minimization algorithm is utilized to achieve a diagonal dominant condition over the extended frequency range of the control system. The minimization is performed on the ratio of the moduli of the off-diagonal terms to the moduli of the diagonal terms of either the inverse or direct open loop transfer function matrix. Several new feedback design concepts were also developed, including: (1) dominance control parameters for each control loop; (2) compensator normalization to evaluate open loop conditions for alternative design configurations; and (3) an interaction index to determine the degree and type of system interaction when all feedback loops are closed simultaneously. This new design capability was implemented on an IBM 360/75 in a batch mode but can be easily adapted to an interactive computer facility. The method was applied to the Pratt and Whitney F100 turbofan engine.
75 FR 51500 - Advisory Committee on Reactor Safeguards
Federal Register 2010, 2011, 2012, 2013, 2014
2010-08-20
..., October 14, 2009 (74 FR 52829-52830). Thursday, September 9, 2010, Conference Room T2-B1, Two White Flint... Fabrication Facility and the Associated Safety Evaluation Report (Open/ Closed)--The Committee will hold... the MOX Fuel Fabrication Facility and the associated Safety Evaluation Report. [Note: A portion of...
41 CFR 301-11.11 - How do I select lodging and make lodging reservations?
Code of Federal Regulations, 2012 CFR
2012-07-01
... always stay in a “fire safe” facility. This is a facility that meets the fire safety requirements of the Hotel and Motel Fire Safety Act of 1990 (the Act), as amended (see 5 U.S.C. 5707a). (c) When selecting a...
41 CFR 301-11.11 - How do I select lodging and make lodging reservations?
Code of Federal Regulations, 2013 CFR
2013-07-01
... always stay in a “fire safe” facility. This is a facility that meets the fire safety requirements of the Hotel and Motel Fire Safety Act of 1990 (the Act), as amended (see 5 U.S.C. 5707a). (c) When selecting a...
41 CFR 301-11.11 - How do I select lodging and make lodging reservations?
Code of Federal Regulations, 2014 CFR
2014-07-01
... always stay in a “fire safe” facility. This is a facility that meets the fire safety requirements of the Hotel and Motel Fire Safety Act of 1990 (the Act), as amended (see 5 U.S.C. 5707a). (c) When selecting a...
49 CFR 1155.27 - Board determinations under 49 U.S.C. 10909.
Code of Federal Regulations, 2010 CFR
2010-10-01
... determines that the facility at the existing or proposed location would not pose an unreasonable risk to... risk to public health, safety, or the environment, the Board shall weigh the particular facility's... comply with an environmental, public health, or public safety standard that falls under the traditional...
Implementation of the Generic Safety Analysis Report - Lessons Learned
DOE Office of Scientific and Technical Information (OSTI.GOV)
Blanchard, A.
1999-06-02
The Savannah River Site has completed the development, review and approval process for the Generic Safety Analysis Report (GSAR) and implemented this information in facility SARs and BIOs. This includes the yearly revision of the GSAR and the facility-specific SARs. The process has provided us with several lessons learned.
10 CFR 1706.1 - Scope; statement of policy.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 4 2011-01-01 2011-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...
10 CFR 1707.205 - Processing demands or requests.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 4 2011-01-01 2011-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...
10 CFR 1707.205 - Processing demands or requests.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...
10 CFR 1707.205 - Processing demands or requests.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...
10 CFR 1707.204 - Service of subpoenas or requests.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...
10 CFR 1705.03 - Systems of records notification.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...
10 CFR 1707.205 - Processing demands or requests.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...
10 CFR 1707.205 - Processing demands or requests.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Processing demands or requests. 1707.205 Section 1707.205 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF OFFICIAL... and/or produce official records and information. (b) The Defense Nuclear Facilities Safety Board will...
10 CFR 1707.204 - Service of subpoenas or requests.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...
10 CFR 1706.1 - Scope; statement of policy.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...
10 CFR 1707.204 - Service of subpoenas or requests.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...
10 CFR 1706.1 - Scope; statement of policy.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...
10 CFR 1707.204 - Service of subpoenas or requests.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 4 2011-01-01 2011-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...
10 CFR 1706.1 - Scope; statement of policy.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...
10 CFR 1707.204 - Service of subpoenas or requests.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Service of subpoenas or requests. 1707.204 Section 1707.204 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY DNFSB EMPLOYEES AND PRODUCTION OF... be served on the General Counsel, Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW...
10 CFR 1706.1 - Scope; statement of policy.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Scope; statement of policy. 1706.1 Section 1706.1 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD ORGANIZATIONAL AND CONSULTANT CONFLICTS OF INTERESTS § 1706.1... the Defense Nuclear Facilities Safety Board will follow in determining whether a contractor or offeror...
Federal Register 2010, 2011, 2012, 2013, 2014
2011-09-19
... NUCLEAR REGULATORY COMMISSION [Docket No. 40-3392-MLA; ASLBP No. 11-910-01-MLA-BD01] Atomic Safety and Licensing Board; Honeywell International, Inc.; Metropolis Works Uranium Conversion Facility... assurance for its Metropolis Works uranium conversion facility in Metropolis, Illinois. \\1\\ LBP-11-19, 74...
Response to in-depth safety audit of the L Lake sampling station
DOE Office of Scientific and Technical Information (OSTI.GOV)
Gladden, J.B.
1986-10-15
An in-depth safety audit of several of the facilities and operations supporting the Biological Monitoring Program on L Lake was conducted. Subsequent to the initial audit, the audit team evaluated the handling of samples taken for analysis of Naegleria fowleri at the 704-U laboratory facility.
10 CFR 1705.08 - Appeals from correction denials.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...
10 CFR 1705.06 - Appeals from access denials.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...
10 CFR 1705.03 - Systems of records notification.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...
10 CFR 1705.08 - Appeals from correction denials.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...
10 CFR 1705.03 - Systems of records notification.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...
10 CFR 1705.07 - Requests for correction of records.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...
10 CFR 1705.08 - Appeals from correction denials.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...
10 CFR 1705.07 - Requests for correction of records.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...
10 CFR 1705.06 - Appeals from access denials.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...
10 CFR 1705.07 - Requests for correction of records.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...
10 CFR 1705.06 - Appeals from access denials.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...
10 CFR 1705.06 - Appeals from access denials.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...
10 CFR 1705.03 - Systems of records notification.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...
10 CFR 1705.08 - Appeals from correction denials.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...
10 CFR 1705.07 - Requests for correction of records.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...
10 CFR 1705.07 - Requests for correction of records.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 4 2011-01-01 2011-01-01 false Requests for correction of records. 1705.07 Section 1705.07 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.07 Requests for correction of..., Defense Nuclear Facilities Safety Board, 625 Indiana Avenue, NW., Suite 700, Washington, DC 20004. The...
10 CFR 1705.03 - Systems of records notification.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 4 2011-01-01 2011-01-01 false Systems of records notification. 1705.03 Section 1705.03 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.03 Systems of records notification. (a... writing. Written requests should be directed to: Privacy Act Officer, Defense Nuclear Facilities Safety...
10 CFR 1705.06 - Appeals from access denials.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 4 2011-01-01 2011-01-01 false Appeals from access denials. 1705.06 Section 1705.06 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.06 Appeals from access denials. When.... This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board, 625 Indiana...
10 CFR 1705.08 - Appeals from correction denials.
Code of Federal Regulations, 2011 CFR
2011-01-01
... 10 Energy 4 2011-01-01 2011-01-01 false Appeals from correction denials. 1705.08 Section 1705.08 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD PRIVACY ACT § 1705.08 Appeals from correction denials. (a... in writing. This appeal should be directed to The Chairman, Defense Nuclear Facilities Safety Board...
Application of the Life Safety Code to a Historic Test Stand
NASA Technical Reports Server (NTRS)
Askins, Bruce; Lemke, Paul R.; Lewis, William L.; Covell, Carol C.
2011-01-01
NASA has conducted a study to assess alternatives to refurbishing existing launch vehicle modal test facilities as opposed to developing new test facilities to meet the demands of a very fiscally constrained test and evaluation environment. The results of this study showed that Marshall Space Flight Center (MSFC) Test Stand (TS) 4550 could be made compliant, within reasonable cost and schedule impacts, if safety processes and operational limitations were put in place to meet the safety codes and concerns of the Fire Marshall. Trades were performed with key selection criteria to ensure that appropriate levels of occupant safety are incorporated into test facility design modifications. In preparation for the ground vibration tests that were to be performed on the Ares I launch vehicle, the Ares Flight and Integrated Test Office (FITO) organization evaluated the available test facility options, which included the existing mothballed structural dynamic TS4550 used by Apollo and Shuttle, alternative ground vibration test facilities at other locations, and construction of a new dynamic test stand. After an exhaustive assessment of the alternatives, the results favored modifying the TS4550 because it was the lowest cost option and presented the least schedule risk to the NASA Constellation Program for Ares Integrated Vehicle Ground Vibration Test (IVGVT). As the renovation design plans and drawings were being developed for TS4550, a safety concern was discovered the original design for the construction of the test stand, originally built for the Apollo Program and renovated for the Shuttle Program, was completed before NASA s adoption of the currently imposed safety and building codes per National Fire Protection Association Life Safety Code [NFPA 101] and International Building Codes. The initial FITO assessment of the design changes, required to make TS4550 compliant with current safety and building standards, identified a significant cost increase and schedule impact. An effort was launched to thoroughly evaluate the applicable life safety requirements, examine the context in which they were derived, and determine a means by which the TS4550 modifications could be made within budget and on schedule, while still providing the occupants with appropriate levels of safety.
Energy Systems Integration Facility Control Room | Energy Systems
Integration Facility | NREL Energy Systems Integration Facility Control Room Energy Systems Integration Facility Control Room The Energy Systems Integration Facility control room allows system engineers as the monitoring point for the facility's integrated safety and control systems. Photo of employees
Mygind, Anna; El-Souri, Mira; Rossing, Charlotte; Thomsen, Linda Aagaard
2018-04-01
To develop and test an educational programme on quality and safety in medication handling for staff in residential facilities for the disabled. The continuing pharmacy education instructional design model was used to develop the programme with 22 learning objectives on disease and medicines, quality and safety, communication and coordination. The programme was a flexible, modular seven + two days' course addressing quality and safety in medication handling, disease and medicines, and medication supervision and reconciliation. The programme was tested in five Danish municipalities. Municipalities were selected based on their application for participation; each independently selected a facility for residents with mental and intellectual disabilities, and a facility for residents with severe mental illnesses. Perceived effects were measured based on a questionnaire completed by participants before and after the programme. Effects on motivation and confidence as well as perceived effects on knowledge, skills and competences related to medication handling, patient empowerment, communication, role clarification and safety culture were analysed conducting bivariate, stratified analyses and test for independence. Of the 114 participants completing the programme, 75 participants returned both questionnaires (response rate = 66%). Motivation and confidence regarding quality and safety in medication handling significantly improved, as did perceived knowledge, skills and competences on 20 learning objectives on role clarification, safety culture, medication handling, patient empowerment and communication. The programme improved staffs' motivation and confidence and their perceived ability to handle residents' medication safely through improved role clarification, safety culture, medication handling and patient empowerment and communication skills. © 2017 Royal Pharmaceutical Society.
Activities of the US-Japan Safety Monitor Joint Working Group
DOE Office of Scientific and Technical Information (OSTI.GOV)
Richard L. Savercool; Lee C. Cadwallader
2004-09-01
This paper documents the activities of the US-Japan exchange in the area of personnel safety at magnetic and laser fusion experiments. A near-miss event with a visiting scientist to the US in 1992 was the impetus for forming the Joint Working Group on Fusion Safety. This exchnge has been under way for over ten years and has provided many safety insights for both US and Japanese facility personnel at national institutes and at universities. The background and activities of the Joint Working Group are described, including the facilities that have been visited for safety walkthroughs, the participants from both countries,more » and the main safety issues examined during visits. Based on these visits, some operational safety ideas to enhance experiment safety are given. The near-term future plans of the Safety Monitor Joint Working group are also discussed.« less
Control Oriented Modeling and Validation of Aeroservoelastic Systems
NASA Technical Reports Server (NTRS)
Crowder, Marianne; deCallafon, Raymond (Principal Investigator)
2002-01-01
Lightweight aircraft design emphasizes the reduction of structural weight to maximize aircraft efficiency and agility at the cost of increasing the likelihood of structural dynamic instabilities. To ensure flight safety, extensive flight testing and active structural servo control strategies are required to explore and expand the boundary of the flight envelope. Aeroservoelastic (ASE) models can provide online flight monitoring of dynamic instabilities to reduce flight time testing and increase flight safety. The success of ASE models is determined by the ability to take into account varying flight conditions and the possibility to perform flight monitoring under the presence of active structural servo control strategies. In this continued study, these aspects are addressed by developing specific methodologies and algorithms for control relevant robust identification and model validation of aeroservoelastic structures. The closed-loop model robust identification and model validation are based on a fractional model approach where the model uncertainties are characterized in a closed-loop relevant way.
Safety Oversight of Decommissioning Activities at DOE Nuclear Sites
DOE Office of Scientific and Technical Information (OSTI.GOV)
Zull, Lawrence M.; Yeniscavich, William
2008-01-15
The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive materialmore » contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites.« less
Advanced reactors and associated fuel cycle facilities: safety and environmental impacts.
Hill, R N; Nutt, W M; Laidler, J J
2011-01-01
The safety and environmental impacts of new technology and fuel cycle approaches being considered in current U.S. nuclear research programs are contrasted to conventional technology options in this paper. Two advanced reactor technologies, the sodium-cooled fast reactor (SFR) and the very high temperature gas-cooled reactor (VHTR), are being developed. In general, the new reactor technologies exploit inherent features for enhanced safety performance. A key distinction of advanced fuel cycles is spent fuel recycle facilities and new waste forms. In this paper, the performance of existing fuel cycle facilities and applicable regulatory limits are reviewed. Technology options to improve recycle efficiency, restrict emissions, and/or improve safety are identified. For a closed fuel cycle, potential benefits in waste management are significant, and key waste form technology alternatives are described. Copyright © 2010 Health Physics Society
Enhanced Time Out: An Improved Communication Process.
Nelson, Patricia E
2017-06-01
An enhanced time out is an improved communication process initiated to prevent such surgical errors as wrong-site, wrong-procedure, or wrong-patient surgery. The enhanced time out at my facility mandates participation from all members of the surgical team and requires designated members to respond to specified time out elements on the surgical safety checklist. The enhanced time out incorporated at my facility expands upon the safety measures from the World Health Organization's surgical safety checklist and ensures that all personnel involved in a surgical intervention perform a final check of relevant information. Initiating the enhanced time out at my facility was intended to improve communication and teamwork among surgical team members and provide a highly reliable safety process to prevent wrong-site, wrong-procedure, and wrong-patient surgery. Copyright © 2017 AORN, Inc. Published by Elsevier Inc. All rights reserved.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Weber, P.; Umminger, K.J.; Schoen, B.
1995-09-01
The thermal hydraulic behavior of a PWR during beyond-design-basis accident scenarios is of vital interest for the verification and optimization of accident management procedures. Within the scope of the German reactor safety research program experiments were performed in the volumetrically scaled PKL 111 test facility by Siemens/KWU. This highly instrumented test rig simulates a KWU-design PWR (1300 MWe). In particular, the latest tests performed related to a SBLOCA with additional system failures, e.g. nitrogen entering the primary system. In the case of a SBLOCA, it is the goal of the operator to put the plant in a condition where themore » decay heat can be removed first using the low pressure emergency core cooling system and then the residual heat removal system. The experimental investigation presented assumed the following beyond-design-basis accident conditions: 0.5% break in a cold leg, 2 of 4 steam generators (SGs) isolated on the secondary side (feedwater- and steam line-valves closed), filled with steam on the primary side, cooldown of the primary system using the remaining two steam generators, high pressure injection system only in the two loops with intact steam generators, if possible no operator actions to reach the conditions for residual heat removal system activation. Furthermore, it was postulated that 2 of the 4 hot leg accumulators had a reduced initial water inventory (increased nitrogen inventory), allowing nitrogen to enter the primary system at a pressure of 15 bar and nearly preventing the heat transfer in the SGs ({open_quotes}passivating{close_quotes} U-tubes). Due to this the heat transfer regime in the intact steam generators changed remarkably. The primary system showed self-regulating system effects and heat transfer improved again (reflux-condenser mode in the U-tube inlet region).« less
2001-12-01
addition, the Defense Nuclear Facilities Safety Board warned in 1997 that, given likely future reductions in DOE’s budget, the department needed to...future leaders of the acquisition workforce. The Defense Nuclear Facilities Safety Board’s 2000 report credited DOE with taking steps to improve the...technical capabilities of personnel at its defense nuclear facilities , but pointed out the need for DOE’s leadership to pay increased attention to this
Progress on plutonium stabilization
DOE Office of Scientific and Technical Information (OSTI.GOV)
Hurt, D.
1996-05-01
The Defense Nuclear Facilities Safety Board has safety oversight responsibility for most of the facilities where unstable forms of plutonium are being processed and packaged for interim storage. The Board has issued recommendations on plutonium stabilization and has has a considerable influence on DOE`s stabilization schedules and priorities. The Board has not made any recommendations on long-term plutonium disposition, although it may get more involved in the future if DOE develops plans to use defense nuclear facilities for disposition activities.
NASA Technical Reports Server (NTRS)
Marmolejo, Jose; Ewert, Michael
2016-01-01
The Engineering Directorate at the NASA - Johnson Space Center is outfitting a 20-Foot diameter hypobaric chamber in Building 7 to support future deep-space Environmental Control & Life Support System (ECLSS) research as part of the Human Exploration System Test-bed for Integration and Advancement (HESTIA) Project. This human-rated chamber is the only NASA facility that has the unique experience, chamber geometry, infrastructure, and support systems capable of conducting this research. The chamber was used to support Gemini, Apollo, and SkyLab Missions. More recently, it was used to conduct 30-, 60-, and 90-day human ECLSS closed-loop testing in the 1990s to support the International Space Station and life support technology development. NASA studies show that both planetary surface and deep-space transit crew habitats will be 3-4 story cylindrical structures driven by human occupancy volumetric needs and launch vehicle constraints. The HESTIA facility offers a 3-story, 20-foot diameter habitat consistent with the studies' recommendations. HESTIA operations follow stringent processes by a certified test team that including human testing. Project management, analysis, design, acquisition, fabrication, assembly and certification of facility build-ups are available to support this research. HESTIA offers close proximity to key stakeholders including astronauts, Human Research Program (who direct space human research for the agency), Mission Operations, Safety & Mission Assurance, and Engineering Directorate. The HESTIA chamber can operate at reduced pressure and elevated oxygen environments including those proposed for deep-space exploration. Data acquisition, power, fluids and other facility resources are available to support a wide range of research. Recently completed HESTIA research consisted of unmanned testing of ECLSS technologies. Eventually, the HESTIA research will include humans for extended durations at reduced pressure and elevated oxygen to demonstrate very high reliability of critical ECLSS and other technologies.
Improvements to a five-phase ABS algorithm for experimental validation
NASA Astrophysics Data System (ADS)
Gerard, Mathieu; Pasillas-Lépine, William; de Vries, Edwin; Verhaegen, Michel
2012-10-01
The anti-lock braking system (ABS) is the most important active safety system for passenger cars. Unfortunately, the literature is not really precise about its description, stability and performance. This research improves a five-phase hybrid ABS control algorithm based on wheel deceleration [W. Pasillas-Lépine, Hybrid modeling and limit cycle analysis for a class of five-phase anti-lock brake algorithms, Veh. Syst. Dyn. 44 (2006), pp. 173-188] and validates it on a tyre-in-the-loop laboratory facility. Five relevant effects are modelled so that the simulation matches the reality: oscillations in measurements, wheel acceleration reconstruction, brake pressure dynamics, brake efficiency changes and tyre relaxation. The time delays in measurement and actuation have been identified as the main difficulty for the initial algorithm to work in practice. Three methods are proposed in order to deal with these delays. It is verified that the ABS limit cycles encircle the optimal braking point, without assuming any tyre parameter being a priori known. The ABS algorithm is compared with the commercial algorithm developed by Bosch.
DOE Office of Scientific and Technical Information (OSTI.GOV)
Chakraborty, Sudipta
Various interconnection challenges exist when connecting distributed PV into the electrical distribution grid in terms of safety, reliability, and stability of the electric power systems. Some of the urgent areas for research, as identified by inverter manufacturers, installers and utilities, are potential for transient overvoltage from PV inverters, multi-inverter anti-islanding, impact of smart inverters on volt-VAR support, impact of bidirectional power flow, and potential for distributed generation curtailment solutions to mitigate grid stability challenges. Under this project, NREL worked with SolarCity to address these challenges through research, testing and analysis at the Energy System Integration Facility (ESIF). Inverters from differentmore » manufacturers were tested at ESIF and NREL's unique power hardware-in-the-loop (PHIL) capability was utilized to evaluate various system-level impacts. Through the modeling, simulation, and testing, this project eliminated critical barriers on high PV penetration and directly supported the Department of Energy's SunShot goal of increasing the solar PV on the electrical grid.« less
Accelerated Performance Testing on the 2006 NCAT Pavement Test Track
DOT National Transportation Integrated Search
2009-12-01
The original National Center for Asphalt Technology (NCAT) Pavement Test Track was built in 2000 in Opelika, Alabama where it has served as a state-of-the-art, full-scale, closed-loop accelerated loading facility. The construction, operation, and res...
Safety analysis in test facility design
NASA Astrophysics Data System (ADS)
Valk, A.; Jonker, R. J.
1990-09-01
The application of safety analysis techniques as developed in, for example nuclear and petrochemical industry, can be very beneficial in coping with the increasing complexity of modern test facility installations and their operations. To illustrate the various techniques available and their phasing in a project, an overview of the most commonly used techniques is presented. Two case studies are described: the hazard and operability study techniques and safety zoning in relation to the possible presence of asphyxiating atmospheres.
CERT tribal internship program. Final intern report: Lewis Yellowrobe, 1995
DOE Office of Scientific and Technical Information (OSTI.GOV)
NONE
1998-09-01
The purpose of this internship was to present state legislators with the history and an overview of the Department of Energy`s policies towards occupational health and safety during cleanup of nuclear weapons production facilities. The approach used library research and phone and personal interviews to acquire information on DOE policies. This intern report contains the final report to legislators entitled ``Environmental restoration and waste management: Worker health and safety concerns during nuclear facility cleanup.`` It presents the current status of DOE occupational health and safety at production facilities, Congressional intent, past DOE occupational policies, and options for state legislators tomore » use to get involved with DOE policy direction.« less
CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP
DOE Office of Scientific and Technical Information (OSTI.GOV)
Kessler, S
2009-04-21
With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5,more » Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since February of 2008 and has proven to be simple and effective. Each control identified in the applicable new/revised CSE is evaluated via the table. The results of this evaluation are documented in tables attached to the CCR as an appendix, for each CSE, to the base document.« less
76 FR 73570 - Pipeline Safety: Miscellaneous Changes to Pipeline Safety Regulations
Federal Register 2010, 2011, 2012, 2013, 2014
2011-11-29
... pipeline facilities to facilitate the removal of liquids and other materials from the gas stream. These... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Parts... Changes to Pipeline Safety Regulations AGENCY: Pipeline and Hazardous Materials Safety Administration...
Safety in Academic Chemistry Laboratories. Fourth Edition.
ERIC Educational Resources Information Center
American Chemical Society, Washington, DC.
This booklet provides guidelines for safety in the chemical laboratory. Part I, "Guides for Instructors and Administrators," includes safety rules, safety practices and facilities, preparation for emergencies, safety committees, accident reporting, fire insurance, and listings of some hazardous chemicals. Part II, "Student Guide to…
76 FR 15348 - Proposed Extension of the Approval of Information Collection Requirements
Federal Register 2010, 2011, 2012, 2013, 2014
2011-03-21
... property to be used for housing migrant agricultural workers shall not permit such housing to be occupied... conducted the housing safety and health inspection is posted at the site of the facility or real property. The certificate attests that the facility or real property meets applicable safety and health...
76 FR 56458 - Proposed Data Collections Submitted for Public Comment and Recommendations
Federal Register 2010, 2011, 2012, 2013, 2014
2011-09-13
... Registered Nurse (Infection 6,000 1 5/60 500 Preventionist). 57.101: Facility Contact Information Registered Nurse (Infection 6,000 1 10/60 1,000 Preventionist). 57.103: Patient Safety Component--Annual Registered Nurse (Infection 6,000 1 30/60 3,000 Facility Survey. Preventionist). 57.104: Patient Safety Component...
Laboratory Safety Needs of Kentucky School-Based Agricultural Mechanics Teachers
ERIC Educational Resources Information Center
Saucier, P. Ryan; Vincent, Stacy K.; Anderson, Ryan G.
2014-01-01
The frequency and severity of accidents that occur in the agricultural mechanics laboratory can be reduced when these facilities are managed by educators who are competent in the area of laboratory safety and facility management (McKim & Saucier, 2011). To ensure teachers are technically competent and prepared to manage an agricultural…
10 CFR 1707.203 - Filing requirements for demands or requests for documents or testimony.
Code of Federal Regulations, 2014 CFR
2014-01-01
... 10 Energy 4 2014-01-01 2014-01-01 false Filing requirements for demands or requests for documents or testimony. 1707.203 Section 1707.203 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY...) The Defense Nuclear Facilities Safety Board reserves the right to require additional information to...
10 CFR 1707.203 - Filing requirements for demands or requests for documents or testimony.
Code of Federal Regulations, 2013 CFR
2013-01-01
... 10 Energy 4 2013-01-01 2013-01-01 false Filing requirements for demands or requests for documents or testimony. 1707.203 Section 1707.203 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY...) The Defense Nuclear Facilities Safety Board reserves the right to require additional information to...
10 CFR 1707.203 - Filing requirements for demands or requests for documents or testimony.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Filing requirements for demands or requests for documents or testimony. 1707.203 Section 1707.203 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY...) The Defense Nuclear Facilities Safety Board reserves the right to require additional information to...
10 CFR 1707.203 - Filing requirements for demands or requests for documents or testimony.
Code of Federal Regulations, 2012 CFR
2012-01-01
... 10 Energy 4 2012-01-01 2012-01-01 false Filing requirements for demands or requests for documents or testimony. 1707.203 Section 1707.203 Energy DEFENSE NUCLEAR FACILITIES SAFETY BOARD TESTIMONY BY...) The Defense Nuclear Facilities Safety Board reserves the right to require additional information to...
Techniques employed by the NASA White Sands Test Facility to ensure oxygen system component safety
NASA Technical Reports Server (NTRS)
Stradling, J. S.; Pippen, D. L.; Frye, G. W.
1983-01-01
Methods of ascertaining the safety and suitability of a variety of oxygen system components are discussed. Additionally, qualification and batch control requirements for soft goods in oxygen systems are presented. Current oxygen system component qualification test activities in progress at White Sands Test Facility are described.
78 FR 67344 - Sunshine Act Meeting; New Time and Date of Proceeding
Federal Register 2010, 2011, 2012, 2013, 2014
2013-11-12
... DEFENSE NUCLEAR FACILITIES SAFETY BOARD Sunshine Act Meeting; New Time and Date of Proceeding AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice of Public Meeting and Hearing; New Time... the postponement in the Federal Register due to the shutdown. The Board has now decided on a new time...
77 FR 75676 - Standard Review Plan for Review of Fuel Cycle Facility License Applications
Federal Register 2010, 2011, 2012, 2013, 2014
2012-12-21
... NUCLEAR REGULATORY COMMISSION [NRC-2012-0220] Standard Review Plan for Review of Fuel Cycle... Review of a License Application for a Fuel Cycle Facility.'' The NRC is extending the public comment... of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2012...
10 CFR 52.79 - Contents of applications; technical information in final safety analysis report.
Code of Federal Regulations, 2010 CFR
2010-01-01
... assurance program will be implemented; (26) The applicant's organizational structure, allocations or... presents a safety analysis of the structures, systems, and components of the facility as a whole. The final... contain an analysis and evaluation of the major structures, systems, and components of the facility that...
30 CFR 71.500 - Sanitary toilet facilities at surface work sites; installation requirements.
Code of Federal Regulations, 2010 CFR
2010-07-01
... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Sanitary toilet facilities at surface work sites; installation requirements. 71.500 Section 71.500 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY HEALTH STANDARDS-SURFACE COAL MINES AND...
Federal Register 2010, 2011, 2012, 2013, 2014
2010-03-01
... capability for non- vital laboratory room electrical loads that provides an engineered control to reduce..., approximately two orders of magnitude higher than our evaluation guideline for selecting safety class controls. Approval of the DSA included recognition of weaknesses in the facility's control set and the need to...
77 FR 74587 - Safety Zone; Grain-Shipment Vessels, Columbia and Willamette Rivers
Federal Register 2010, 2011, 2012, 2013, 2014
2012-12-17
... 1625-AA00 Safety Zone; Grain-Shipment Vessels, Columbia and Willamette Rivers AGENCY: Coast Guard, DHS... inbound and outbound grain-shipment vessels involved in commerce with the Columbia Grain facility on the Willamette River in Portland, OR, and the United Grain Corporation facility on the Columbia River in...
40 CFR 170.135 - Posted pesticide safety information.
Code of Federal Regulations, 2011 CFR
2011-07-01
..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...
40 CFR 170.135 - Posted pesticide safety information.
Code of Federal Regulations, 2012 CFR
2012-07-01
..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...
40 CFR 170.135 - Posted pesticide safety information.
Code of Federal Regulations, 2014 CFR
2014-07-01
..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...
40 CFR 170.135 - Posted pesticide safety information.
Code of Federal Regulations, 2010 CFR
2010-07-01
..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...
40 CFR 170.135 - Posted pesticide safety information.
Code of Federal Regulations, 2013 CFR
2013-07-01
..., pesticide safety information. (b) Pesticide safety poster. A safety poster must be displayed that conveys..., and telephone number of the nearest emergency medical care facility shall be on the safety poster or displayed close to the safety poster. (2) The agricultural employer shall inform workers promptly of any...
10 CFR 830.204 - Documented safety analysis.
Code of Federal Regulations, 2010 CFR
2010-01-01
... 10 Energy 4 2010-01-01 2010-01-01 false Documented safety analysis. 830.204 Section 830.204 Energy DEPARTMENT OF ENERGY NUCLEAR SAFETY MANAGEMENT Safety Basis Requirements § 830.204 Documented safety analysis... approval from DOE for the methodology used to prepare the documented safety analysis for the facility...
49 CFR 193.2189-193.2233 - [Reserved
Code of Federal Regulations, 2010 CFR
2010-10-01
... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Design Lng Storage Tanks §§ 193.2189-193.2233 [Reserved] ...
49 CFR 193.2121-193.2153 - [Reserved
Code of Federal Regulations, 2010 CFR
2010-10-01
... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Design Design of Components and Buildings §§ 193.2121-193...
10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.
Code of Federal Regulations, 2011 CFR
2011-01-01
... behavior of items relied on for safety. (b) Facility and system design and facility layout must be based on... existing facilities. (a) Baseline design criteria. Each prospective applicant or licensee shall address the following baseline design criteria in the design of new facilities. Each existing licensee shall address the...
10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.
Code of Federal Regulations, 2013 CFR
2013-01-01
... behavior of items relied on for safety. (b) Facility and system design and facility layout must be based on... existing facilities. (a) Baseline design criteria. Each prospective applicant or licensee shall address the following baseline design criteria in the design of new facilities. Each existing licensee shall address the...
10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.
Code of Federal Regulations, 2012 CFR
2012-01-01
... behavior of items relied on for safety. (b) Facility and system design and facility layout must be based on... existing facilities. (a) Baseline design criteria. Each prospective applicant or licensee shall address the following baseline design criteria in the design of new facilities. Each existing licensee shall address the...
10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.
Code of Federal Regulations, 2014 CFR
2014-01-01
... behavior of items relied on for safety. (b) Facility and system design and facility layout must be based on... existing facilities. (a) Baseline design criteria. Each prospective applicant or licensee shall address the following baseline design criteria in the design of new facilities. Each existing licensee shall address the...
Closed-Loop Control for Sonic Fatigue Testing Systems
NASA Technical Reports Server (NTRS)
Rizzi, Stephen A.; Bossaert, Guido
2001-01-01
This article documents recent improvements to the acoustic control system of the Thermal Acoustic Fatigue Apparatus (TAFA), a progressive wave tube test facility at the NASA Langley Research Center, Hampton, VA. A brief summary of past acoustic performance is first given to serve as a basis of comparison with the new performance data using a multiple-input, closed-loop, narrow-band controller. Performance data in the form of test section acoustic power spectral densities and coherence are presented for a variety of input spectra including uniform, band-limited random and an expendable launch vehicle payload bay environment.
49 CFR 193.2019 - Mobile and temporary LNG facilities.
Code of Federal Regulations, 2011 CFR
2011-10-01
... 49 Transportation 3 2011-10-01 2011-10-01 false Mobile and temporary LNG facilities. 193.2019... LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS General § 193.2019 Mobile and temporary LNG facilities. (a) Mobile and temporary LNG facilities for peakshaving application, for service maintenance...
Optics Recycle Loop Strategy for NIF Operations above UV Laser-Induced Damage Threshold
Spaeth, M. L.; Wegner, P. J.; Suratwala, T. I.; ...
2017-03-23
The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL) houses the world’s largest laser system, composed of 192 individual, 40-cm-aperture beamlines. The NIF laser routinely operates at ultraviolet (UV) fluences above 8 J/cm 2, more than twice the (3ω only) damage threshold of commercially available UV-grade fused silica. NIF is able to maintain such high fluence operation by using an optics recycling loop strategy. Successful operation of the loop relies on a number of technologies specifically developed for NIF. One of the most important is the capability developed by LLNL and their vendors for producing highly damage-resistant optics.more » Other technologies developed for the optics recycle loop raise the operating point of NIF by keeping damage growth in check. LLNL has demonstrated the capability to sustain UV fused silica optic recycling rates of up to 40 optics per week. The optics are ready for reinstallation after a 3-week trip through a recycle loop where the damage state of each optic is assessed and repaired. The impact of the optics recycle loop has been profound, allowing the experimental program to routinely employ energies and fluences that would otherwise have been unachievable. Without the recycle loop, it is likely that the NIF fluence would need to be kept below the UV threshold for damage growth, ~4 J/cm 2, thus keeping the energy delivered to the target significantly below 1 MJ. With the recycle loop implemented during the National Ignition Campaign, NIF can routinely deliver >1.8 MJ on target, an increase in operational capability of more than 100%. Finally, in this paper, the enabling technological advances, optical performance, and operational capability implications of the optics recycle loop are discussed.« less
Optics Recycle Loop Strategy for NIF Operations above UV Laser-Induced Damage Threshold
DOE Office of Scientific and Technical Information (OSTI.GOV)
Spaeth, M. L.; Wegner, P. J.; Suratwala, T. I.
The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL) houses the world’s largest laser system, composed of 192 individual, 40-cm-aperture beamlines. The NIF laser routinely operates at ultraviolet (UV) fluences above 8 J/cm 2, more than twice the (3ω only) damage threshold of commercially available UV-grade fused silica. NIF is able to maintain such high fluence operation by using an optics recycling loop strategy. Successful operation of the loop relies on a number of technologies specifically developed for NIF. One of the most important is the capability developed by LLNL and their vendors for producing highly damage-resistant optics.more » Other technologies developed for the optics recycle loop raise the operating point of NIF by keeping damage growth in check. LLNL has demonstrated the capability to sustain UV fused silica optic recycling rates of up to 40 optics per week. The optics are ready for reinstallation after a 3-week trip through a recycle loop where the damage state of each optic is assessed and repaired. The impact of the optics recycle loop has been profound, allowing the experimental program to routinely employ energies and fluences that would otherwise have been unachievable. Without the recycle loop, it is likely that the NIF fluence would need to be kept below the UV threshold for damage growth, ~4 J/cm 2, thus keeping the energy delivered to the target significantly below 1 MJ. With the recycle loop implemented during the National Ignition Campaign, NIF can routinely deliver >1.8 MJ on target, an increase in operational capability of more than 100%. Finally, in this paper, the enabling technological advances, optical performance, and operational capability implications of the optics recycle loop are discussed.« less
The Worker Exposure Failure Modes and Effects Analysis
DOE Office of Scientific and Technical Information (OSTI.GOV)
Lee C. Cadwallader
2004-09-01
This paper documents the activities of the US-Japan exchange in the area of personnel safety at magnetic and laser fusion experiments. A near-miss event with a visiting scientist to the US in 1992 was the impetus for forming the Joint Working Group on Fusion Safety. This exchange has been under way for over ten years and has provided many safety insights for both US and Japanese facility personnel at national institutes and at universities. The background and activities of the Joint Working Group are described, including the facilities that have been visited for safety walkthroughs, the participants from both countries,more » and the main safety issues examined during visits. Based on these visits, some operational safety ideas to enhance experiment safety are given. The near-term future plans of the Safety Monitor Joint Working Group are also discussed.« less
Gallè, Francesca; Di Onofrio, Valeria; Arpesella, Marisa; Bacci, Silvia; Bianco, Antonino; Brandi, Giorgio; Bruno, Stefania; Anastasi, Daniela; Carraro, Elisabetta; Flacco, Maria Elena; Giampaoli, Saverio; Izzotti, Alberto; Leoni, Erica; Bertoncello, Chiara; Minelli, Liliana; Napoli, Christian; Nobile, Carmelo; Pasquarella, Cesira; Liguori, Giorgio; Romano Spica, Vincenzo
2015-01-01
In Italy, students from Movement Science (MS) Degree Courses often work in sport and recreational facilities before graduation. The employment conditions of Movement Science students working in sport/recreational facilities were investigated, and the management and structural features of the facilities were evaluated, including safety policies. Regional differences were also considered. Questionnaires were administered to undergraduate and graduate students (N = 4,217) in 17 Universities. Students' perceptions of the quality of the facilities where they had been employed was evaluated using multivariate analysis. A latent class model with covariates was used to evaluate how variables relating to participants, employment facilities or regions influence their opinions. A high proportion of MS students were employed in sporting facilities (undergraduate level: 33% ; graduate level: 55%), in most cases without any formal employment contracts. Both the structural and hygienic features, as well as the professional knowledge of the staff, were considered good to excellent by the majority of participants (about 70%). Communication of the basic behavioral rules was considered adequate by 61-63% of undergraduate students and 71-75% of graduate students, while nearly half of the participants were dissatisfied with the staff safety training. Correlations between the perceived good structural/hygienic conditions, the presence of regulations and training programs for the staff were investigated. Differences regarding occupational level and safety training among different regions of Italy were also observed. Italian students in Movement Science were easily employed in sport/recreational facilities, but frequently without a formal contract. This is a consequence of the lack of specific regulations in the field of recreational/leisure employment and could have negative implications, especially in terms of safety.
Association between health worker motivation and healthcare quality efforts in Ghana.
Alhassan, Robert Kaba; Spieker, Nicole; van Ostenberg, Paul; Ogink, Alice; Nketiah-Amponsah, Edward; de Wit, Tobias F Rinke
2013-08-14
Ghana is one of the sub-Saharan African countries making significant progress towards universal access to quality healthcare. However, it remains a challenge to attain the 2015 targets for the health related Millennium Development Goals (MDGs) partly due to health sector human resource challenges including low staff motivation. This paper addresses indicators of health worker motivation and assesses associations with quality care and patient safety in Ghana. The aim is to identify interventions at the health worker level that contribute to quality improvement in healthcare facilities. The study is a baseline survey of health workers (n = 324) in 64 primary healthcare facilities in two regions in Ghana. Data collection involved quality care assessment using the SafeCare Essentials tool, the National Health Insurance Authority (NHIA) accreditation data and structured staff interviews on workplace motivating factors. The Spearman correlation test was conducted to test the hypothesis that the level of health worker motivation is associated with level of effort by primary healthcare facilities to improve quality care and patient safety. The quality care situation in health facilities was generally low, as determined by the SafeCare Essentials tool and NHIA data. The majority of facilities assessed did not have documented evidence of processes for continuous quality improvement and patient safety. Overall, staff motivation appeared low although workers in private facilities perceived better working conditions than workers in public facilities (P <0.05). Significant positive associations were found between staff satisfaction levels with working conditions and the clinic's effort towards quality improvement and patient safety (P <0.05). As part of efforts towards attainment of the health related MDGs in Ghana, more comprehensive staff motivation interventions should be integrated into quality improvement strategies especially in government-owned healthcare facilities where working conditions are perceived to be the worst.
Infection prevention and control in the design of healthcare facilities.
Farrow, Tye S; Black, Stephen M
2009-01-01
The lead paper, "Healthcare-Associated Infections as Patient Safety Indicators," written by Gardam, Lemieux, Reason, van Dijk and Goel, puts forward the design of healthcare facilities as one of many strategies to improve patient safety with respect to healthcare-associated infections. This commentary explores some of the issues in balancing infection prevention and control priorities with other needs and values brought to the design process. This balance is challenged not only by a lack of supporting evidence but also by the superficial nature in which infection prevention and control are often discussed within a design context. For the physical environment to support any patient safety initiative, the design of the processes must be developed in conjunction with that of the physical environment so that compliance can be natural and convenient. Finally, consideration is given to the value of documenting decision-making related to infection prevention and control in facility design and ongoing assessments of existing facilities.
The Department of Energy Nuclear Criticality Safety Program
NASA Astrophysics Data System (ADS)
Felty, James R.
2005-05-01
This paper broadly covers key events and activities from which the Department of Energy Nuclear Criticality Safety Program (NCSP) evolved. The NCSP maintains fundamental infrastructure that supports operational criticality safety programs. This infrastructure includes continued development and maintenance of key calculational tools, differential and integral data measurements, benchmark compilation, development of training resources, hands-on training, and web-based systems to enhance information preservation and dissemination. The NCSP was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 97-2, Criticality Safety, and evolved from a predecessor program, the Nuclear Criticality Predictability Program, that was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 93-2, The Need for Critical Experiment Capability. This paper also discusses the role Dr. Sol Pearlstein played in helping the Department of Energy lay the foundation for a robust and enduring criticality safety infrastructure.
48 CFR 923.7001 - Nuclear safety.
Code of Federal Regulations, 2010 CFR
2010-10-01
... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Nuclear safety. 923.7001... Efficiency, Renewable Energy Technologies, and Occupational Safety Programs 923.7001 Nuclear safety. The DOE regulates the nuclear safety of its major facilities under its own statutory authority derived from the...