Experimental study of near-field entrainment of moderately overpressured jets

Science.gov (United States)

Solovitz, S.A.; Mastin, L.G.; Saffaraval, F.

2011-01-01

Particle image velocimetry (PIV) experiments have been conducted to study the velocity flow fields in the developing flow region of high-speed jets. These velocity distributions were examined to determine the entrained mass flow over a range of geometric and flow conditions, including overpressured cases up to an overpressure ratio of 2.83. In the region near the jet exit, all measured flows exhibited the same entrainment up until the location of the first shock when overpressured. Beyond this location, the entrainment was reduced with increasing overpressure ratio, falling to approximately 60 of the magnitudes seen when subsonic. Since entrainment ratios based on lower speed, subsonic results are typically used in one-dimensional volcanological models of plume development, the current analytical methods will underestimate the likelihood of column collapse. In addition, the concept of the entrainment ratio normalization is examined in detail, as several key assumptions in this methodology do not apply when overpressured.

Calculating overpressure from BLEVE explosions

Energy Technology Data Exchange (ETDEWEB)

Planas-Cuchi, E.; Casal, J. [Universitat Politecnica de Catalunya, Barcelona (Spain). Department of Chemical Engineering, Centre for Technological Risk Studies; Salla, J.M. [Universitat Politecnica de Catalunya, Barcelona (Spain). Department of Heat Engines

2004-11-01

Although a certain number of authors have analyzed the prediction of boiling liquid expanding vapour explosion (BLEVE) and fireball effects, only very few of them have proposed methodologies for predicting the overpressure from such explosions. In this paper, the methods previously published are discussed and shown to introduce a significant overestimation due to erroneous thermodynamic assumptions - ideal gas behaviour and isentropic vapour expansion - on which they are based (in fact, they give the maximum value of overpressure which can be caused by a BLEVE). A new approach is proposed, based on the - more realistic - assumption of an adiabatic and irreversible expansion process; the real properties of the substance involved in the explosion are used. The two methods are compared through the application to a given case. (author)

A wireless lingual feedback device to reduce overpressures in seated posture: a feasibility study.

Directory of Open Access Journals (Sweden)

Olivier Chenu

2009-10-01

Full Text Available Pressure sores are localized injuries to the skin and underlying tissues and are mainly resulting from overpressure. Paraplegic peoples are particularly subjects to pressure sores because of long-time seated postures and sensory deprivation at the lower limbs.Here we report outcomes of a feasibility trial involving a biofeedback system aimed at reducing buttock overpressure whilst an individual is seated. The system consists of (1 pressure sensors, (2 a laptop coupling sensors and actuator (3 a wireless Tongue Display Unit (TDU consisting of a circuit embedded in a dental retainer with electrodes put in contact with the tongue. The principle consists in (1 detecting overpressures in people who are seated over long periods of time, (2 estimating a postural change that could reduce these overpressures and (3 communicating this change through directional information transmitted by the TDU.Twenty-four healthy subjects voluntarily participated in this study. Twelve healthy subjects initially formed the experimental group (EG and were seated on a chair with the wireless TDU inside their mouth. They were asked to follow TDU orders that were randomly spread throughout the session. They were evaluated during two experimental sessions during which 20 electro-stimulations were sent. Twelve other subjects, added retrospectively, formed the control group (CG. These subjects participated in one session of the same experiment without any biofeedback.Three dependent variables were computed: (1 the ability of subjects to reach target posture (EG versus CG, (2 high pressure reductions after a biofeedback (EG versus CG and (3 the level of these reductions relative to their initial values (EG only. Results show (1 that EG reached target postures in 90.2% of the trials, against 5,3% in the CG, (2 a significant reduction in overpressures in the EG compared to the CG and (3, for the EG, that the higher the initial pressures were, the more they were decreased

A Wireless Lingual Feedback Device to Reduce Overpressures in Seated Posture: A Feasibility Study

Science.gov (United States)

Chenu, Olivier; Vuillerme, Nicolas; Demongeot, Jacques; Payan, Yohan

2009-01-01

Background Pressure sores are localized injuries to the skin and underlying tissues and are mainly resulting from overpressure. Paraplegic peoples are particularly subjects to pressure sores because of long-time seated postures and sensory deprivation at the lower limbs. Methodology/Principal Findings Here we report outcomes of a feasibility trial involving a biofeedback system aimed at reducing buttock overpressure whilst an individual is seated. The system consists of (1) pressure sensors, (2) a laptop coupling sensors and actuator (3) a wireless Tongue Display Unit (TDU) consisting of a circuit embedded in a dental retainer with electrodes put in contact with the tongue. The principle consists in (1) detecting overpressures in people who are seated over long periods of time, (2) estimating a postural change that could reduce these overpressures and (3) communicating this change through directional information transmitted by the TDU.Twenty-four healthy subjects voluntarily participated in this study. Twelve healthy subjects initially formed the experimental group (EG) and were seated on a chair with the wireless TDU inside their mouth. They were asked to follow TDU orders that were randomly spread throughout the session. They were evaluated during two experimental sessions during which 20 electro-stimulations were sent. Twelve other subjects, added retrospectively, formed the control group (CG). These subjects participated in one session of the same experiment without any biofeedback.Three dependent variables were computed: (1) the ability of subjects to reach target posture (EG versus CG), (2) high pressure reductions after a biofeedback (EG versus CG) and (3) the level of these reductions relative to their initial values (EG only). Results show (1) that EG reached target postures in 90.2% of the trials, against 5,3% in the CG, (2) a significant reduction in overpressures in the EG compared to the CG and (3), for the EG, that the higher the initial pressures

Analysis of selected Halden overpressure tests using the FALCON code

Energy Technology Data Exchange (ETDEWEB)

Khvostov, G., E-mail: grigori.khvostov@psi.ch [Paul Scherrer Institut, CH 5232 Villigen PSI (Switzerland); Wiesenack, W. [Institute for Energy Technology – OECD Halden Reactor Project, P.O. Box 173, N-1751 Halden (Norway)

2016-12-15

Highlights: • We analyse four Halden overpressure tests. • We determine a critical overpressure value for lift-off in a BWR fuel sample. • We show the role of bonding in over-pressurized rod behaviour. • We analytically quantify the degree of bonding via its impact on cladding elongation. • We hypothesize on an effect of circumferential cracks on thermal fuel response to overpressure. • We estimate a thermal effect of circumferential cracks based on interpretation of the data. - Abstract: Four Halden overpressure (lift-off) tests using samples with uranium dioxide fuel pre-irradiated in power reactors to a burnup of 60 MWd/kgU are analyzed. The FALCON code coupled to a mechanistic model, GRSW-A for fission gas release and gaseous-bubble swelling is used for the calculation. The advanced version of the FALCON code is shown to be applicable to best-estimate predictive analysis of overpressure tests using rods without, or weak pellet-cladding bonding, as well as scoping analysis of tests with fuels where stronger pellet-cladding bonding occurs. Significant effects of bonding and fuel cracking/relocation on the thermal and mechanical behaviour of highly over-pressurized rods are shown. The effect of bonding is particularly pronounced in the tests with the PWR samples. The present findings are basically consistent with an earlier analysis based on a direct interpretation of the experimental data. Additionally, in this paper, the specific effects are quantified based on the comparison of the data with the results of calculation. It is concluded that the identified effects are largely beyond the current traditional fuel-rod licensing analysis methods.

Improved Overpressure Recording and Modeling for Near-Surface Explosion Forensics

Science.gov (United States)

Kim, K.; Schnurr, J.; Garces, M. A.; Rodgers, A. J.

2017-12-01

The accurate recording and analysis of air-blast acoustic waveforms is a key component of the forensic analysis of explosive events. Smartphone apps can enhance traditional technologies by providing scalable, cost-effective ubiquitous sensor solutions for monitoring blasts, undeclared activities, and inaccessible facilities. During a series of near-surface chemical high explosive tests, iPhone 6's running the RedVox infrasound recorder app were co-located with high-fidelity Hyperion overpressure sensors, allowing for direct comparison of the resolution and frequency content of the devices. Data from the traditional sensors is used to characterize blast signatures and to determine relative iPhone microphone amplitude and phase responses. A Wiener filter based source deconvolution method is applied, using a parameterized source function estimated from traditional overpressure sensor data, to estimate system responses. In addition, progress on a new parameterized air-blast model is presented. The model is based on the analysis of a large set of overpressure waveforms from several surface explosion test series. An appropriate functional form with parameters determined empirically from modern air-blast and acoustic data will allow for better parameterization of signals and the improved characterization of explosive sources.

Over-pressure in road tankers; Ueberdrucksicherung an Tankfahrzeugen

Energy Technology Data Exchange (ETDEWEB)

Frobese, Dirk-Hans; Pape, Harald [Physikalisch-Technische Bundesanstalt, Braunschweig (Germany)

2011-08-15

This work was aimed at determining possible causes of overpressure damages on road tankers. In cooperation with the manufacturers of road tankers, the equipment of road tankers usually used today was, therefore, discussed and possible error sources determined. In measurements performed at two filling stations, real pressure, temperature and volume flow ratios for the loading of a road tanker were recorded. Parallel to it, tests in a cold chamber were carried out to determine the possibility and the general conditions of an icing of the tilting valve and the flame arrester. With these results, scenarios have been worked out which can explain known overpressure damaging events. On the basis of a risk assessment, measures are described how such overpressure damages on road tankers can in future be avoided. (orig.)

Effect of overpressure on gas hydrate distribution

Energy Technology Data Exchange (ETDEWEB)

Bhatnagar, G.; Chapman, W.G.; Hirasaki, G.J. [Rice Univ., Houston, TX (United States). Dept. of Chemical and Biomolecular Engineering; Dickens, G.R.; Dugan, B. [Rice Univ., Houston, TX (United States). Dept. of Earth Sciences

2008-07-01

Natural gas hydrate systems can be characterized by high sedimentation rates and/or low permeability sediments, which can lead to pore pressure higher than hydrostatic. This paper discussed a study that examined this effect of overpressure on gas hydrate and free gas distribution in marine sediments. A one-dimensional numerical model that coupled sedimentation, fluid flow, and gas hydrate formation was utilized. In order to quantify the relative importance of sedimentation rates and low permeability sediments, a dimensionless sedimentation-compaction group (scN) was defined, that compared the absolute permeability of the sediments to the sedimentation rate. Higher values of scN mean higher permeability or low sedimentation rate which generally yield hydrostatic pore pressure while lower values of scN normally create pore pressure greater than hydrostatic. The paper discussed non-hydrostatic consolidation in gas hydrate systems, including mass balances; constitutive relationships; normalized variables; and dimensionless groups. A numerical solution to the problem was presented. It was concluded that simulation results demonstrated that decreasing scN not only increased pore pressure above hydrostatic values, but also lowered the lithostatic stress gradient and gas hydrate saturation. This occurred because overpressure resulted in lower effective stress, causing higher porosity and lower bulk density of the sediment. 16 refs., 5 figs., 1 appendix.

A Study on the Optimization Method of the Main Steam Safety Valve Characteristics for Overpressure Protection

Energy Technology Data Exchange (ETDEWEB)

Kim, Kyoung Ryun; Kim, Ung Soo; Pakr, Min Soo; Lee, Gyu Cheon; Kim, Shin Whan [KEPCO EnC Company Inc., Daejeon (Korea, Republic of)

2015-05-15

safety margin of overpressure protection. And this can be used as a good technical background for the design modification of NPPs.

The Development of a Cryogenic Over-Pressure

Energy Technology Data Exchange (ETDEWEB)

Alvarez, Matthew L. [Illinois Inst. of Technology, Chicago, IL (United States)

2012-01-01

The Dark Energy Survey (DES) project will study the accelerated expansion of the universe. In order to further study this phenomenon, scientists have devised a method of creating an array of charged couple devices (CCD) to capture images that will be studied. These CCDs must be cooled and remain at 173K to eliminate thermal gradients and dark current. Therefore, a two-phase CCD liquid nitrogen (LN2) cooling system was designed to maintain the array of CCDs at a constant temperature. However, the centrifugal pump used to supply LN2 has a mean time between failure (MTBF) of approximately two thousand-eight hundred hours (116 days). Because of the low MTBF of the centrifugal pump, a new pump is being considered to replace the existing one. This positive displacement pump is a simpler design that is expected to have a MTBF that will exceed 116 days (2800hrs). This positive displacement reciprocating pump, also known as, the cryogenic over-pressure pump (OPP), was tested in February 2012 and successfully cooled the CCD array to 173K. Though unfit for service for DES CCD cooling system, the overall concept of this pump has been proven. Typical ow rates, pressures, and temperatures trends have been captured via instrumentation and are specific to the operation of future over-pressure pumps.

REDUCING THE BOOSTER STATIONS ENERGY CONSUMPTION BY WAY OF ELIMINATING OVERPRESSURE IN THE WATER SUPPLY NETWORK

Directory of Open Access Journals (Sweden)

G. N. Zdor

2015-01-01

Full Text Available The energy efficiency improvement of the city housing-and-utilities infrastructure and watersupply and water-disposal systems poses an occurrent problem. The water-supply systems energy consumption sizable share falls on the pump plants. The article deals with the issues of the operating regime management of the existing booster stations equipped with a group of pumping units regulated with frequency converters. One of the optimization directions of their energy consumption is the reduction of over-pressure in the water-distribution network and its sustentation within the regulatory values. The authors offer the structure and methodology of the data collection-and-analysis automated system utilization for revealing and eliminating the overpressure in the water-supply network. This system is designed for the group management of booster-stations operating regimes on the ground of data obtained from the pressure controlling devices at the consumers. The data exchange in the system is realized via GSM.The paper presents results of the tests carried out at the booster stations in some major cities of the Republic of Belarus. The authors analyze dependence of overpressure in the network on the methods of the plant output pressure sustentation (daily graph or constant pressure. The authors study the elimination effect of over-pressure in the water distribution network on changing the booster station pumping units operation regimes. The study shows that eliminating over pressure in the water distributing network leads to lowering the booster station pressure. This in its turn decreases its energy consumption by 15–20 % depending on the over pressure fixed level.

Attenuation of blast pressure behind ballistic protective vests.

Science.gov (United States)

Wood, Garrett W; Panzer, Matthew B; Shridharani, Jay K; Matthews, Kyle A; Capehart, Bruce P; Myers, Barry S; Bass, Cameron R

2013-02-01

Clinical studies increasingly report brain injury and not pulmonary injury following blast exposures, despite the increased frequency of exposure to explosive devices. The goal of this study was to determine the effect of personal body armour use on the potential for primary blast injury and to determine the risk of brain and pulmonary injury following a blast and its impact on the clinical care of patients with a history of blast exposure. A shock tube was used to generate blast overpressures on soft ballistic protective vests (NIJ Level-2) and hard protective vests (NIJ Level-4) while overpressure was recorded behind the vest. Both types of vest were found to significantly decrease pulmonary injury risk following a blast for a wide range of conditions. At the highest tested blast overpressure, the soft vest decreased the behind armour overpressure by a factor of 14.2, and the hard vest decreased behind armour overpressure by a factor of 56.8. Addition of body armour increased the 50th percentile pulmonary death tolerance of both vests to higher levels than the 50th percentile for brain injury. These results suggest that ballistic protective body armour vests, especially hard body armour plates, provide substantial chest protection in primary blasts and explain the increased frequency of head injuries, without the presence of pulmonary injuries, in protected subjects reporting a history of blast exposure. These results suggest increased clinical suspicion for mild to severe brain injury is warranted in persons wearing body armour exposed to a blast with or without pulmonary injury.

Displacement and stress fields around rock fractures opened by irregular overpressure variations

Directory of Open Access Journals (Sweden)

Shigekazu eKusumoto

2014-05-01

Full Text Available Many rock fractures are entirely driven open by fluids such as ground water, geothermal water, gas, oil, and magma. These are a subset of extension fractures (mode I cracks; e.g., dikes, mineral veins and joints referred to as hydrofractures. Field measurements show that many hydrofractures have great variations in aperture. However, most analytical solutions for fracture displacement and stress fields assume the loading to be either constant or with a linear variation. While these solutions have been widely used, it is clear that a fracture hosted by heterogeneous and anisotropic rock is normally subject to loading that is neither constant nor with a linear variation. Here we present new general solutions for the displacement and stress fields around hydrofractures, modelled as two-dimensional elastic cracks, opened by irregular overpressure variations given by the Fourier cosine series. Each solution has two terms. The first term gives the displacement and stress fields due to the average overpressure acting inside the crack; it is given by the initial term of the Fourier coefficients expressing the overpressure variation. The second term gives the displacement and stress fields caused by the overpressure variation; it is given by general terms of the Fourier coefficients and solved through numerical integration. Our numerical examples show that the crack aperture variation closely reflects the overpressure variation. Also, that the general displacement and stress fields close to the crack follow the overpressure variation but tend to be more uniform far from the crack. The present solutions can be used to estimate the displacement and stress fields around any fluid-driven crack, that is, any hydrofracture, as well as its aperture, provided the variation in overpressure can be described by Fourier series. The solutions add to our understanding of local stresses, displacements, and fluid transport associated with hydrofractures in the crust.

Study of blast wave overpressures using the computational fluid dynamics

Directory of Open Access Journals (Sweden)

M. L. COSTA NETO

Full Text Available ABSTRACT The threats of bomb attacks by criminal organizations and accidental events involving chemical explosives are a danger to the people and buildings. Due the severity of these issues and the need of data required for a safety design, more research is required about explosions and shock waves. This paper presents an assessment of blast wave overpressures using a computational fluid dynamics software. Analyses of phenomena as reflection of shock waves and channeling effects were done and a comparison between numerical results and analytical predictions has been executed, based on the simulation on several models. The results suggest that the common analytical predictions aren’t accurate enough for an overpressure analysis in small stand-off distances and that poorly designed buildings may increase the shock wave overpressures due multiple blast wave reflections, increasing the destructive potential of the explosions.

Investigation on the relationship between overpressure and sub-harmonic response from encapsulated microbubbles

International Nuclear Information System (INIS)

Wu Jun; Xu Di; Fan Ting-Bo; Zhang Dong

2014-01-01

Sub-harmonic component generated from microbubbles is proven to be potentially used in noninvasive blood pressure measurement. Both theoretical and experimental studies are performed in the present work to investigate the dependence of the sub-harmonic generation on the overpressure with different excitation pressure amplitudes and pulse lengths. With 4-MHz ultrasound excitation at an applied acoustic pressure amplitude of 0.24 MPa, the measured sub-harmonic amplitude exhibits a decreasing change as overpressure increases; while non-monotonic change is observed for the applied acoustic pressures of 0.36 MPa and 0.48 MPa, and the peak position in the curve of the sub-harmonic response versus the overpressure shifts toward higher overpressure as the excitation pressure amplitude increases. Furthermore, the exciting pulse with long duration could lead to a better sensitivity of the sub-harmonic response to overpressure. The measured results are explained by the numerical simulations based on the Marmottant model. The numerical simulations qualitatively accord with the measured results. This work might provide a preliminary proof for the optimization of the noninvasive blood pressure measurement through using sub-harmonic generation from microbubbles. (electromagnetism, optics, acoustics, heat transfer, classical mechanics, and fluid dynamics)

Investigation on the relationship between overpressure and sub-harmonic response from encapsulated microbubbles

Science.gov (United States)

Wu, Jun; Fan, Ting-Bo; Xu, Di; Zhang, Dong

2014-10-01

Sub-harmonic component generated from microbubbles is proven to be potentially used in noninvasive blood pressure measurement. Both theoretical and experimental studies are performed in the present work to investigate the dependence of the sub-harmonic generation on the overpressure with different excitation pressure amplitudes and pulse lengths. With 4-MHz ultrasound excitation at an applied acoustic pressure amplitude of 0.24 MPa, the measured sub-harmonic amplitude exhibits a decreasing change as overpressure increases; while non-monotonic change is observed for the applied acoustic pressures of 0.36 MPa and 0.48 MPa, and the peak position in the curve of the sub-harmonic response versus the overpressure shifts toward higher overpressure as the excitation pressure amplitude increases. Furthermore, the exciting pulse with long duration could lead to a better sensitivity of the sub-harmonic response to overpressure. The measured results are explained by the numerical simulations based on the Marmottant model. The numerical simulations qualitatively accord with the measured results. This work might provide a preliminary proof for the optimization of the noninvasive blood pressure measurement through using sub-harmonic generation from microbubbles.

Analysis of Reactor Pressurized Thermal Shock Conditions Considering Upgrading of Systems Important to Safety

International Nuclear Information System (INIS)

Mazurok, A.S; Vyshemirskyij, M.P.

2015-01-01

The paper analyzes conditions of pressurized thermal shock on the reactor pressure vessel taking into account upgrading of the emergency core cooling system and primary overpressure protection system. For representative accident scenarios, calculation and comparative analysis was carried out. These scenarios include a small leak from the hot leg and PRZ SV stuck opening with re closure after 3600 sec and 3 SG heat transfer tube rupture. The efficiency of mass flow control by valves on the pump head (emergency core cooling systems) and cold overpressure protection (primary overpressure protection system) was analyzed. The thermal hydraulic model for RELAP5/Mod3.2 code with detailed downcomer (DC) model and changes in accordance with upgrades was used for calculations. Detailed (realistic) modeling of piping and equipment was performed. The upgrades prevent excessive primary cooling and, consequently, help to preserve the RPV integrity and to avoid the formation of a through crack, which can lead to a severe accident

Nankai Stress History and Implications for an Overpressured Decollement

Science.gov (United States)

Moran, K.; O'Regan, M.

2005-12-01

The Nankai Trough, formed from the subduction of the Shikoku Basin beneath the island arc of southwestern Japan, is a relatively young accretionary complex converging at a rate of ~4 cm/yr [Shipboard Scientific Party, 2001a]. The region was studied during the Deep Sea Drilling Project and on three Ocean Drilling Program (ODP) Legs-131, 190 and 196. Three sites visited during these Legs form a single cross-margin transect (dubbed the Muroto Transect) that traverses the leading edge of the Nankai accretionary prism, from seaward of the deformation front at Site 1173, to close to the deformation front (Site 1174), and landward to the first frontal thrust (Site 808). The decollement, which forms the major boundary between the converging plates, occurs within the Lower Shikoku Basin stratigraphic unit. The ODP sites were drilled and cored to depths below the decollement (Sites 808 and 1174) and the proto-decollement (Site 1173). Here we present consolidation test results [Moran et al., 1993] that are consistent with porosity-depth functions from core and log measurements for the Lower Shikoku Basin sediments, assuming that the decollement is an overpressured seal. At 1173, where a true decollement has not yet formed, moderate fluid overpressures occur that can be fully attributed to high turbiditic sedimentation rates. Forward modeling of this site into the deformation front over a period of ~300 ky shows that the present 1173 porosity-depth function matches the porosity-depth function at 1174. These results suggest that the young decollement on the Muroto Transect at the deformation front and landward is highly overpressured and forms a seal to sediments below that can be classically modeled as a one-dimensional consolidation system.

Detecting overpressure using the Eaton and Equivalent Depth methods in Offshore Nova Scotia, Canada

Science.gov (United States)

Ernanda; Primasty, A. Q. T.; Akbar, K. A.

2018-03-01

Overpressure is an abnormal high subsurface pressure of any fluids which exceeds the hydrostatic pressure of column of water or formation brine. In Offshore Nova Scotia Canada, the values and depth of overpressure zone are determined using the eaton and equivalent depth method, based on well data and the normal compaction trend analysis. Since equivalent depth method is using effective vertical stress principle and Eaton method considers physical property ratio (velocity). In this research, pressure evaluation only applicable on Penobscot L-30 well. An abnormal pressure is detected at depth 11804 feet as possibly overpressure zone, based on pressure gradient curve and calculation between the Eaton method (7241.3 psi) and Equivalent Depth method (6619.4 psi). Shales within Abenaki formation especially Baccaro Member is estimated as possible overpressure zone due to hydrocarbon generation mechanism.

Overpressure, Flow Focusing, Compaction and Slope Stability on the continental slope: Insights from IODP Expedition 308

Science.gov (United States)

Flemings, P. B.

2010-12-01

Integrated Ocean Drilling Program Expepedition 308 used direct measurements of pore pressure, analysis of hydromechanical properties, and geological analysis to illuminate how sedimentation, flow focusing, overpressure, and slope stability couple beneath the seafloor on the deepwater continental slope in the Gulf of Mexico. We used pore pressure penetrometers to measure severe overpressures (60% of the difference between lithostatic stress and hydrostatic pressure) that extend from the seafloor for 100’s of meters. We ran uniaxial consolidation experiments on whole core and found that although permeability is relatively high near the seafloor, the sediments are highly compressible. As a result, the coefficient of consolidation (the hydraulic diffusivity) is remarkably constant over a large range of effective stresses. This behavior accounts for the high overpressure that begins near the seafloor and extends to depth. Forward modeling suggests that flow is driven laterally along a permeable unit called the Blue Unit. Calculations suggest that soon after deposition, lateral flow lowered the effective stress and triggered the submarine landslides that we observe. Later in the evolution of this system, overpressure may have pre-conditioned the slope to failure by earthquakes. Results from IODP Expedition 308 illustrate how pore pressure and sedimentation control the large-scale form of continental margins, how submarine landslides form, and provide strategies for designing stable drilling programs.

A study of sonic boom overpressure trends with respect to weight, altitude, Mach number, and vehicle shaping

Science.gov (United States)

Needleman, Kathy E.; Mack, Robert J.

1990-01-01

This paper presents and discusses trends in nose shock overpressure generated by two conceptual Mach 2.0 configurations. One configuration was designed for high aerodynamic efficiency, while the other was designed to produce a low boom, shaped-overpressure signature. Aerodynamic lift, sonic boom minimization, and Mach-sliced/area-rule codes were used to analyze and compute the sonic boom characteristics of both configurations with respect to cruise Mach number, weight, and altitude. The influence of these parameters on the overpressure and the overpressure trends are discussed and conclusions are given.

Use of loop-seals for the control of the overpressures in hydraulic transients evolving in a sea service water system

Energy Technology Data Exchange (ETDEWEB)

Canetta, D.; Capozza, A.; Iovino, G.

1985-01-01

The transient response following pump trip-offs and start-ups was investigated in the sea water system of a nuclear power plant. Specific care was devoted to water column separation and cavity collapse phenomena. A computer program designed for analysis of complex hydraulic networks was used. It is found that dangerous overpressures can be avoided by the use of loop seals. The design of the vacuum breaker valves of the loop seals and the optimization of overall transient behavior is discussed. 1 reference.

Identification of low-overpressure interval and its implication to hydrocarbon migration: Case study in the Yanan sag of the Qiongdongnan Basin, South China Sea

Science.gov (United States)

Xu, Qinghai; Shi, Wanzhong; Xie, Yuhong; Wang, Zhenfeng; Li, Xusheng; Tong, Chuanxin

2017-01-01

The Qiongdongnan Basin is a strongly overpressured basin with the maximum pressure coefficient (the ratio of the actual pore pressure versus hydrostatic pressure at the same depth) over 2.27. However, there exists a widespread low-overpressure interval between the strong overpressure intervals in the Yanan Sag of western basin. The mechanisms of the low-overpressure interval are not well understood. Three main approaches, pore pressure test data and well-log analysis, pressure prediction based on the relationship between the deviation of the velocity and the pressure coefficients, and numerical modeling, were employed to illustrate the distribution and evolution of the low-overpressure interval. And we analyzed and explained the phenomenon of the low-overpressure interval that is both underlain and overlain by high overpressure internal. The low-overpressure interval between the strong overpressure intervals can be identified and modelled by drilling data of P-wave sonic and the mud weight, and the numerical modeling using the PetroMod software. Results show that the low-overpressure interval is mainly composed of sandstone sediments. The porosities of sandstone in the low-overpressure interval primarily range from 15%-20%, and the permeabilities range from 10–100 md. Analysis of the geochemical parameters of C1, iC4/nC4, ΔR3, and numerical modeling shows that oil and gas migrated upward into the sandstone in the low-overpressure interval, and then migrated along the sandstone of low-overpressure interval into the Yacheng uplift. The low-overpressure both underlain and overlain by overpressure resulted from the fluids migrating along the sandstones in the low-overpressure interval into the Yacheng uplift since 1.9Ma. The mudstone in the strong overpressure interval is good cap overlain the sandstone of low-overpressure interval, therefore up-dip pinchouts or isolated sandstone in the low-overpressure interval locating the migration path of oil and gas are good

Investigation of Thermophysical Parameters Properties for Enhancing Overpressure Mechanism Estimation. Case Study: Miri Area, West Baram Delta

Science.gov (United States)

Adha, Kurniawan; Yusoff, Wan Ismail Wan; Almanna Lubis, Luluan

2017-10-01

Determining the pore pressure data and overpressure zone is a compulsory part of oil and gas exploration in which the data can enhance the safety with profit and preventing the drilling hazards. Investigation of thermophysical parameters such as temperature and thermal conductivity can enhance the pore pressure estimation for overpressure mechanism determination. Since those parameters are dependent on rock properties, it may reflect the changes on the column of thermophysical parameters when there is abnormally in pore pressure. The study was conducted in “MRI 1” well offshore Sarawak, where a new approach method designed to determine the overpressure generation. The study was insisted the contribution of thermophysical parameters for supporting the velocity analysis method, petrophysical analysis were done in these studies. Four thermal facies were identified along the well. The overpressure developed below the thermal facies 4, where the pressure reached 38 Mpa and temperature was increasing significantly. The velocity and the thermal conductivity cross plots shows a linear relationship since the both parameters mainly are the function of the rock compaction. When the rock more compact, the particles were brought closer into contact and making the sound wave going faster while the thermal conductivity were increasing. In addition, the increment of temperature and high heat flow indicated the presence of fluid expansion mechanism. Since the shale sonic velocity and density analysis were the common methods in overpressure mechanism and pore pressure estimation. As the addition parameters for determining overpressure zone, the presence of thermophysical analysis was enhancing the current method, where the current method was the single function of velocity analysis. The presence of thermophysical analysis will improve the understanding in overpressure mechanism determination as the new input parameters. Thus, integrated of thermophysical technique and velocity

Rapid sedimentation and overpressure in shallow sediments of the Bering Trough, offshore southern Alaska

Science.gov (United States)

Daigle, Hugh; Worthington, Lindsay L.; Gulick, Sean P. S.; Van Avendonk, Harm J. A.

2017-04-01

Pore pressures in sediments at convergent margins play an important role in driving chemical fluxes and controlling deformation styles and localization. In the Bering Trough offshore Southern Alaska, extreme sedimentation rates over the last 140 kyr as a result of glacial advance/retreats on the continental shelf have resulted in elevated pore fluid pressures in slope sediments overlying the Pamplona Zone fold and thrust belt, the accretionary wedge resulting from subduction of the Yakutat microplate beneath the North American Plate. Based on laboratory experiments and downhole logs acquired at Integrated Ocean Drilling Program Site U1421, we predict that the overpressure in the slope sediments may be as high as 92% of the lithostatic stress. Results of one-dimensional numerical modeling accounting for changes in sedimentation rate over the last 130 kyr predicted overpressures that are consistent with our estimates, suggesting that the overpressure is a direct result of the rapid sedimentation experienced on the Bering shelf and slope. Comparisons with other convergent margins indicate that such rapid sedimentation and high overpressure are anomalous in sediments overlying accretionary wedges. We hypothesize that the shallow overpressure on the Bering shelf/slope has fundamentally altered the deformation style within the Pamplona Zone by suppressing development of faults and may inhibit seismicity by focusing faulting elsewhere or causing deformation on existing faults to be aseismic. These consequences are probably long-lived as it may take several million years for the excess pressure to dissipate.

New-construction techniques and HVAC overpressurization for radon reduction in schools

International Nuclear Information System (INIS)

Saum, D.; Witter, K.A.; Craig, A.B.

1988-01-01

Construction of a school in Fairfax County, Virginia, is being carefully monitored since elevated indoor radon levels have been identified in many existing houses near the site. Soil gas radon concentrations measured prior to pouring of the slabs were also indicative of a potential radon problem should the soil gas enter the school; however, subslab radon measurements collected thus far are lower than anticipated. Radon-resistant features have been incorporated into construction of the school and include the placing of at least 100 mm of clean coarse aggregate under the slab and a plastic film barrier between the aggregate and the slab, the sealing of all expansion joints, the sealing or plugging of all utility penetrations where possible, and the painting of interior block walls. In addition, the school's heating, ventilating, and air-conditioning (HVAC) system has been designed to operate continuously in overpressurization to help reduce pressure-driven entry of radon-containing soil gas into the building. Following completion, indoor radon levels in the school will be monitored to determine the effectiveness of these radon-resistant new-construction techniques and HVAC overpressurization in limiting radon entry into the school

Thermodynamically consistent model of brittle oil shales under overpressure

Science.gov (United States)

Izvekov, Oleg

2016-04-01

The concept of dual porosity is a common way for simulation of oil shale production. In the frame of this concept the porous fractured media is considered as superposition of two permeable continua with mass exchange. As a rule the concept doesn't take into account such as the well-known phenomenon as slip along natural fractures, overpressure in low permeability matrix and so on. Overpressure can lead to development of secondary fractures in low permeability matrix in the process of drilling and pressure reduction during production. In this work a new thermodynamically consistent model which generalizes the model of dual porosity is proposed. Particularities of the model are as follows. The set of natural fractures is considered as permeable continuum. Damage mechanics is applied to simulation of secondary fractures development in low permeability matrix. Slip along natural fractures is simulated in the frame of plasticity theory with Drucker-Prager criterion.

Simulation and Measurements of Small Arms Blast Wave Overpressure in the Process of Designing a Silencer

Directory of Open Access Journals (Sweden)

Hristov Nebojša

2015-02-01

Full Text Available Simulation and measurements of muzzle blast overpressure and its physical manifestations are studied in this paper. The use of a silencer can have a great influence on the overpressure intensity. A silencer is regarded as an acoustic transducer and a waveguide. Wave equations for an acoustic dotted source of directed effect are used for physical interpretation of overpressure as an acoustic phenomenon. Decomposition approach has proven to be suitable to describe the formation of the output wave of the wave transducer. Electroacoustic analogies are used for simulations. A measurement chain was used to compare the simulation results with the experimental ones.

Explosion overpressure test series: General-Purpose Heat Source development: Safety Verification Test program

International Nuclear Information System (INIS)

Cull, T.A.; George, T.G.; Pavone, D.

1986-09-01

The General-Purpose Heat Source (GPHS) is a modular, radioisotope heat source that will be used in radioisotope thermoelectric generators (RTGs) to supply electric power for space missions. The first two uses will be the NASA Galileo and the ESA Ulysses missions. The RTG for these missions will contain 18 GPHS modules, each of which contains four 238 PuO 2 -fueled clads and generates 250 W/sub (t)/. A series of Safety Verification Tests (SVTs) was conducted to assess the ability of the GPHS modules to contain the plutonia in accident environments. Because a launch pad or postlaunch explosion of the Space Transportation System vehicle (space shuttle) is a conceivable accident, the SVT plan included a series of tests that simulated the overpressure exposure the RTG and GPHS modules could experience in such an event. Results of these tests, in which we used depleted UO 2 as a fuel simulant, suggest that exposure to overpressures as high as 15.2 MPa (2200 psi), without subsequent impact, does not result in a release of fuel

Analysis of over-pressure mechanisms in the Uinta Basin, Utah

Energy Technology Data Exchange (ETDEWEB)

McPherson, B.; Bredehoeft, J. [Geological Survey, Menlo Park, CA (United States)

1995-03-01

Extremely high pore fluid pressures exist in the area of the Altamount/Bluebell oil field in the Uinta basin, Utah. We discuss two possible mechanisms for the cause of these over-pressures in this paper: (1) compaction disequilibrium, and (2) conversion of kerogen to liquid hydrocarbon (oil). Compaction disequilibrium occurs during periods of rapid sedimentation. If the permeability of deeply buried strata is low, then connate water within the rock matrix does not escape rapidly enough as compaction occurs; as sedimentary deposition continues, high pore fluid pressures develop. Conversion of solid kerogen to a liquid generates both a liquid and additional pore space for the liquid to occupy. If the volume of the liquid generated is just sufficient to fill the pore space generated, then there will be no accompanying effect on the pore pressure. If the liquid is less dense than the solid it replaces, then there is more liquid than pore space created; pore pressure will increase, causing flow away from the area of the reaction. Pore pressure is a sensitive measure of the balance between hydrocarbon generation and expulsion from the source into adjacent strata. If high pore pressures exist only where source rocks are thought to be generating oil, then kerogen conversion is a likely over-pressure mechanism. However, if over-pressures are found in low-permeability strata regardless of source rock proximity, then sedimentary compaction is probably a more dominant mechanism.

Insulation vacuum and beam vacuum overpressure release

CERN Document Server

Parma, V

2009-01-01

There is evidence that the incident of 19th September caused a high pressure build-up inside the cryostat insulation vacuum which the existing overpressure devices could not contain. As a result, high longitudinal forces acting on the insulation vacuum barriers developed and broke the floor and the floor fixations of the SSS with vacuum barriers. The consequent large longitudinal displacements of the SSS damaged chains of adjacent dipole cryo-magnets. Estimates of the helium mass flow and the pressure build- up experienced in the incident are presented together with the pressure build-up for an even more hazardous event, the Maximum Credible Incident (MCI). The strategy of limiting the maximum pressure by the installation of addition pressure relieve devices is presented and discussed. Both beam vacuum lines were ruptured during the incident in sector 3-4 giving rise to both mechanical damage and pollution of the system. The sequence, causes and effects of this damage will be briefly reviewed. We will then an...

Characterization of the Scale Model Acoustic Test Overpressure Environment using Computational Fluid Dynamics

Science.gov (United States)

Nielsen, Tanner; West, Jeff

2015-01-01

The Scale Model Acoustic Test (SMAT) is a 5% scale test of the Space Launch System (SLS), which is currently being designed at Marshall Space Flight Center (MSFC). The purpose of this test is to characterize and understand a variety of acoustic phenomena that occur during the early portions of lift off, one being the overpressure environment that develops shortly after booster ignition. The pressure waves that propagate from the mobile launcher (ML) exhaust hole are defined as the ignition overpressure (IOP), while the portion of the pressure waves that exit the duct or trench are the duct overpressure (DOP). Distinguishing the IOP and DOP in scale model test data has been difficult in past experiences and in early SMAT results, due to the effects of scaling the geometry. The speed of sound of the air and combustion gas constituents is not scaled, and therefore the SMAT pressure waves propagate at approximately the same speed as occurs in full scale. However, the SMAT geometry is twenty times smaller, allowing the pressure waves to move down the exhaust hole, through the trench and duct, and impact the vehicle model much faster than occurs at full scale. The DOP waves impact portions of the vehicle at the same time as the IOP waves, making it difficult to distinguish the different waves and fully understand the data. To better understand the SMAT data, a computational fluid dynamics (CFD) analysis was performed with a fictitious geometry that isolates the IOP and DOP. The upper and lower portions of the domain were segregated to accomplish the isolation in such a way that the flow physics were not significantly altered. The Loci/CHEM CFD software program was used to perform this analysis.

Overpressurization performance of containment structures

International Nuclear Information System (INIS)

Barr, P.; Bleackley, M.; Harrop, L.P.; Hargreaves, J.; Jowett, J.; Phillips, D.W.

1987-01-01

The containment building of a PWR is the outermost engineered barrier between the reactor and the environment. The most important element of such a containment system is the pressure boundary structure and its associated seals and penetrations. This containment structure is designed deterministically to withstand a number of loads and load combinations of which the dominant one is generally the internal pressure due to the double-ended guillotine break in one of the primary circuit loops. Typically, the design basis large LOCA produces a peak pressure increase in the region of 0.3 MPa in some 10 seconds and with a duration of up to a few tens of seconds. The assessment of overpressure performance of the containment structure is a key component of the PWR safety case, and is usually carried out by estimating a static factor of safety to some failure limit state. These estimates can be made using simple force-balance calculations or complicated finite element calculations, and both approaches have merit. In this paper we examine these approaches and discuss their value in estimating failure pressures and failure modes for a variety of internal pressurization transients. This discussion covers both general design and risk considerations and is illustrated by numerical examples taken from previous and on-going analysis

CFD Assessment of Forward Booster Separation Motor Ignition Overpressure on ET XT 718 Ice/Frost Ramp

Science.gov (United States)

Tejnil, Edward; Rogers, Stuart E.

2012-01-01

Computational fluid dynamics assessment of the forward booster separation motor ignition over-pressure was performed on the space shuttle external tank X(sub T) 718 ice/frost ramp using the flow solver OVERFLOW. The main objective of this study was the investigation of the over-pressure during solid rocket booster separation and its affect on the local pressure and air-load environments. Delta pressure and plume impingement were investigated as a possible contributing factor to the cause of the debris loss on shuttle missions STS-125 and STS-127. A simplified computational model of the Space Shuttle Launch Vehicle was developed consisting of just the external tank and the solid rocket boosters with separation motor nozzles and plumes. The simplified model was validated by comparison to full fidelity computational model of the Space Shuttle without the separation motors. Quasi steady-state plume solutions were used to calibrate the thrust of the separation motors. Time-accurate simulations of the firing of the booster-separation motors were performed. Parametric studies of the time-step size and the number of sub-iterations were used to find the best converged solution. The computed solutions were compared to previous OVERFLOW steady-state runs of the separation motors with reaction control system jets and to ground test data. The results indicated that delta pressure from the overpressure was small and within design limits, and thus was unlikely to have contributed to the foam losses.

Passive cooling system for nuclear reactor containment structure

Science.gov (United States)

Gou, Perng-Fei; Wade, Gentry E.

1989-01-01

A passive cooling system for the contaminant structure of a nuclear reactor plant providing protection against overpressure within the containment attributable to inadvertent leakage or rupture of the system components. The cooling system utilizes natural convection for transferring heat imbalances and enables the discharge of irradiation free thermal energy to the atmosphere for heat disposal from the system.

Acoustic investigation of the aperture dynamics of an elastic membrane closing an overpressurized cylindrical cavity

Science.gov (United States)

Sánchez, Claudia; Vidal, Valérie; Melo, Francisco

2015-08-01

We report an experimental study of the acoustic signal produced by the rupture of an elastic membrane that initially closes a cylindrical overpressurized cavity. This configuration has been recently used as an experimental model system for the investigation of the acoustic emission from the bursting of elongated gas bubbles rising in a conduit. Here, we investigate the effect of the membrane rupture dynamics on the acoustic signal produced by the pressure release by changing the initial tension of the membrane. The initial overpressure in the cavity is fixed at a value such that the system remains in the linear acoustic regime. For large initial membrane deformation, the rupture time τ rup is small compared to the wave propagation time in the cavity and the pressure wave inside the conduit can be fully captured by the linear theory. For low membrane tension, a hole is pierced in the membrane but its rupture does not occur. For intermediate deformation, finally, the rupture progresses in two steps: first the membrane opens slowly; then, after reaching a critical size, the rupture accelerates. A transversal wave is excited along the membrane surface. The characteristic signature of each opening dynamics on the acoustic emission is described.

Natural circulating passive cooling system for nuclear reactor containment structure

Science.gov (United States)

Gou, Perng-Fei; Wade, Gentry E.

1990-01-01

A passive cooling system for the contaminant structure of a nuclear reactor plant providing protection against overpressure within the containment attributable to inadvertent leakage or rupture of the system components. The cooling system utilizes natural convection for transferring heat imbalances and enables the discharge of irradiation free thermal energy to the atmosphere for heat disposal from the system.

Comparison of under-pressure and over-pressure pulse tests conducted in low-permeability basalt horizons at the Hanford Site, Washington State

International Nuclear Information System (INIS)

Thorne, P.D.; Spane, F.A. Jr.

1984-10-01

Over-pressure pulse tests (pressurized slug tests have been widely used by others for hydraulic characterization of low-permeability ( -8 m/sec) rock formations. Recent field studies of low-permeability basalt horizons at the Hanford Site, Washington, indicate that the under-pressure pulse technique is also a viable test method for hydraulic characterization studies. For over-pressure pulse tests, fluid within the test system is rapidly pressurized and the associated pressure decay is monitored as compressed fluid within the test system expands and flows into the test formation. Under-pressure pulse tests are conducted in a similar manner by abruptly decreasing the pressure of fluid within the test system, and monitoring the associated increase in pressure as fluid flows from the formation into the test system. Both pulse test methods have been used in conjunction with other types of tests to determine the hydraulic properties of selected low-permeability basalt horizons at Hanford test sites. Results from both pulse test methods generally provide comparable estimates of hydraulic properties and are in good agreement with those from other tests

BLEVE overpressure: multi-scale comparison of blast wave modeling

International Nuclear Information System (INIS)

Laboureur, D.; Buchlin, J.M.; Rambaud, P.; Heymes, F.; Lapebie, E.

2014-01-01

BLEVE overpressure modeling has been already widely studied but only few validations including the scale effect have been made. After a short overview of the main models available in literature, a comparison is done with different scales of measurements, taken from previous studies or coming from experiments performed in the frame of this research project. A discussion on the best model to use in different cases is finally proposed. (authors)

Study on the Rationality and Validity of Probit Models of Domino Effect to Chemical Process Equipment caused by Overpressure

International Nuclear Information System (INIS)

Sun, Dongliang; Huang, Guangtuan; Jiang, Juncheng; Zhang, Mingguang; Wang, Zhirong

2013-01-01

Overpressure is one important cause of domino effect in accidents of chemical process equipments. Some models considering propagation probability and threshold values of the domino effect caused by overpressure have been proposed in previous study. In order to prove the rationality and validity of the models reported in the reference, two boundary values of three damage degrees reported were considered as random variables respectively in the interval [0, 100%]. Based on the overpressure data for damage to the equipment and the damage state, and the calculation method reported in the references, the mean square errors of the four categories of damage probability models of overpressure were calculated with random boundary values, and then a relationship of mean square error vs. the two boundary value was obtained, the minimum of mean square error was obtained, compared with the result of the present work, mean square error decreases by about 3%. Therefore, the error was in the acceptable range of engineering applications, the models reported can be considered reasonable and valid.

Study on the Rationality and Validity of Probit Models of Domino Effect to Chemical Process Equipment caused by Overpressure

Science.gov (United States)

Sun, Dongliang; Huang, Guangtuan; Jiang, Juncheng; Zhang, Mingguang; Wang, Zhirong

2013-04-01

Overpressure is one important cause of domino effect in accidents of chemical process equipments. Some models considering propagation probability and threshold values of the domino effect caused by overpressure have been proposed in previous study. In order to prove the rationality and validity of the models reported in the reference, two boundary values of three damage degrees reported were considered as random variables respectively in the interval [0, 100%]. Based on the overpressure data for damage to the equipment and the damage state, and the calculation method reported in the references, the mean square errors of the four categories of damage probability models of overpressure were calculated with random boundary values, and then a relationship of mean square error vs. the two boundary value was obtained, the minimum of mean square error was obtained, compared with the result of the present work, mean square error decreases by about 3%. Therefore, the error was in the acceptable range of engineering applications, the models reported can be considered reasonable and valid.

Liquefied extinguishing agent discharge to an overpressure-sensitive enclosed volume

Directory of Open Access Journals (Sweden)

Hurda Lukáš

2018-01-01

Full Text Available The throttling of liquefied substances from high pressure vessels to an enclosed volume starting at atmospheric pressure is described in order to determine thermodynamic state of the extinguished room gaseous contents. Time dependent, 0D mathematical model is implemented describing the state inside the agent container, the isenthalpic throttling in the distribution system, agent vaporization and mixing with air. The agent is modelled as real gas. Other influences on the process including the heat transfer from selected solid parts inside the room and the gas mixture leakage out of the room are taken into account. Main outcome is an MS Excel tool for integrated fire extinguishers design optimization. The optimization balances the two contradictory requirements: Agent volumetric concentration to sustain the fire extinguishing capabilities and tolerable room overpressure. Agent fill weight and discharge time are being adjusted. The discharge time is controlled by the distribution piping and spray nozzles design. System operation is checked concerning various initial and boundary conditions.

Spark gap overpressures in the transfer capacitor device

International Nuclear Information System (INIS)

Burkhardt, L.C.; Dike, R.S.

1977-01-01

A designer of spark gaps is often faced with two gas pressure problems, one static and one dynamic. The former is easy to obtain data on which to base intelligent design specifications; about the latter, less is known. It is the total internal pressure environment we have attempted to measure, in an un-time-resolved way, in order to give the designer some rationale in designing gaps of this category. We measure overpressures of approximately 400 PSI in a 13 cubic inch gap passing currents of approximately 200 kA

The development of shock wave overpressure driven by channel expansion of high current impulse discharge arc

Science.gov (United States)

Xiong, Jia-ming; Li, Lee; Dai, Hong-yu; Wu, Hai-bo; Peng, Ming-yang; Lin, Fu-chang

2018-03-01

During the formation of a high current impulse discharge arc, objects near the discharge arc will be strongly impacted. In this paper, a high power, high current gas switch is used as the site of the impulse discharge arc. The explosion wave theory and the arc channel energy balance equation are introduced to analyze the development of the shock wave overpressure driven by the high current impulse discharge arc, and the demarcation point of the arc channel is given, from which the energy of the arc channel is no longer converted into shock waves. Through the analysis and calculation, it is found that the magnitude of the shock wave overpressure caused by impulse discharge arc expansion is closely related to the arc current rising rate. The arc shock wave overpressure will undergo a slow decay process and then decay rapidly. The study of this paper will perform the function of deepening the understanding of the physical nature of the impulse arc discharge, which can be used to explain the damage effect of the high current impulse discharge arc.

Overpressures: Causal Mechanisms, Conventional and Hydromechanical Approaches Surpressions : origine, approches conventionnelle et hydromécanique

Directory of Open Access Journals (Sweden)

Grauls D.

2006-12-01

Full Text Available Abnormal fluid pressure regimes are commonly encountered at depth in most sedimentary basins. Relationships between effective vertical stress and porosity have been applied, since 1970 to the Gulf Coast area, to assess the magnitude of overpressures. Positive results have been obtained from seismic and basin-modeling techniques in sand-shale, vertical-stress-dominated tertiary basins, whenever compaction disequilibrium conditions apply. However, overpressures resulting from other and/or additional causes (tectonic stress, hydrocarbon generation, thermal stress, fault-related transfer, hydrofracturing. . . cannot be quantitatively assessed using this approach. A hydromechanical approach is then proposed in addition to conventional methods. At any depth, the upper bound fluid pressure is controlled by in situ conditions related to hydrofracturing or fault reactivation. Fluid-driven fracturing implies an episodically open system, under a close to zerominimum effective stress regime. Sound knowledge of present-day tectonic stress regimes allows a direct estimation of minimum stress evolution. A quantitative fluid pressure assessment at depth is therefore possible, as in undrained or/and compartmented geological systems, pressure regimes, whatever their origin, tend to rapidly reach a value close to the minimum principal stress. Therefore, overpressure assessment will be improved, as this methodology can be applied to various geological settings and situations where present-day overpressures originated from other causal mechanisms, very often combined. However, pressure trends in transition zones are more difficult to assess correctly. Additional research on cap rocks and fault seals is therefore required to improve their predictability. In addition to overpressure assessment, the minimum principal stress concept allows a better understanding of petroleum system, as fault-related hydrocarbon dynamic transfers, hydrofractured domains and cap

A new method for calculating gas content of coal reservoirs with consideration of a micro-pore overpressure environment

Directory of Open Access Journals (Sweden)

Jinxing Song

2017-05-01

Full Text Available When the gas content of a coal reservoir is calculated, the reservoir pressure measured by well logging and well testing is generally used for inversion calculation instead of gas pressure. However, the calculation result is not accurate because the reservoir pressure is not equal to the gas pressure in overpressure environments. In this paper, coal samples of different ranks in Shanxi and Henan are collected for testing the capillary pressure of coal pores. Based on the formation process of CBM reservoirs and the hydrocarbon generation and expulsion history of coal beds, the forming mechanisms of micro-pore overpressure environments in coal reservoirs were analyzed. Accordingly, a new method for calculating the gas content of coal reservoirs with consideration of a micro-pore overpressure environment was developed. And it was used to calculate the gas content of No. 1 coal bed of the 2nd member of Lower Permian Shanxi Fm in the Zhongmacun Coal Mine in Jiaozuo, Henan. It is indicated that during the formation and evolution of coals, some solid organic matters were converted into gas and water, and gas–water contact is surely formed in pores. In the end, capillary pressure is generated, so the gas pressure in micro-pores is much higher than the hydrostatic column pressure, which results in a micro-pore overpressure environment. Under such an environment, gas pressure is higher than reservoir pressure, so the gas content of coal reservoirs calculated previously based on the conventional reservoir pressure evaluation are usually underestimated. It is also found that the micro-pore overpressure environment exerts a dominating effect on the CBM content calculation of 3–100 nm pores, especially that of 3–10 nm pores, but a little effect on that of pores >100 nm. In conclusion, this new method clarifies the pressure environment of CBM gas reservoirs, thereby ensuring the calculation accuracy of gas content of coal reservoirs.

A study on the overpressure estimation of BLEVE

Energy Technology Data Exchange (ETDEWEB)

Kim, In Tae [Korean Fire Protection Association (Korea); Kim, In Won; Song, Hee Oeul [Department of Chemical Engineering, Konkuk University (Korea)

2000-03-01

Explosion quantities and flashing mass resulting from the variation of temperature are calculated by a computer program, BLEVE ESTIMATOR, to carry out the risk assessment of BLEVE. The damages caused by the BLEVE are estimated under the explosion of the simulation condition similar to the Puchun LP gas station accident, and the results are compared with the commercial program SAFER of Dupont Co. Explosion quantities and flashing mass increase exponentially with the increase of explosion temperature. These values for propane are relatively higher than those for n-butane. In conditions of higher vessel temperature, vessel pressure, and liquid ratio of containment, higher overpressures are calculated. 10 refs., 12 figs., 2 tabs.

Prevention of overpressurization of lithium-thionyl chloride battery cells

Energy Technology Data Exchange (ETDEWEB)

Ramsay, G. R.; Salmon, D. J.

1984-12-25

A method of preventing overpressurization of a lithium-thionyl chloride battery cell by formation of excessive SO/sub 2/ during high rate discharge. The method comprises the step of providing PCl/sub 5/ in the cathode. Alternatively, the PCl/sub 5/ may be provided in the electrolyte or in both the cathode and electrolyte as desired. The PCl/sub 5/ may be incorporated in the cathode by introduction thereof into the porous carbon structure of a preformed carbon element. Alternatively, the PCl/sub 5/ may be dry mixed with the carbon and the mixture formed into the desired cathode element.

Current state of knowledge on the behavior of steel liners in concrete containments subjected to overpressurization loads

International Nuclear Information System (INIS)

Riesemann, W.A. von; Parks, M.B.

1995-01-01

In the US, concrete containment buildings for commercial nuclear power plants have steel liners that act as the internal pressure boundary. The liner abuts the concrete, acting as the interior concrete form. The liner is attached to the concrete by either studs or by a continuous structural shape (such as a T-section or channel) that is either continuously or intermittently welded to the liner. Studs are commonly used in reinforced concrete containments, while prestressed containments utilize a structural element as the anchorage. The practice in some countries follows the US practice, while in other countries the containment does not have a steel liner. In this latter case, there is a true double containment, and the annular region between the two containments is vented.This paper will review the practice of design of the liner system prior to the consideration of severe accident loads (overpressurization loads beyond the design conditions).An overpressurization test of a 1:6 scale reinforced concrete containment at Sandia National Laboratories resulted in a failure mechanism in the liner that was not fully anticipated. Post-test analyses and experiments have been conducted to understand the failure better. This work and the activities that followed the test are reviewed. Areas in which additional research should be conducted are given. (orig.)

The overpressure protection for the chemical reactors: the batch-size approach

International Nuclear Information System (INIS)

Dellavedova, M.; Gigante, L.; Lunghi, A.; Pasturenzi, C.; Cardillo, P.; Gerosa, N.P.; Rota, R.

2008-01-01

Small and medium enterprises (SMEs) main feature is to run batch and semi-batch processes, working on job orders. They generally have multi propose reactors with an emergency relief system (ERS) already installed. These are normally sized when the reactor is designed, assuming as worst incidental scenario a single phase vapour flow generated by a fire developed outside the apparatus. These assumptions can lead to a big underestimation of the vent area if the actual flow is two-phase and besides generated by a runaway reaction. ERS sizing is particularly hazardous and complex for small mills, as for example fine chemicals and pharmaceutical companies. These factories have usually narrow financial and personal resources, moreover they often use fast processes turnovers. In many cases a complete safety study or the replacement of the ERS is not possible and it can lead to not sustainable costs. The batch-size approach is focused on discontinuous process conditions: aim of this approach is to find the reactor fill level that can lead a vapour single phase flow whether an incident occurs, this condition is considered safe that the ERS installed on the reactor can protect the plant from explosions [it

Machine protection systems

CERN Document Server

Macpherson, A L

2010-01-01

A summary of the Machine Protection System of the LHC is given, with particular attention given to the outstanding issues to be addressed, rather than the successes of the machine protection system from the 2009 run. In particular, the issues of Safe Machine Parameter system, collimation and beam cleaning, the beam dump system and abort gap cleaning, injection and dump protection, and the overall machine protection program for the upcoming run are summarised.

Behaviour of concrete containment under over-pressure conditions

International Nuclear Information System (INIS)

Atchison, R.J.; Asmis, G.J.K.; Campbell, F.R.

1979-01-01

The Atomic Energy Control Board of Canada initiated June, 1975, a major study of the behaviour of concrete containment under over-pressure conditions. Although extensive theoretical and experimental work has been carried out for thick-walled Prestressed Concrete Reactor Vessels (PCRV's), there is a want of information on the non-linear response of thin-walled structures typical of the CANDU, 600 MW(e) cylindrical/spherical, post-tensioned containment shells. The purpose of this paper is to provide an overview of the total program, to present the reasons behind the research contract, and the specification and implementation of the work. The results of the theoretical and experimental work and their implications with respect to Canadian Concrete Containment practice are discussed. This study is unique, and, as far as is known, has no world-wide precedence. (orig.)

Blast overpressure after tire explosion: a fatal case.

Science.gov (United States)

Pomara, Cristoforo; D'Errico, Stefano; Riezzo, Irene; Perilli, Gabriela; Volpe, Umberto; Fineschi, Vittorio

2013-12-01

Fatal blast injuries are generally reported in literature as a consequence of the detonation of explosives in war settings. The pattern of lesion depends on the position of the victim in relation to the explosion, on whether the blast tracks through air or water, and whether it happens in the open air or within an enclosed space and the distance from the explosion. Tire explosion-related injuries are rarely reported in literature. This study presents a fatal case of blast overpressure due to the accidental explosion of a truck tire occurring in a tire repair shop. A multidisciplinary approach to the fatality involving forensic pathologists and engineers revealed that the accidental explosion, which caused a series of primary and tertiary blast wave injuries, was due to tire deterioration.

Prediction of sonic boom from experimental near-field overpressure data. Volume 2: Data base construction

Science.gov (United States)

Glatt, C. R.; Reiners, S. J.; Hague, D. S.

1975-01-01

A computerized method for storing, updating and augmenting experimentally determined overpressure signatures has been developed. A data base of pressure signatures for a shuttle type vehicle has been stored. The data base has been used for the prediction of sonic boom with the program described in Volume I.

Protective containment behaviour under exceeded design loads

International Nuclear Information System (INIS)

Holub, I.; Stepan, J.; Maly, J.; Schererova, K.

2003-01-01

The contribution describes the calculation results of the behaviour of containment structure if loaded in excess of its design load. The Temelin NPP comprises two WWER 1000 blocks and containment consists of a pre-stressed reinforced concrete structure with a system of unbonded cables. The objective of the calculations was to determine the level of load caused by the internal pressure and temperature at which the containment protective function would fail. In the first step, the maximum overpressure was determined, which may be transferred by the containment structure. In further steps analyses were made of various combinations of simultaneous pressure and temperature loads. The contribution presents relevant calculation results, including the evaluation of containment structure behaviour including liner under loads that exceed its design parameters. (author)

Armored garment for protecting

Science.gov (United States)

Purvis, James W [Albuquerque, NM; Jones, II, Jack F.; Whinery, Larry D [Albuquerque, NM; Brazfield, Richard [Albuquerque, NM; Lawrie, Catherine [Tijeras, NM; Lawrie, David [Tijeras, NM; Preece, Dale S [Watkins, CO

2009-08-11

A lightweight, armored protective garment for protecting an arm or leg from blast superheated gases, blast overpressure shock, shrapnel, and spall from a explosive device, such as a Rocket Propelled Grenade (RPG) or a roadside Improvised Explosive Device (IED). The garment has a ballistic sleeve made of a ballistic fabric, such as an aramid fiber (e.g., KEVLAR.RTM.) cloth, that prevents thermal burns from the blast superheated gases, while providing some protection from fragments. Additionally, the garment has two or more rigid armor inserts that cover the upper and lower arm and protect against high-velocity projectiles, shrapnel and spall. The rigid inserts can be made of multiple plies of a carbon/epoxy composite laminate. The combination of 6 layers of KEVLAR.RTM. fabric and 28 plies of carbon/epoxy laminate inserts (with the inserts being sandwiched in-between the KEVLAR.RTM. layers), can meet the level IIIA fragmentation minimum V.sub.50 requirements for the US Interceptor Outer Tactical Vest.

Shelter to provide protection from nuclear fallout and/or war

International Nuclear Information System (INIS)

Northgreaves, K.R.

1982-01-01

A shelter to provide protection from nuclear fall-out and/or war gas is described. It has a flexible inflatable envelope containing its own life support system and can be stored in a collapsed condition until required. A sealable access is provided and an over-pressure within the envelope can be maintained by means of a hand-operated air compressor which draws in external air through an air inlet and through a dust and war gas filter. The shelter can be divided into two chambers of which one can form an air-lock chamber between the access opening and the other chamber. Sanitary and decontamination equipment can be provided in the air-lock chamber. (author)

Simulation of overpressure events with a Laguna Verde model for the RELAP code to conditions of extended power up rate

International Nuclear Information System (INIS)

Rodriguez H, A.; Araiza M, E.; Fuentes M, L.; Ortiz V, J.

2012-10-01

In this work the main results of the simulation of overpressure events are presented using a model of the nuclear power plant of Laguna Verde developed for the RELAP/SCDAPSIM code. As starting point we have the conformation of a Laguna Verde model that represents a stationary state to similar conditions to the operation of the power station with Extended Power Up rate (EPU). The transitory of simulated pressure are compared with those documented in the Final Safety Analysis Report of Laguna Verde (FSAR). The results of the turbine shot transitory with and without by-pass of the main turbine are showed, and the event of closes of all the valves of main vapor isolation. A preliminary simulation was made and with base in the results some adjustments were made for the operation with EPU, taking into account the Operation Technical Specifications of the power station. The results of the final simulations were compared and analyzed with the content in the FSAR. The response of the power station to the transitory, reflected in the model for RELAP, was satisfactory. Finally, comments about the improvement of the model are included, for example, the response time of the protection and mitigation systems of the power station. (Author)

FPGA-Based Plant Protection System

Energy Technology Data Exchange (ETDEWEB)

Lee, Yoon Hee; Ha, Jae Hong; Kim, Hang Bae [KEPCO E and C, Daejeon (Korea, Republic of)

2011-08-15

This paper relates to a plant protection system which detects non-permissible conditions and determines initiation of protective actions for nuclear power plants (NPPs). Conventional plant protection systems were designed based on analog technologies. It is well known that existing protection systems for NPPs contain many components which are becoming obsolete at an increasing rate. Nowadays maintenance and repair for analog-based plant protection systems may be difficult as analog parts become obsolete or difficult to obtain. Accordingly, as an alternative to the analog technology, the digitalisation of the plant protection system was required. Recently digital plant protection systems which include programmable logic controllers (PLCs) and/or computers have been introduced. However PLC or computer-based plant protection systems use an operating system and application software, and so they may result in a common mode failure when a problem occurs in the operating system or application software. Field Programmable Gate Arrays (FPGAs) are highlighted as an alternative to conventional protection or control systems. The paper presents the design of a four-channel plant protection system whose protection functions are implemented in FPGAs without any central processing unit or operating system.

FPGA-Based Plant Protection System

International Nuclear Information System (INIS)

Lee, Yoon Hee; Ha, Jae Hong; Kim, Hang Bae

2011-01-01

This paper relates to a plant protection system which detects non-permissible conditions and determines initiation of protective actions for nuclear power plants (NPPs). Conventional plant protection systems were designed based on analog technologies. It is well known that existing protection systems for NPPs contain many components which are becoming obsolete at an increasing rate. Nowadays maintenance and repair for analog-based plant protection systems may be difficult as analog parts become obsolete or difficult to obtain. Accordingly, as an alternative to the analog technology, the digitalisation of the plant protection system was required. Recently digital plant protection systems which include programmable logic controllers (PLCs) and/or computers have been introduced. However PLC or computer-based plant protection systems use an operating system and application software, and so they may result in a common mode failure when a problem occurs in the operating system or application software. Field Programmable Gate Arrays (FPGAs) are highlighted as an alternative to conventional protection or control systems. The paper presents the design of a four-channel plant protection system whose protection functions are implemented in FPGAs without any central processing unit or operating system

Depth protection system

International Nuclear Information System (INIS)

Arita, Setsuo; Izumi, Shigeru; Suzuki, Satoru; Noguchi, Atomi.

1988-01-01

Purpose: To previously set a nuclear reactor toward safety side by the reactor scram if an emergency core cooling system is failed to operate. Constitution If abnormality occurs in an emergency core cooling system or an aqueous boric acid injection system, a reactor protection system is operated and, if the reactor protection system shows an abnormal state, a control rod withdrawal inhibition system is operated as a fundamental way. For instance, when the driving power source voltage for the emergency core cooling system is detected and, if it is lower than a predetermined value, the reactor protection system is operated. Alternatively, if the voltage goes lower than the predetermined value, the control rod withdrawal is inhibited. In addition, stopping for the feedwater system is inhibited. Further, integrity of the driving means for the emergency core cooling system is positively checked and the protection function is operated depending on the result of check. Since the nuclear reactor can be set toward the safety side even if the voltage for the driving power source of the aqueous boric acid injection system is lower than a predetermined value, the reactor safety can further be improved. (Horiuchi, T.)

An Evaluation of the Compressive Properties of Helmet Pads Pre- and Post-Shock Wave Overpressure Exposure

Science.gov (United States)

2015-08-14

Regulation, Chapter IX. For Unclassified/Limited Distribution Documents: Destroy by any method that prevents disclosure of contents or reconstruction of...OVERPRESSURE WOUNDS AND INJURIES IMPACT STATIC TESTS PADS(CUSHIONS) TEST AND EVALUATION TRAUMA ...simplified version of the Facial and Ocular Countermeasure for Safety (FOCUS) headform. The FOCUS headform is commercially available through Humanetics

System level ESD protection

CERN Document Server

Vashchenko, Vladislav

2014-01-01

This book addresses key aspects of analog integrated circuits and systems design related to system level electrostatic discharge (ESD) protection.  It is an invaluable reference for anyone developing systems-on-chip (SoC) and systems-on-package (SoP), integrated with system-level ESD protection. The book focuses on both the design of semiconductor integrated circuit (IC) components with embedded, on-chip system level protection and IC-system co-design. The readers will be enabled to bring the system level ESD protection solutions to the level of integrated circuits, thereby reducing or completely eliminating the need for additional, discrete components on the printed circuit board (PCB) and meeting system-level ESD requirements. The authors take a systematic approach, based on IC-system ESD protection co-design. A detailed description of the available IC-level ESD testing methods is provided, together with a discussion of the correlation between IC-level and system-level ESD testing methods. The IC-level ESD...

Method for the protection of the cladding tubes of fuel rods

International Nuclear Information System (INIS)

Steinberg, E.

1978-01-01

To present stress crack corrosion and to protect the cladding tubes of the fuel rods made of a circonium alloy from attack by iodine, the inward surfaces are provided with protective coatings. Therefore the casting tubes already filled with fuel element pellets are put under over-pressure at a temperature range between 300 and 500 0 C, until almost yield-point is reached. A small amount of H 2 O or H 2 O 2 , filled in, reacts with the cladding tube material to form the Zr-O 2 protective coating. Afterwards comes a pressure relief, and the cladding tube reaches its original dimensions. (DG) [de

Groundwater Chemistry and Overpressure Evidences in Cerro Prieto Geothermal Field

Directory of Open Access Journals (Sweden)

Ivan Morales-Arredondo

2017-01-01

Full Text Available In order to understand the geological and hydrogeological processes influencing the hydrogeochemical behavior of the Cerro Prieto Geothermal Field (CP aquifer, Mexico, a characterization of the water samples collected from geothermal wells was carried out. Different hydrochemical diagrams were used to evaluate brine evolution of the aquifer. To determine pressure conditions at depth, a calculation was performed using hydrostatic and lithostatic properties from CP, considering geological characteristics of the study area, and theoretical information about some basin environments. Groundwater shows hydrogeochemical and geological evidences of the diagenetic evolution that indicate overpressure conditions. Some physical, chemical, textural, and mineralogical properties reported in the lithological column from CP are explained understanding the evolutionary process of the sedimentary material that composes the aquifer.

Power system protection

International Nuclear Information System (INIS)

Venkata, S.S.; Damborg, M.J.; Jampala, A.K.

1991-01-01

Power systems of the 21st century will be more modern, and complex, utilizing the latest available technologies. At the same time, generating plants will have to operate with minimal spinning margins and energy transportation has to take place at critical levels due to environmental and economical constraints. These factors dictate that the power systems be protected with optimum sensitivity, selectivity and time of operation to assure maximum reliability, and security at minimal cost. With an increasing role played by digital computers in every aspect of protection, it is important to take a critical and fresh look at the art and science of relaying and protection. The main objective of this paper is to review the past, present and future of power system protection from a software point of view

Bioeffects on an In Vitro Model by Small-Scale Explosives and Shock Wave Overpressure Impacts

Science.gov (United States)

2017-11-01

Many TBIs are associated with blast from improvised explosive devices.2–4 Explosions are physical, chemical , or nuclear reactions involving a rapid...ARL-TR-8210 ● NOV 2017 US Army Research Laboratory Bioeffects on an In Vitro Model by Small-Scale Explosives and Shock Wave...Research Laboratory Bioeffects on an In Vitro Model by Small-Scale Explosives and Shock Wave Overpressure Impacts by Nicole E Zander, Thuvan

The role of salt tectonics and overburden in the generation of overpressure in the Dutch North Sea area

NARCIS (Netherlands)

Nelskamp, S.; Verweij, J.M.; Witmans, N.

2012-01-01

In this paper we study the effects of timing of salt movement and mechanical compaction on the generation of overpressures in Mesozoic rocks. To that end we apply 2D basin modelling on two N-S trending cross sections in the Dutch Central Graben and Terschelling Basin, respectively. Several

Buffer moisture protection system

International Nuclear Information System (INIS)

Ritola, J.; Peura, J.

2013-11-01

With the present knowledge, bentonite blocks have to be protected from the air relative humidity and from any moisture leakages in the environment that might cause swelling of the bentonite blocks during the 'open' installation phase before backfilling. The purpose of this work was to design the structural reference solution both for the bottom of the deposition hole and for the buffer moisture protection and dewatering system with their integrated equipment needed in the deposition hole. This report describes the Posiva's reference solution for the buffer moisture protection system and the bottom plate on basis of the demands and functional requirements set by long-term safety. The reference solution with structural details has been developed in research work made 2010-2011. The structural solution of the moisture protection system has not yet been tested in practice. On the bottom of the deposition hole a copper plate which protects the lowest bentonite block from the gathered water is installed straight to machined and even rock surface. The moisture protection sheet made of EPDM rubber is attached to the copper plate with an inflatable seal. The upper part of the moisture protection sheet is fixed to the collar structures of the lid which protects the deposition hole in the disposal tunnel. The main function of the moisture protection sheet is to protect bentonite blocks from the leaking water and from the influence of the air humidity at their installation stage. The leaking water is controlled by the dewatering and alarm system which has been integrated into the moisture protection liner. (orig.)

FIRE PROTECTION SYSTEMS AND TECHNOLOGIES

Directory of Open Access Journals (Sweden)

Aristov Denis Ivanovich

2016-03-01

Full Text Available The All-Russian Congress “Fire Stop Moscow” was de-voted to the analysis of the four segments of the industry of fire protection systems and technologies: the design of fire protec-tion systems, the latest developments and technologies of active and passive fire protection of buildings, the state and the devel-opment of the legal framework, the practice of fire protection of buildings and structures. The forum brought together the repre-sentatives of the industry of fire protection systems, scientists, leading experts, specialists in fire protection and representatives of construction companies from different regions of Russia. In parallel with the Congress Industrial Exhibition of fire protection systems, materials and technology was held, where manufacturers presented their products. The urgency of the “Fire Stop Moscow” Congress in 2015 organized by the Congress Bureau ODF Events lies primarily in the fact that it considered the full range of issues related to the fire protection of building and construction projects; studied the state of the regulatory framework for fire safety and efficiency of public services, research centers, private companies and busi-nesses in the area of fire safety. The main practical significance of the event which was widely covered in the media space, was the opportunity to share the views and information between management, science, and practice of business on implementing fire protection systems in the conditions of modern economic relations and market realities. : congress, fire protection, systems, technologies, fire protection systems, exhibition

Formation and destruction mechanism as well as major controlling factors of the Silurian shale gas overpressure in the Sichuan Basin, China

Directory of Open Access Journals (Sweden)

Shuangjian Li

2016-08-01

Full Text Available Taking the Well JY1 and Well PY1 in the Eastern Sichuan Basin as examples, the formation mechanism of shale gas overpressure was studied by using the cross plot of acoustic versus density logging data. During the processes of hydrocarbon generation and the uplifting, the pressure evolution of fluids in shale gas layers was reconstructed by fluid inclusions and PVTSIM software. The major factors controlling the evolution of shale gas overpressure were established according to the study of fracture, the timing of the uplifting, and episodes of tectonic deformation. Our results showed that the main mechanism of overpressure in the Silurian shale gas reservoirs in the Sichuan Basin was the fluid expansion, which was caused by hydrocarbon generation. Since the Yanshanian, the strata were uplifted and fluid pressure generally showed a decreasing trend. However, due to the low compression rebound ratio of shale gas reservoir rocks, poor connectivity of reservoir rocks, and low content of formation water and so on, such factors made fluid pressure decrease, but these would not be enough to make up the effects of strata erosion resulting in a further increase in fluid pressure in shale gas reservoirs during the whole uplifting processes. Since the Yanshanian, the Well PY1 zone had been reconstructed by at least three episodes of tectonic movement. The initial timing of the uplifting is 130 Ma. Compared to the former, the Well JY1 zone was firstly uplifted at 90 Ma, which was weakly reconstructed. As a result, low-angle fractures and few high resistance fractures developed in the Well JY1, while high-angle fractures and many high resistance fractures developed in the Well PY1. In totality, the factors controlling the overpressure preservation in shale gas reservoirs during the late periods include timing of late uplifting, superposition and reconstruction of stress fields, and development of high-angle fractures.

Influence of the geometry of protective barriers on the propagation of shock waves

Science.gov (United States)

Sochet, I.; Eveillard, S.; Vinçont, J. Y.; Piserchia, P. F.; Rocourt, X.

2017-03-01

The protection of industrial facilities, classified as hazardous, against accidental or intentional explosions represents a major challenge for the prevention of personal injury and property damage, which also involves social and economic issues. We consider here the use of physical barriers against the effects of these explosions, which include the pressure wave, the projection of fragments and the thermal flash. This approach can be recommended for the control of major industrial risks, but no specific instructions are available for its implementation. The influence of a protective barrier against a detonation-type explosion is studied in small-scale experiments. The effects of overpressure are examined over the entire path of the shock wave across the barrier and in the downstream zone to be protected. Two series of barrier structures are studied. The first series (A) of experiments investigates two types of barrier geometry with dimensions based on NATO recommendations. These recommendations stipulate that the barrier should be 2 m higher than the charge height, the thickness at the crest should be more than 0.5 m, while its length should be equal to twice the protected structure length and the bank slope should be equivalent to the angle of repose of the soil. The second series (B) of experiments investigates the influence of geometrical parameters of the barrier (thickness at the crest and inclination angles of the front and rear faces) on its protective effects. This project leads to an advance in our understanding of the physical phenomena involved in the propagation of blast waves resulting from an external explosion, in the area around a protective physical barrier. The study focuses on the dimensioning of protective barriers against overpressure effects arising from detonation and shows the advantage of using a barrier with a vertical front or rear face.

Reactor protection system

International Nuclear Information System (INIS)

Fairbrother, D.B.; Lesniak, L.M.; Orgera, E.G.

1977-10-01

The report describes the reactor protection system (RPS-II) designed for use on Babcock and Wilcox 145-, later 177-, and 205-fuel assembly pressurized water reactors. In this system, relays in the trip logic have been replaced by solid state devices. A calculating module for the low DNBR, pump status, and offset trip functions has replaced the overpower trip (based on flow and imbalance), the power/RC pump trip, and the variable low-pressure trip. Included is a description of the changes from the present Oconee-type reactor protection system (RPS-I), a functional and hardware description of the calculating module, a description of the software programmed in the calculating module, and a discussion of the qualification program conducted to ensure that the degree of protection provided by RPS-II is not less than that provided by previously licensed systems supplied by B and W

Systems approach to tamper protection

International Nuclear Information System (INIS)

Myre, W.C.; Eaton, M.J.

1980-01-01

Tamper-protection is a fundamental requirement of effective containment and surveillance systems. Cost effective designs require that the tamper protection requirements be considered early in the design phase and at the system level. A discussion of tamper protection alternatives as well as an illustrative example system is presented

Physical protection system design and evaluation

International Nuclear Information System (INIS)

Williams, J.D.

1997-01-01

The design of an effective physical protection system includes the determination of physical protection system objectives, initial design of a physical protection system, design evaluation, and probably a redesign or refinement. To develop the objectives, the designer must begin by gathering information about facility operation and conditions, such as a comprehensive description of the facility, operating conditions, and the physical protection requirements. The designer then needs to define the threat. This involves considering factors about potential adversaries: class of adversary, adversary's capabilities, and range of adversary's tactics. Next, the designer should identify targets. Determination of whether or not the materials being protected are attractive targets is based mainly on the ease or difficulty of acquisition and desirability of the material. The designer now knows the objectives of the physical protection system, that is, open-quotes what to protect against whom.close quotes The next step is to design the system by determining how best to combine such elements as fences, vaults, sensors and assessment devices, entry control elements, procedures, communication devices, and protective forces personnel to meet the objectives of the system. Once a physical protection system is designed, it must be analyzed and evaluated to ensure it meets the physical protection objectives. Evaluation must allow for features working together to ensure protection rather than regarding each feature separately. Due to the complexity of the protection systems, an evaluation usually requires modeling techniques. If any vulnerabilities are found, the initial system must be redesigned to correct the vulnerabilities and a reevaluation conducted. This paper reviews the physical protection system design and methodology mentioned above. Examples of the steps required and a brief introduction to some of the technologies used in modem physical protections system are given

The use of HANDIDET reg-sign non-electric detonator assemblies to reduce blast-induced overpressure at AECL's Underground Research Laboratory

International Nuclear Information System (INIS)

Onagi, D.P.; Keith, S.G.; Kuzyk, G.W.

1996-01-01

A number of aspects of the Canadian concept for nuclear fuel waste disposal are being assessed by Atomic Energy of Canada Limited (AECL) in a series of experiments at its Underground Research Laboratory (URL) near Lac du Bonnet, Manitoba, Canada. One of the major objectives of the work being carried out at the URL is to develop and evaluate the methods and technology to ensure safe, permanent disposal of Canada's nuclear fuel waste. In 1994, AECL excavated access tunnels and a laboratory room for the Quarried Block Fracture Migration Experiment (QBFME) at the 240 Level of the URL. This facility will be used to study the transport of radionuclides in natural fractures in quarried blocks of granite under in-situ groundwater conditions. The experiment is being carried out under a cooperative agreement with the Japan Atomic Energy Research Institute. The excavation of the QBFME access tunnels and laboratory was carried out using controlled blasting techniques that minimized blast-induced overpressure which could have damaged or interrupted other ongoing experiments in the vicinity. The majority of the blasts used conventional long delay non-electric detonators but a number of blasts were carried out using HANDIDET 250/6000 non-electric long delay detonator assemblies and HTD reg-sign non-electric short delay trunkline detonator assemblies. The tunnel and laboratory excavation was monitored to determine the levels of blast-induced overpressure. This paper describes the blasting and monitoring results of the blasts using HANDIDET non-electric detonator assemblies and the effectiveness of these detonators in reducing blast-induced overpressure

SMART core protection system design

International Nuclear Information System (INIS)

Lee, J. K.; Park, H. Y.; Koo, I. S.; Park, H. S.; Kim, J. S.; Son, C. H.

2003-01-01

SMART COre Protection System(SCOPS) is designed with real-tims Digital Signal Processor(DSP) board and Network Interface Card(NIC) board. SCOPS has a Control Rod POSition (CRPOS) software module while Core Protection Calculator System(CPCS) consists of Core Protection Calculators(CPCs) and Control Element Assembly(CEA) Calculators(CEACs) in the commercial nuclear plant. It's not necessary to have a independent cabinets for SCOPS because SCOPS is physically very small. Then SCOPS is designed to share the cabinets with Plant Protection System(PPS) of SMART. Therefor it's very easy to maintain the system because CRPOS module is used instead of the computer with operating system

Evolution of the radiation protection system; L'evolution du systeme de protection radiologique

Energy Technology Data Exchange (ETDEWEB)

Clarke, R.H. [International Commission on Radiological Protection, Stockholm (Sweden); Schieber, C.; Cordoliani, Y.S. [Societe Francaise de Radioprotection, 92 - Fontenay aux Roses (France); Brechignac, F. [CEA Cadarache, Institut de Radioprotection et de Surete Nucleaire, Dept. de Protection de l' Environnement, 13 - Saint Paul Lez Durance (France)

2003-07-01

The evolution of the system of radiological protection: justification for new ICRP recommendations, thoughts of the SFRP work group about the evolution of the system of radiation protection proposed by the ICRP, protection of environment against ionizing radiations seen by the ICRP are the three parts of this chapter. (N.C.)

Influence of overpressure on formation velocity evaluation of Neogene strata from the eastern Bengal Basin, Bangladesh

Science.gov (United States)

Zahid, Khandaker M.; Uddin, Ashraf

2005-06-01

Interpretation of sonic log data of anticlinal structures from eastern Bangladesh reveals significant variations of acoustic velocity of subsurface strata. The amount of variation in velocity is 32% from Miocene to Pliocene stratigraphic units in Titas and Bakhrabad structure, whereas 21% in Rashidpur structure. Velocity fluctuations are influenced by the presence of gas-bearing horizons, with velocities of gas-producing strata 3-7% lower than laterally equivalent strata at similar depth. Average velocities of Miocene Boka Bil and Bhuban formations are, respectively, 2630 and 3480 m/s at Titas structure; 2820 and 3750 m/s at Bakhrabad; and 3430 and 3843 m/s at the Rashidpur structure. From the overall velocity-depth distribution for a common depth range of 915-3000 m, the Titas, Bakhrabad and Rashidpur structures show a gradual increase in velocity with depth. In contrast, the Sitakund anticline in SE Bangladesh reveals a decrease in velocity with depth from 3000 to 4000 m, probably due to the presence of overpressured mudrocks of the Bhuban Formation. Tectonic compression, associated with the Indo-Burmese plate convergence likely contributed the most toward formation of subsurface overpressure in the Sitakund structure situated in the Chittagong-Tripura Fold Belt of the eastern Bengal basin, Bangladesh.

Digital integrated protection system

International Nuclear Information System (INIS)

Savornin, M.; Furet, M.

1978-01-01

As a result of technological progress it is now possible to achieve more elaborate protection functions able to follow more closely the phenomena to be supervised. For this reason the CEA, Framatome and Merlin/Gerin/CERCI have undertaken in commonn to develop a Digital Integrated Protection System (D.I.P.S.). This system is designed with the following aims: to improve the safety of the station, . to improve its availability, . to facilitate installation, . to facilitate tests and maintenance. The main characteristics adopted are: . possibilities of obtaining more elaborate monitoring and protection algorithm treatments, . order 4 redundancy of transducers, associated instruments and signal processing, . possibility of inhibiting part of the protection system, . standardisation of equipment, physical and electrical separation of redundant units, . use of multiplexed connections, . automation of tests. Four flow charts are presented: - DIPS with four APUP (Acquisition and Processing Unit for Protection) - APUP - LSU (Logic Safeguard Unit), number LSU corresponding to number fluidic safeguard circuits, - structure of a function unit, - main functions of the APUP [fr

Effect of Remote Back-Up Protection System Failure on the Optimum Routine Test Time Interval of Power System Protection

Directory of Open Access Journals (Sweden)

Y Damchi

2013-12-01

Full Text Available Appropriate operation of protection system is one of the effective factors to have a desirable reliability in power systems, which vitally needs routine test of protection system. Precise determination of optimum routine test time interval (ORTTI plays a vital role in predicting the maintenance costs of protection system. In the most previous studies, ORTTI has been determined while remote back-up protection system was considered fully reliable. This assumption is not exactly correct since remote back-up protection system may operate incorrectly or fail to operate, the same as the primary protection system. Therefore, in order to determine the ORTTI, an extended Markov model is proposed in this paper considering failure probability for remote back-up protection system. In the proposed Markov model of the protection systems, monitoring facility is taken into account. Moreover, it is assumed that the primary and back-up protection systems are maintained simultaneously. Results show that the effect of remote back-up protection system failures on the reliability indices and optimum routine test intervals of protection system is considerable.

Adaptive protection algorithm and system

Science.gov (United States)

Hedrick, Paul [Pittsburgh, PA; Toms, Helen L [Irwin, PA; Miller, Roger M [Mars, PA

2009-04-28

An adaptive protection algorithm and system for protecting electrical distribution systems traces the flow of power through a distribution system, assigns a value (or rank) to each circuit breaker in the system and then determines the appropriate trip set points based on the assigned rank.

High-Temperature Gas-cooled Reactor steam-cycle/cogeneration lead plant reactor vessel: system design description

International Nuclear Information System (INIS)

1983-01-01

The Reactor Vessel System contains the primary coolant inventory within a gas-tight pressure boundary, and provides the necessary flow paths and overpressure protection for this pressure boundary. The Reactor Vessel System also houses the components of the Reactor System, the Heat Transport System, and the Auxiliary Heat Removal System. The scope of the Reactor Vessel System includes the prestressed concrete reactor vessel (PCRV) structure with its reinforcing steel and prestressing components; liners, penetrations, closures, and cooling water tubes attached to the concrete side of the liner; the thermal barrier (insulation) on the primary coolant side of the liner; instrumentation for structural monitoring; and a pressure relief system. Specifications are presented

Advanced Worker Protection System

International Nuclear Information System (INIS)

1996-04-01

The Advanced Worker Protection System (AWPS) is a liquid-air-based, self-contained breathing and cooling system with a duration of 2 hrs. AWPS employs a patented system developed by Oceaneering Space Systems (OSS), and was demonstrated at their facility in Houston, TX as well as at Kansas State University, Manhattan. The heart of the system is the life-support backpack that uses liquid air to provide cooling as well as breathing gas to the worker. The backpack is combined with advanced protective garments, an advanced liquid cooling garment (LCG), a respirator, and communications and support equipment. The prototype unit development and testing under Phase 1 has demonstrated that AWPS has the ability to meet performance criteria. These criteria were developed with an understanding of both the AWPS capabilities and the DOE decontamination and decommissioning (D and D) activities protection needs

49 CFR 195.428 - Overpressure safety devices and overfill protection systems.

Science.gov (United States)

2010-10-01

... reliability of operation for the service in which it is used. (b) In the case of relief valves on pressure... the operator notes in the manual required by § 195.402 why compliance with that part is not necessary...

The use of HANDIDET{reg_sign} non-electric detonator assemblies to reduce blast-induced overpressure at AECL`s Underground Research Laboratory

Energy Technology Data Exchange (ETDEWEB)

Onagi, D.P.; Keith, S.G.; Kuzyk, G.W. [AECL, Pinawa, Manitoba (Canada). Underground Research Lab.; Proudfoot, D.F. [ICI Explosives Canada, North Delta, British Columbia (Canada)

1996-12-01

A number of aspects of the Canadian concept for nuclear fuel waste disposal are being assessed by Atomic Energy of Canada Limited (AECL) in a series of experiments at its Underground Research Laboratory (URL) near Lac du Bonnet, Manitoba, Canada. One of the major objectives of the work being carried out at the URL is to develop and evaluate the methods and technology to ensure safe, permanent disposal of Canada`s nuclear fuel waste. In 1994, AECL excavated access tunnels and a laboratory room for the Quarried Block Fracture Migration Experiment (QBFME) at the 240 Level of the URL. This facility will be used to study the transport of radionuclides in natural fractures in quarried blocks of granite under in-situ groundwater conditions. The experiment is being carried out under a cooperative agreement with the Japan Atomic Energy Research Institute. The excavation of the QBFME access tunnels and laboratory was carried out using controlled blasting techniques that minimized blast-induced overpressure which could have damaged or interrupted other ongoing experiments in the vicinity. The majority of the blasts used conventional long delay non-electric detonators but a number of blasts were carried out using HANDIDET 250/6000 non-electric long delay detonator assemblies and HTD{reg_sign} non-electric short delay trunkline detonator assemblies. The tunnel and laboratory excavation was monitored to determine the levels of blast-induced overpressure. This paper describes the blasting and monitoring results of the blasts using HANDIDET non-electric detonator assemblies and the effectiveness of these detonators in reducing blast-induced overpressure.

Protection of industrial power systems

CERN Document Server

DAVIES, T

2006-01-01

The protection which is installed on an industrial power system is likely to be subjected to more difficult conditions than the protection on any other kind of power system. Starting with the many simple devices which are employed and covering the whole area of industrial power system protection, this book aims to help achieve a thorough understanding of the protection necessary.Vital aspects such as the modern cartridge fuse, types of relays, and the role of the current transformer are covered and the widely used inverse definite-minimum time overcurrent relay, the theory of the M

Relay protection coordination with generator capability curve, excitation system limiters and power system relay protections settings

Directory of Open Access Journals (Sweden)

Buha Danilo

2016-01-01

Full Text Available The relay protection settings performed in the largest thermal powerplant (TE "Nikola Tesla B" are reffered and explained in this paper. The first calculation step is related to the coordination of the maximum stator current limiter settings, the overcurrent protection with inverse characteristics settings and the permitted overload of the generator stator B1. In the second calculation step the settings of impedance generator protection are determined, and the methods and criteria according to which the calculations are done are described. Criteria used to provide the protection to fulfill the backup protection role in the event of malfunction of the main protection of the transmission system. are clarified. The calculation of all protection functions (32 functions of generator B1 were performed in the project "Coordination of relay protection blocks B1 and B2 with the system of excitation and power system protections -TENT B".

Fundamentals of boiling water reactor systems

International Nuclear Information System (INIS)

Mattern, J.

1976-01-01

The reactor assembly consists of the reactor vessel, its internal components of the core, shroud, steam separator, dryer assemblies, feedwater spargers, internal recirculation pumps and control rod drive housings. Connected to the steam lines are the pressure relief valves which protect the pressure boundary from damage due to overpressure. (orig./TK) [de

Statistics of peak overpressure and shock steepness for linear and nonlinear N-wave propagation in a kinematic turbulence.

Science.gov (United States)

Yuldashev, Petr V; Ollivier, Sébastien; Karzova, Maria M; Khokhlova, Vera A; Blanc-Benon, Philippe

2017-12-01

Linear and nonlinear propagation of high amplitude acoustic pulses through a turbulent layer in air is investigated using a two-dimensional KZK-type (Khokhlov-Zabolotskaya-Kuznetsov) equation. Initial waves are symmetrical N-waves with shock fronts of finite width. A modified von Kármán spectrum model is used to generate random wind velocity fluctuations associated with the turbulence. Physical parameters in simulations correspond to previous laboratory scale experiments where N-waves with 1.4 cm wavelength propagated through a turbulence layer with the outer scale of about 16 cm. Mean value and standard deviation of peak overpressure and shock steepness, as well as cumulative probabilities to observe amplified peak overpressure and shock steepness, are analyzed. Nonlinear propagation effects are shown to enhance pressure level in random foci for moderate initial amplitudes of N-waves thus increasing the probability to observe highly peaked waveforms. Saturation of the pressure level is observed for stronger nonlinear effects. It is shown that in the linear propagation regime, the turbulence mainly leads to the smearing of shock fronts, thus decreasing the probability to observe high values of steepness, whereas nonlinear effects dramatically increase the probability to observe steep shocks.

Protective and Catching Safety Systems In Construction

Directory of Open Access Journals (Sweden)

Kuzhin Marat

2017-01-01

Full Text Available In the article is described application of protective and catching systems in construction. Classification of similar systems, their types and purpose are listed. Dangerous zones on construction site and events to for limiting their influence or protection from the factors. Protective and catching systems is one of the most effective technical equipment, applied in recent time. Protective fences and catching systems are important part in the problem solution. Protective fences protect workers from falling from height. Protective and catching systems allows avoid injuries by workers, also catch debris, fallen from constructing buildings. In regard with continuing development in technical and technological solutions, protective and catching systems require adaptation to a new requirements of construction industry and requirements of normative documents. Technical regulations in the appliance sphere of protective and catching systems requires actualization and aligning with modern normatives. Important role should be given to developing organizational and technological documentation for application of the systems. Scientific studying of technical parameters of fences and protective catching nets also has great interest.

Over-pressure test on BARCOM pre-stressed concrete containment

Energy Technology Data Exchange (ETDEWEB)

Parmar, R.M.; Singh, Tarvinder; Thangamani, I.; Trivedi, Neha; Singh, Ram Kumar, E-mail: rksingh@barc.gov.in

2014-04-01

Bhabha Atomic Research Centre (BARC), Trombay has organized an International Round Robin Analysis program to carry out the ultimate load capacity assessment of BARC Containment (BARCOM) test model. The test model located in BARC facilities Tarapur; is a 1:4 scale representation of 540 MWe Pressurized Heavy Water Reactor (PHWR) pre-stressed concrete inner containment structure of Tarapur Atomic Power Station (TAPS) unit 3 and 4. There are a large number of sensors installed in BARCOM that include vibratory wire strain gauges of embedded and spot-welded type, surface mounted electrical resistance strain gauges, dial gauges, earth pressure cells, tilt meters and high resolution digital camera systems for structural response, crack monitoring and fracture parameter measurement to evaluate the local and global behavior of the containment test model. The model has been tested pneumatically during the low pressure tests (LPTs) followed by proof test (PT) and integrated leakage rate test (ILRT) during commissioning. Further the over pressure test (OPT) has been carried out to establish the failure mode of BARCOM Test-Model. The over-pressure test will be completed shortly to reach the functional failure of the test model. Pre-test evaluation of BARCOM was carried out with the results obtained from the registered international round robin participants in January 2009 followed by the post-test assessment in February 2011. The test results along with the various failure modes related to the structural members – concrete, rebars and tendons identified in terms of prescribed milestones are presented in this paper along with the comparison of the pre-test predictions submitted by the registered participants of the Round Robin Analysis for BARCOM test model.

Smart machine protection system

International Nuclear Information System (INIS)

Clark, S.; Nelson, D.; Grillo, A.

1992-01-01

A Machine Protection System implemented on the SLC automatically controls the beam repetition rates in the accelerator so that radiation or temperature faults slow the repetition rate to bring the fault within tolerance without shutting down the machine. This process allows the accelerators to aid in the fault diagnostic process, and the protection system automatically restores the beams back to normal rates when the fault is diagnosed and corrected. The user interface includes facilities to monitor the performance of the system, and track rate limits, faults, and recoveries. There is an edit facility to define the devices to be included in the protection system, along with their set points, limits, and trip points. This set point and limit data is downloaded into the CAMAC modules, and the configuration data is complied into a logical decision tree for the 68030 processor. (author)

Smart Machine Protection System

International Nuclear Information System (INIS)

Clark, S.; Nelson, D.; Grillo, A.; Spencer, N.; Hutchinson, D.; Olsen, J.; Millsom, D.; White, G.; Gromme, T.; Allison, S.; Underwood, K.; Zelazny, M.; Kang, H.

1991-11-01

A Machine Protection System implemented on the SLC automatically controls the beam repetition rates in the accelerator so that radiation or temperature faults slow the repetition rate to bring the fault within tolerance without shutting down the machine. This process allows the accelerator to aid in the fault diagnostic process, and the protection system automatically restores the beams back to normal rates when the fault is diagnosed and corrected. The user interface includes facilities to monitor the performance of the system, and track rate limits, faults, and recoveries. There is an edit facility to define the devices to be included in the protection system, along with their set points, limits, and trip points. This set point and limit data is downloaded into the CAMAC modules, and the configuration data is compiled into a logical decision tree for the 68030 processor. 3 figs

Maximum overpressure in gastight containers of the storage and transport of dangerous liquids

International Nuclear Information System (INIS)

Steen, H.

1977-11-01

For a design of containers suitable under safety aspects for the transport and storage of dangerous liquids the maximum overpressure to be expected is an important value. The fundamentals for the determination of the internal pressure are pointed out for the simplified model of a rigid (i.e. not elastically or plastically deforming) and gastight container. By assuming of extreme storage and transport conditions (e.g. for the maximum liquid temperatures due to sun radiation) the figures of the maximum overpressure are calculated for about hundred liquids being of practical interest. The results show a significant influence of the compression of air in the ullage space caused by liquid expansion due to temperature rise (compression effect), particularly for liquids with a higher boiling point. The influence of the solubility of air in the liquid on the internal pressure can be neglected under the assumed transport conditions. The estimation of the volume increase of the container due to the effect of the internal pressure leads to the limitation, that the assumption of a rigid container is only justified for cylindrical and spherical steel tanks. The enlargement of the container volume due to a heating of the container shell does play no significant roll for all metal containers under the assumed conditions of storage and transport. The results obtained bear out essentially the stipulations for the test pressure and the filling limits laid down in the older German regulations for the transport of dangerous liquids in rail tank waggons and road tank vehicles without pressure relief valves. For the recently fixed and internationally harmonized regulations for tankcontainers the considerations and the results pointed out in this paper give rise to a review. (orig.) [de

Deficiencies in radiation protection record systems

International Nuclear Information System (INIS)

Martin, J.B.; Lyon, M.

1991-01-01

Radiation protection records are a fundamental part of any program for protecting radiation workers. Records are essential to epidemiological studies of radiation workers and are becoming increasingly important as the number of radiation exposure litigation cases increases. Ready retrievability of comprehensive records is also essential to the adequate defense of a radiation protection program. Appraisals of numerous radiation protection programs have revealed that few record-keeping systems comply with American National Standards Institute, Standard Practice N13.6-1972. Record-keeping requirements and types of deficiencies in radiation protection records systems are presented in this paper, followed by general recommendations for implementing a comprehensive radiation protection records system

Deficiencies in radiation protection record systems

International Nuclear Information System (INIS)

Martin, J.B.; Lyon, M.

1991-01-01

Radiation protection records are a fundamental part of any program for protecting radiation workers. Records are essential to epidemiological studies of radiation workers and are becoming increasingly important as the number of radiation exposure litigation cases increases. Ready retrievability of comprehensive records is also essential to the adequate defense of a radiation protection program. Appraisals of numerous radiation protection programs have revealed that few record-keeping systems comply with American National Standards Institute, Standard Practice N13.6-1972. Record-keeping requirements and types of deficiencies in radiation protection records systems are presented in this paper, followed by general recommendations for implementing a comprehensive radiation protection records system. 8 refs

Current state of knowledge on the behavior of steel liners in concrete containments subjected to overpressurization loads

International Nuclear Information System (INIS)

von Riesemann, W.A.; Parks, M.B.

1993-01-01

In the United States, concrete containment buildings for commercial nuclear power plants have steel liners that act as the intemal pressure boundary. The liner abuts the concrete, acting as the interior concrete form. The liner is attached to the concrete by either studs or by a continuous structural shape (such as a T-section or channel) that is either continuously or intermittently welded to the liner. Studs are commonly used in reinforced concrete containments, while prestressed containments utilize a structural element as the anchorage. The practice in some countries follows the US practice, while in other countries the containment does not have a steel liner. In this latter case, there is a true double containment, and the annular region between the two containments is vented. This paper will review the practice of design of the liner system prior to the consideration of severe accident loads (overpressurization loads beyond the design conditions)

Mechanical study of the Chartreuse Fold-and-Thrust Belt: relationships between fluids overpressure and decollement within the Toarcian source-rock

Science.gov (United States)

Berthelon, Josselin; Sassi, William; Burov, Evgueni

2016-04-01

Many source-rocks are shale and constitute potential detachment levels in Fold-and-Thrust Belts (FTB): the toarcian Schistes-Cartons in the French Chartreuse FTB for example. Their mechanical properties can change during their burial and thermal maturation, as for example when large amount of hydrocarbon fluids are generated. A structural reconstruction of the Chartreuse FTB geo-history places the Toarcian Formation as the major decollement horizon. In this work, a mechanical analysis integrating the fluids overpressuring development is proposed to discuss on the validity of the structural interpretation. At first, an analogue of the Chartreuse Toarcian Fm, the albanian Posidonia Schist, is documented as it can provide insights on its initial properties and composition of its kerogen content. Laboratory characterisation documents the vertical evolution of the mineralogical, geochemical and mechanical parameters of this potential decollement layer. These physical parameters (i.e. Total Organic Carbon (TOC), porosity/permeability relationship, friction coefficient) are used to address overpressure buildup in the frontal part of the Chartreuse FTB with TEMISFlow Arctem Basin modelling approach (Faille et al, 2014) and the structural emplacement of the Chartreuse thrust units using the FLAMAR thermo-mechanical model (Burov et al, 2014). The hydro-mechanical modeling results highlight the calendar, distribution and magnitude of the overpressure that developed within the source-rock in the footwall of a simple fault-bend fold structure localized in the frontal part of the Chartreuse FTB. Several key geological conditions are required to create an overpressure able to fracture the shale-rocks and induce a significant change in the rheological behaviour: high TOC, low permeability, favourable structural evolution. These models highlight the importance of modeling the impact of a diffuse natural hydraulic fracturing to explain fluids propagation toward the foreland within

Selectivity of power system protections at power swings in power system

Directory of Open Access Journals (Sweden)

Jan Machowski

2012-12-01

Full Text Available The paper discusses out-of-step protection systems such as: generator pole slip protections, out of step tripping protections, distance protections of step-up transformer, distance protections of transmission lines and transformers, power swing blocking, and special out-of-step protection. It is shown that all these protections make up a protection system, to which a setting concept uniform for the entire power system has to be applied. If a power system is inappropriately equipped with these protections, or their settings are inappropriate, they may operate unselectively, thus contributing to the development of power system blackouts. In the paper the concepts for a real power system are given for the two stages: target stage fully compliant with selectivity criteria, and transitional stage between the current and target stages.

Reactor protection and shut-down system

International Nuclear Information System (INIS)

Klar

1980-01-01

The reactor protection system being a part of the reactor safety system. The requirements on the reactor protection system are: high safety with regard to signal processing, high availability, self-reporting of faults etc. The functional sections of the reactor protection system are the analog section, the logic section and the generating of output signals. Description of the operation characteristics and of the extension of function. (orig.)

Seismic chimneys in the Southern Viking Graben - Implications for palaeo fluid migration and overpressure evolution

Science.gov (United States)

Karstens, Jens; Berndt, Christian

2015-02-01

Detailed understanding of natural fluid migration systems is essential to minimize risks during hydrocarbon exploration and to evaluate the long-term efficiency of the subsurface storage of waste water and gas from hydrocarbon production as well as CO2. The Southern Viking Graben (SVG) hosts numerous focused fluid flow structures in the shallow (expressions of vertical fluid conduits are variously known as seismic chimneys or pipes. Seismic pipes are known to form large clusters. Seismic chimneys have so far been described as solitary structures. Here, we show that the study area in the SVG hosts more than 46 large-scale vertical chimney structures, which can be divided in three categories implying different formation processes. Our analysis reveals that seal-weakening, formation-wide overpressure and the presence of free gas are required to initiate the formation of vertical fluid conduits in the SVG. The presence of numerous vertical fluid conduits implies inter-stratigraphic hydraulic connectivity, which significantly affects the migration of fluids in the subsurface. Chimney structures are important for understanding the transfer of pore pressure anomalies to the shallow parts of the basin.

Regulatory control of physical protection systems

International Nuclear Information System (INIS)

Rajdeep; Mayya, Y.S.

2017-01-01

The safety of facilities in BARC is under the regulatory oversight of BSC. The security architecture for these facilities incorporates multiple layers of Physical Protection Systems. The demands of safety may sometimes conflict with the needs of security. Realizing the need to identify these interfaces and extend the regulatory coverage to Physical Protection Systems, a Standing Committee named Physical Protection System Review Committee (PPSRC) has been constituted as a 2"n"d tier entity of BSC. PPSRC includes experts from various domains concerned with nuclear security, viz. physical protection systems, cyber security, radiation safety, security operations, technical services and security administration

Distributed Supervisory Protection Interlock System

International Nuclear Information System (INIS)

Walz, H.V.; Agostini, R.C.; Barker, L.; Cherkassky, R.; Constant, T.; Matheson, R.

1989-03-01

The Distributed Supervisory Protection Interlock System, DSPI, is under development at the Stanford Linear Accelerator Center for requirements in the areas of personnel protection, beam containment and equipment protection interlocks. The DSPI system, distributed over the application site, consists of segments with microprocessor-based controller and I/O modules, local area networks for communication, and a global supervisor computer. Segments are implemented with commercially available controller and I/O modules arranged in local interlock clusters, and associated software. Segments provide local interlock data acquisition, processing and control. Local area networks provide the communication backbone between segments and a global supervisor processor. The supervisor processor monitors the overall system, reports detail status and provides human interfaces. Details of an R and D test system, which will implement the requirements for personnel protection of 4 typical linear accelerator sectors, will be described. 4 refs., 2 figs

Power system protection 2 systems and methods

CERN Document Server

1995-01-01

The worldwide growth in demand for electricity has forced the pace of developments in electrical power system design to meet consumer needs for reliable, secure and cheap supplies. Power system protection, as a technology essential to high quality supply, is widely recognised as a specialism of growing and often critical importance, in which power system needs and technological progress have combined to result in rapid developments in policy and practice in recent years. In the United Kingdom, the need for appropriate training in power system protection was recognised in the early 1960s with t

Wind turbine with lightning protection system

DEFF Research Database (Denmark)

2016-01-01

The present invention relates to a wind turbine comprising a lightning protection system comprising a waveguide interconnecting a communication device and a signal-carrying structure. In other aspects, the present invention relates to the use of a waveguide in a lightning protection system...... of a wind turbine, a power splitter and its use in a lightning protection system of a wind turbine....

Experimental study of the overpressures generated by the detonation of spherical air-hydrocarbon gaseous mixtures

International Nuclear Information System (INIS)

Brossard, J.

1978-01-01

The characteristics of the pressure waves transmitted by detonation of gaseous mixtures to the surrounding air were measured by tests made near the ground level in 1 to 54 m 3 spherical balloons containing air-acetylene or air-ethylene mixtures. As concerns the peak overpressure Δp, a theoretical dimensional analysis in accordance with the experimental results shows that Δp can be expressed as a function of two independent variables, which are the radial distance R and the volume V of the balloon . A semi-empirical formula, including ground effects, is proposed and its present validity range is given. (author)

Design Of Photovoltaic Powered Cathodic Protection System

Directory of Open Access Journals (Sweden)

Golina Samir Adly

2017-07-01

Full Text Available The corrosion caused by chemical reaction between metallic structures and surrounding mediums such as soil or water .the CP cathodic protection system is used to protect metallic structure against corrosion. Cathodic protection CP used to minimize corrosion by utilizing an external source of electrical current which forces the entire structure to become a cathode. There are two Types of cathodic protection system Galvanic current Impressed current.the Galvanic current is called a sacrificial anode is connected to the protected structure cathode through a DC power supply. In Galvanic current system a current passes from the sacrificing anode to the protected structure .the sacrificial anode is corroded rather than causing the protected structure corrosion .protected structure requires a constant current to stop the corrosion which determined by area structure metal and the surrounding medium. The rains humidity are decrease soil resistivity and increase the DC current .The corrosion and over protection resulting from increase in the DC current is harmful for the metallic structure. This problem can be solved by conventional cathodic protection system by manual adjustment of DC voltage periodically to obtain a constant current .the manual adjustment of DC voltage depends on experience of the technician and using the accuracy of the measuring equipment. The errors of measuring current depend on error from the technician or error from the measuring equipment. the corrosion of structure may occur when the interval between two successive adjustment is long .An automatically regulated cathodic protection system is used to overcome problems from conventional cathodic protection system .the regulated cathodic protection system adjust the DC voltage of the system automatically when it senses the variations of surrounding medium resistivity so the DC current is constant at the required level.

CCF analysis of high redundancy systems safety/relief valve data analysis and reference BWR application

International Nuclear Information System (INIS)

Mankamo, T.; Bjoere, S.; Olsson, Lena

1992-12-01

Dependent failure analysis and modeling were developed for high redundancy systems. The study included a comprehensive data analysis of safety and relief valves at the Finnish and Swedish BWR plants, resulting in improved understanding of Common Cause Failure mechanisms in these components. The reference application on the Forsmark 1/2 reactor relief system, constituting of twelve safety/relief lines and two regulating relief lines, covered different safety criteria cases of reactor depressurization and overpressure protection function, and failure to re close sequences. For the quantification of dependencies, the Alpha Factor Model, the Binomial Probability Model and the Common Load Model were compared for applicability in high redundancy systems

Optimizing Blasting’s Air Overpressure Prediction Model using Swarm Intelligence

Science.gov (United States)

Nur Asmawisham Alel, Mohd; Ruben Anak Upom, Mark; Asnida Abdullah, Rini; Hazreek Zainal Abidin, Mohd

2018-04-01

Air overpressure (AOp) resulting from blasting can cause damage and nuisance to nearby civilians. Thus, it is important to be able to predict AOp accurately. In this study, 8 different Artificial Neural Network (ANN) were developed for the purpose of prediction of AOp. The ANN models were trained using different variants of Particle Swarm Optimization (PSO) algorithm. AOp predictions were also made using an empirical equation, as suggested by United States Bureau of Mines (USBM), to serve as a benchmark. In order to develop the models, 76 blasting operations in Hulu Langat were investigated. All the ANN models were found to outperform the USBM equation in three performance metrics; root mean square error (RMSE), mean absolute percentage error (MAPE) and coefficient of determination (R2). Using a performance ranking method, MSO-Rand-Mut was determined to be the best prediction model for AOp with a performance metric of RMSE=2.18, MAPE=1.73% and R2=0.97. The result shows that ANN models trained using PSO are capable of predicting AOp with great accuracy.

Temporary physical protection systems

International Nuclear Information System (INIS)

Williams, J.D.; Gangel, D.J.; Madsen, R.W.

1991-01-01

Terrorism and other aspects of world political instability have created a high demand for temporary physical protection systems within the nuclear materials management community. They can be used when vehicles carrying important assets are away from their permanent fixed site location, around areas where experiments are being temporarily conducted, around construction areas and one portions of a fixed site physical security system which is temporarily inoperable. Physical security systems can be grouped into four categories: tactical, portable, semi-permanent, and fixed. The resources and experience gained at Sandia National Laboratories in over forty years of developing and implementing security systems for protecting nuclear weapons and fixed nuclear facilities is now being applied to temporary physical security systems. This paper emphasizes temporary physical security systems and their component parts that are presently available and identify additional system-subsystem objectives, requirements, and concepts

Identity management and witness protection system

OpenAIRE

Paunović, Saša; Starčević, Dušan; Nešić, Lazar

2013-01-01

The protection of participants in criminal proceedings is one of the most important tools for prosecution of war crimes and organized crime cases. The paper presents the basic characteristics and the importance of implementing the Program of protection in criminal proceedings, with emphasis on the protection system and management of identity. Special attention was paid to challenges facing the protection system in criminal proceedings and the management of identities, which are caused by the ...

78 FR 77574 - Protection System Maintenance Reliability Standard

Science.gov (United States)

2013-12-24

... commissioning of power system protection systems.\\55\\ NERC commits in its Comments to keep the Commission... commissioning of power system protection systems.\\62\\ As explained in the NOPR, our concern is with a protection... protection system, ``resulting in line relays being placed in service with the incorrect transformer ratio...

Digital protection in power plants. Electrical unit and line protection. Digital protection systems for NPP

International Nuclear Information System (INIS)

Kaczmarek, A.

2000-01-01

In this presentation author deals with the digital protection systems for nuclear power plants. The evolution of protection devices, protection concept for power plants, concept of functional redundancy, references for digital protection, benefits for the customer well as concept fault recorder are presented. (author)

Smart cathodic protection systems

NARCIS (Netherlands)

Polder, R.B.; Leggedoor, J.; Schuten, G.; Sajna, S.; Kranjc, A.

2010-01-01

Cathodic protection delivers corrosion protection in concrete structures exposed to aggressive environments, e.g. in de-icing salt and marine climates. Working lives of a large number of CP systems are at least more than 13 years and probably more than 25 years, provided a minimum level of

[Artificial intelligence] AI for protection systems

Energy Technology Data Exchange (ETDEWEB)

Aggarwal, R.; Johns, A.

1997-12-31

The reliable operation of large power systems with small stability margins is highly dependent on control systems and protection devices. Progress in the field of microprocessor systems and demanding requirements in respect of the performance of protective relays are the reasons for digital device applications to power system protection. The superiority of numeric protection over its analogue alternatives is attributed to such factors as accurate extraction of the fundamental voltage and current components through filtering, functional benefits resulting from multi-processor design and extensive self-monitoring, etc. However, all these reasons have not led to a major impact on speed, sensitivity and selectivity of primary protective relays, and the gains are only marginal; this is so because conventional digital relays still rely on deterministic signal models and a heuristic approach for decision making, so that only a fraction of the information contained within voltage and current signals as well as knowledge about the plant to be protected is used. The performance of digital relays may be substantially improved if the decision making is based on elements of artificial intelligence (AI). (Author)

Pressure Sores Prevention for Paraplegic People: Effects of Visual, Auditory and Tactile Supplementations on Overpressures Distribution in Seated Posture

Directory of Open Access Journals (Sweden)

Olivier Chenu

2012-01-01

Full Text Available This paper presents a study on the usage of different informative modalities as biofeedbacks of a perceptual supplementation device aiming at reducing overpressure at the buttock area. Visual, audio and lingual electrotactile modalities are analysed and compared with a non-biofeedback session. In conclusion, sensory modalities have a positive and equal effect, but they are not equally judged in terms of comfort and disturbance with some other activities.

Physical protection system design and evaluation

International Nuclear Information System (INIS)

Williams, J.D.

1997-11-01

The design of an effective physical protection system (PPS) includes the determination of the PPS objectives, the initial design of a PPS, the evaluation of the design, and probably, the redesign or refinement of the system. To develop the objectives, the designer must begin by gathering information about facility operation and conditions, such as a comprehensive description of the facility, operating conditions, and the physical protection requirements. The designer then needs to define the threat. This involves considering factors about potential adversaries: class of adversary, adversary's capabilities, and range of adversary's tactics. Next, the designer should identify targets. Determination of whether or not the materials being protected are attractive targets is based mainly on the ease or difficulty of acquisition and desirability of the material. The designer now knows the objectives of the PPS, that is, ''what to protect against whom.'' The next step is to design the system by determining how best to combine such elements as fences, vaults, sensors and assessment devices, entry control devices, communication devices, procedures, and protective force personnel to meet the objectives of the system. Once a PPS is designed, it must be analyzed and evaluated to ensure it meets the PPS objectives. Evaluation must allow for features working together to ensure protection rather than regarding each feature separately. Due to the complexity of the protection systems, an evaluation usually requires modeling techniques. If any vulnerabilities are found, the initial system must be redesigned to correct the vulnerabilities and a reevaluation conducted. After the system is installed, the threat and system parameters may change with time. If they do, the analysis must be performed periodically to ensure the system objectives are still being met

An integrated system for physical protection

International Nuclear Information System (INIS)

Kumar, Ranajit

2001-01-01

An Integrated Physical Protection System (IPPS) was developed for the consolidation of all sub systems, sensors and elements related to physical protection for an efficient and effective security environment of a facility. An effective physical protection system discharges the functions of detection, delay, communication, response, access control etc. IPPS performs, controls and monitors all the above functionality and helps in taking quick action on occurrence of unusual incidents by instantly reporting the incident in easily understandable audio, video, graphical and textual format and also by initiating automatic interactions among sub-systems

Reactor protection system. Revision 1

International Nuclear Information System (INIS)

Fairbrother, D.B.; Vincent, D.R.; Lesniak, L.M.

1975-04-01

The reactor protection system-II (RPS-II) designed for use on Babcock and Wilcox 145- and 205-fuel assembly pressurized water reactors is described. In this system, relays in the trip logic have been replaced by solid state devices. A calculating module for the low DNBR, pump status, and offset trip functions has replaced the overpower trip (based on flow and imbalance), the power/RC pump trip, and the variable low pressure trip. Included is a description of the changes from the present Oconee-type reactor protection system (RPS-I), a functional and hardware description of the calculating module, and a discussion of the qualification program conducted to ensure that the degree of protection provided by RPS-II is not less than that provided by previously licensed systems supplied by B and W. (U.S.)

Advanced physical protection systems for nuclear materials

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major US Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed in this paper. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. Finally, a list of measures is given for assessing overall physical protection system performance. (author)

Advanced physical protection systems for nuclear materials

International Nuclear Information System (INIS)

Jones, O.E.

1975-10-01

Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely-activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. A list of measures is given for assessing overall physical protection system performance. (auth)

Improved core protection calculator system algorithm

International Nuclear Information System (INIS)

Yoon, Tae Young; Park, Young Ho; In, Wang Kee; Bae, Jong Sik; Baeg, Seung Yeob

2009-01-01

Core Protection Calculator System (CPCS) is a digitized core protection system which provides core protection functions based on two reactor core operation parameters, Departure from Nucleate Boiling Ratio (DNBR) and Local Power Density (LPD). It generates a reactor trip signal when the core condition exceeds the DNBR or LPD design limit. It consists of four independent channels which adapted a two out of four trip logic. CPCS algorithm improvement for the newly designed core protection calculator system, RCOPS (Reactor COre Protection System), is described in this paper. New features include the improvement of DNBR algorithm for thermal margin, the addition of pre trip alarm generation for auxiliary trip function, VOPT (Variable Over Power Trip) prevention during RPCS (Reactor Power Cutback System) actuation and the improvement of CEA (Control Element Assembly) signal checking algorithm. To verify the improved CPCS algorithm, CPCS algorithm verification tests, 'Module Test' and 'Unit Test', would be performed on RCOPS single channel facility. It is expected that the improved CPCS algorithm will increase DNBR margin and enhance the plant availability by reducing unnecessary reactor trips

Simulations of the design basis accident at conditions of power increase and the o transient of MSIV at overpressure conditions of the Laguna Verde Power Station

International Nuclear Information System (INIS)

Araiza M, E.; Nunez C, A.

2001-01-01

This document presents the analysis of the simulation of the loss of coolant accident at uprate power conditions, that is 2027 MWt (105% of the current rated power of 1931MWt). This power was reached allowing an increase in the turbine steam flow rate without changing the steam dome pressure value at its rated conditions (1020 psiaJ. There are also presented the results of the simulation of the main steam isolation va/ve transient at overpressure conditions 1065 psia and 1067 MWt), for Laguna Verde Nuclear Power Station. Both simulations were performed with the best estimate computer code TRA C BF1. The results obtained in the loss of coolant accident show that the emergency core coolant systems can recover the water level in the core before fuel temperature increases excessively, and that the peak pressure reached in the drywell is always below its design pressure. Therefore it is concluded that the integrity of the containment is not challenged during a loss of coolant accident at uprate power conditions.The analysis of the main steam isolation valve transients at overpressure conditions, and the analysis of the particular cases of the failure of one to six safety relief valves to open, show that the vessel peak pressures are below the design pressure and have no significant effect on vessel integrity. (Author)

Availability analysis of supervised protective systems

International Nuclear Information System (INIS)

Kontoleon, N.; Kontoleon, J.M.; Chrysochoides, N.G.

1975-01-01

The behaviour in time of a nuclear reactor supervised protective system is modelled mathematically by a Markov process, continuous in time and with three discrete states. Failure and repair rates are assumed to be exponentially distributed. An analytical expression of system availability as a function of failure and repair rates as well as the inspection intervals and duration is derived. An optimization problem is then discussed in order to maximize system availability with respect to imposed cost constraints. Finally, an example of a supervised protective system with short inactive times is given, which may be found in many practical situations of modern protective systems. (author)

The LHC quench protection system

CERN Multimedia

2009-01-01

The new quench protection system (QPS) has the crucial roles of providing an early warning for any part of the superconducting coils and busbars that develop high resistance, as well as triggering the switch-off of the machine. Over 2000 new detectors will be installed around the LHC to make sure every busbar segment between magnets is monitored and protected. One of the major consolidation activities for the LHC is the addition of two new detectors to the quench protection system. A magnet quench occurs when part of the superconducting cable becomes normally-conducting. When the protection system detects an increased resistance the huge amount of energy stored in the magnet chains is safely extracted and ‘dumped’ into specially designed resistors. In the case of the main dipole chain, the stored energy in a single LHC sector is roughly the same as the kinetic energy of a passenger jet at cruising speed. The first new detector is designed to monitor the superconducting...

Radiological protection system in the era of nuclear renaissance expectation for development of radiological protection system

International Nuclear Information System (INIS)

Toyomatsu, Hideki

2008-01-01

The current radiological protection system, which was established mainly by the ICRP and UNSCEAR, has contributed to the prevention of potential radiological health hazards, and has been a fundamental concept during the development of nuclear energy. Through a detailed discussion regarding the new ICRP recommendations, the world nuclear industry has reached a consensus that the current radiological protection system keeps its integrity in principle although it involves some remaining issues, such as the disposal of radioactive waste. In order to maximize the advantages of nuclear energy while keeping the integrity of radiological protection system, it is essential to address the characteristics of radiation, which is specific to nuclear energy, so that nuclear energy can coexist with other energy sources. The three basic principles of radiological protection (i.e., justification, optimization and dose limits), which were completed in the 1990 recommendations of ICRP, should be retained as the basic concepts for the future radiological protection system in order to maintain the continuity and consistency of the radiological protection system. The radiological protection system can be furthermore developed only by combining the above three principles with best practices extracted from utilities' field experience. The significant reduction of radiation exposures received by members of the public and radiation workers in the field has resulted from the efforts by the world utilities to achieve the optimization. In order to correctly apply the theory to the work practices, it is essential to see how the theory is practically used in the field. Such a process should be also emphasized in the revision work of the IAEA Basic Safety Standards (BSS), which is currently under progress. Integrating the theory in the work practices is the key to the true development of nuclear renaissance, which could lead to the establishment of the nuclear safety regime. (author)

Power system protection 3 application

CERN Document Server

1995-01-01

The worldwide growth in demand for electricity has forced the pace of developments in electrical power system design to meet consumer needs for reliable, secure and cheap supplies. Power system protection, as a technology essential to high quality supply, is widely recognised as a specialism of growing and often critical importance, in which power system needs and technological progress have combined to result in rapid developments in policy and practice in recent years. In the United Kingdom, the need for appropriate training in power system protection was recognised in the early 1960s with t

46 CFR 153.460 - Fire protection systems.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Fire protection systems. 153.460 Section 153.460... Requirements for Flammable Or Combustible Cargoes § 153.460 Fire protection systems. Each self-propelled ship... protection system listed beside the cargo in Table 1 and described in the footnotes to Table 1. (b) The...

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

J. D. Bigbee

2000-06-21

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

J. D. Bigbee

2000-01-01

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status

Advanced worker protection system

International Nuclear Information System (INIS)

Caldwell, B.; Duncan, P.; Myers, J.

1995-01-01

The Department of Energy (DOE) is in the process of defining the magnitude and diversity of Decontamination and Decommissioning (D ampersand D) obligations at its numerous sites. The DOE believes that existing technologies are inadequate to solve many challenging problems such as how to decontaminate structures and equipment cost effectively, what to do with materials and wastes generated, and how to adequately protect workers and the environment. Preliminary estimates show a tremendous need for effective use of resources over a relatively long period (over 30 years). Several technologies are being investigated which can potentially reduce D ampersand D costs while providing appropriate protection to DOE workers. The DOE recognizes that traditional methods used by the EPA in hazardous waste site clean up activities are insufficient to provide the needed protection and worker productivity demanded by DOE D ampersand D programs. As a consequence, new clothing and equipment which can adequately protect workers while providing increases in worker productivity are being sought for implementation at DOE sites. This project will result in the development of an Advanced Worker Protection System (AWPS). The AWPS will be built around a life support backpack that uses liquid air to provide cooling as well as breathing gas to the worker. The backpack will be combined with advanced protective garments, advanced liquid cooling garment, respirator, communications, and support equipment to provide improved worker protection, simplified system maintenance, and dramatically improve worker productivity through longer duration work cycles. Phase I of the project has resulted in a full scale prototype Advanced Worker Protection Ensemble (AWPE, everything the worker will wear), with sub-scale support equipment, suitable for integrated testing and preliminary evaluation. Phase II will culminate in a full scale, certified, pre-production AWPS and a site demonstration

Advanced worker protection system

Energy Technology Data Exchange (ETDEWEB)

Caldwell, B.; Duncan, P.; Myers, J.

1995-12-01

The Department of Energy (DOE) is in the process of defining the magnitude and diversity of Decontamination and Decommissioning (D&D) obligations at its numerous sites. The DOE believes that existing technologies are inadequate to solve many challenging problems such as how to decontaminate structures and equipment cost effectively, what to do with materials and wastes generated, and how to adequately protect workers and the environment. Preliminary estimates show a tremendous need for effective use of resources over a relatively long period (over 30 years). Several technologies are being investigated which can potentially reduce D&D costs while providing appropriate protection to DOE workers. The DOE recognizes that traditional methods used by the EPA in hazardous waste site clean up activities are insufficient to provide the needed protection and worker productivity demanded by DOE D&D programs. As a consequence, new clothing and equipment which can adequately protect workers while providing increases in worker productivity are being sought for implementation at DOE sites. This project will result in the development of an Advanced Worker Protection System (AWPS). The AWPS will be built around a life support backpack that uses liquid air to provide cooling as well as breathing gas to the worker. The backpack will be combined with advanced protective garments, advanced liquid cooling garment, respirator, communications, and support equipment to provide improved worker protection, simplified system maintenance, and dramatically improve worker productivity through longer duration work cycles. Phase I of the project has resulted in a full scale prototype Advanced Worker Protection Ensemble (AWPE, everything the worker will wear), with sub-scale support equipment, suitable for integrated testing and preliminary evaluation. Phase II will culminate in a full scale, certified, pre-production AWPS and a site demonstration.

The Analysis of Loop Seal Purge Time for the KHNP Pressurizer Safety Valve Test Facility Using the GOTHIC Code

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Ae; Kim, Chang Hyun; Kweon, Gab Joo; Park, Jong Woon [Korea Hydro and Nuclear Power Co., Ltd., Daejeon (Korea, Republic of)

2007-10-15

The pressurizer safety valves (PSV) in Pressurized Water Reactors are required to provide the overpressure protection for the Reactor Coolant System (RCS) during the overpressure transients. Korea Hydro and Nuclear Power Company (KHNP) plans to build the PSV test facility for the purpose of providing the PSV pop-up characteristics and the loop seal dynamics for the new safety analysis. When the pressurizer safety valve is mounted in a loop seal configuration, the valve must initially pass the loop seal water prior to popping open on steam. The loop seal in the upstream of PSV prevents leakage of hydrogen gas or steam through the safety valve seat. This paper studies on the loop seal clearing dynamics using GOTHIC-7.2a code to verify the effects of loop seal purge time on the reactor coolant system overpressure.

EMP protection procedure for electrical/electronic systems

International Nuclear Information System (INIS)

Latorre, V.R.

1976-01-01

This paper presents a procedure for the protection engineer to follow in assessing a system with respect to its susceptibility to an electromagnetic pulse (EMP), and in determining whether the system requires protection. If the system is determined to be vulnerable to EMP, the procedure also indicates how to decide upon the most suitable protection scheme. The discussion centers on two flow charts, which illustrate the step-by-step procedure which utilizes the necessary ingredients of EMP protection engineering discussed in a previous paper. The description of the protection procedure is divided into two parts: the first dealing with issues on the macroscopic or large-scale system level, while the second is concerned with operations on the subsystem level or lower

Sandia Laboratories plutonium protection system

International Nuclear Information System (INIS)

Bernard, E.A.; Miyoshi, D.S.; Gutierrez, F.D.

1977-01-01

Sandia Laboratories is developing an improved plutonium protection system (PPS) to demonstrate new concepts for enhancing special nuclear materials safeguards. PPS concepts include separation of functions, real-time item accountability and improved means for control of materials, activities and personnel access. Physical barriers and a secure communications network are designed into the system to offer greater protection against sabotage, diversion and theft attempts. Prototype systems are being constructed at Hanford, Washington and Albuquerque, New Mexico and will be subjected to a comprehensive testing and evaluation program

The Diamond machine protection system

International Nuclear Information System (INIS)

Heron, M.T.; Lay, S.; Chernousko, Y.; Hamadyk, P.; Rotolo, N.

2012-01-01

The Diamond Light Source Machine Protection System (MPS) manages the hazards from high power photon beams and other hazards to ensure equipment protection on the booster synchrotron and storage ring. The system has a shutdown requirement, on a beam mis-steer of under 1 msec and has to manage in excess of a thousand interlocks. This is realised using a combination of bespoke hardware and programmable logic controllers. The MPS monitors a large number of interlock signals from diagnostics instrumentation, vacuum instrumentation, photon front ends and plant monitoring subsystems. Based on logic it can then remove the source of the energy to ensure protection of equipment. Depending on requirements, interlocks are managed on a Local or a Global basis. The Global system is structured as two layers, and supports fast- and slow-response-time interlock requirements. A Global MPS module takes the interlock permits for a given interlock circuit from each of the cells of the accelerator, and, subject to all interlocks being good, produces a permit to operate the source of energy: the RF amplifier for vessel protection and the PSU for magnet protection. The Local MPS module takes fast Interlock inputs from one cell of the Storage Ring or one quadrant of the Booster. Fast interlocks are those that must drop the beam in under 400 μsec (the maximum speed of the interlock) in the event of failure. EPIC provides the user interface to the MPS system

Reactor protection system design using micro-computers

International Nuclear Information System (INIS)

Fairbrother, D.B.

1977-01-01

Reactor Protection Systems for Nuclear Power Plants have traditionally been built using analog hardware. This hardware works quite well for single parameter trip functions; however, optimum protection against DNBR and KW/ft limits requires more complex trip functions than can easily be handled with analog hardware. For this reason, Babcock and Wilcox has introduced a Reactor Protection System, called the RPS-II, that utilizes a micro-computer to handle the more complex trip functions. This paper describes the design of the RPS-II and the operation of the micro-computer within the Reactor Protection System

Reactor protection system design using micro-computers

International Nuclear Information System (INIS)

Fairbrother, D.B.

1976-01-01

Reactor protection systems for nuclear power plants have traditionally been built using analog hardware. This hardware works quite well for single parameter trip functions; however, optimum protection against DNBR and KW/ft limits requires more complex trip functions than can easily be handled with analog hardware. For this reason, Babcock and Wilcox has introduced a Reactor Protection System, called the RPS-II, that utilizes a micro-computer to handle the more complex trip functions. The paper describes the design of the RPS-II and the operation of the micro-computer within the Reactor Protection System

Comparison, with regard to safety, between a hard-wired reactor protection system and a computerized protection system. Pt. 1

International Nuclear Information System (INIS)

Buettner, W.E.

1976-07-01

The study compares a conventional hard-wired dynamic reactor protection system with a computerized protection system. In the comparison, only the unequivocally safety-oriented protection actions are considered. In the first part, the different structures of both systems and the method of verification for their functional safety will be described. In the second part, the mean unavailability in case of demand for both systems under defined conditions will be determined. (orig.) [de

Management information system on radiation protection

Energy Technology Data Exchange (ETDEWEB)

Grossi, Pablo Andrade; Souza, Leonardo Soares de; Figueiredo, Geraldo Magela, E-mail: pabloag@cdtn.b, E-mail: lss@cdtn.b, E-mail: gmf@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

Considering the flux complexity and the multi source information of all radiation protection activities on nuclear organizations, an effective management information system based on technology, information and people is necessary to improve the safety on all processes and operations subjected to radiation risks. An effective management information system is an essential tool to highlight the strengths and weaknesses and identify behaviors and trends on the activities requiring radiation protection programs. Such kind of distinct knowledge is useful to reach an effective management and support the human decision-making on nuclear organization. This paper presents a management information system based on Brazilian directives and regulations on radiation protection. Due to its generic characteristics, this radiation protection control system can be implemented on any nuclear organization by reediting the non restricted parameters which could differ considering all facilities and laboratories expected on-site with diverse technologies applications. This system can be considered as a powerful tool applied on the continuous management of radiation protection activities on nuclear organizations and research institutes as well as for long term planning, not only indicating how the safety activities are going, but why they are not going as well as planned where that is the case. (author)

Management information system on radiation protection

International Nuclear Information System (INIS)

Grossi, Pablo Andrade; Souza, Leonardo Soares de; Figueiredo, Geraldo Magela

2011-01-01

Considering the flux complexity and the multi source information of all radiation protection activities on nuclear organizations, an effective management information system based on technology, information and people is necessary to improve the safety on all processes and operations subjected to radiation risks. An effective management information system is an essential tool to highlight the strengths and weaknesses and identify behaviors and trends on the activities requiring radiation protection programs. Such kind of distinct knowledge is useful to reach an effective management and support the human decision-making on nuclear organization. This paper presents a management information system based on Brazilian directives and regulations on radiation protection. Due to its generic characteristics, this radiation protection control system can be implemented on any nuclear organization by reediting the non restricted parameters which could differ considering all facilities and laboratories expected on-site with diverse technologies applications. This system can be considered as a powerful tool applied on the continuous management of radiation protection activities on nuclear organizations and research institutes as well as for long term planning, not only indicating how the safety activities are going, but why they are not going as well as planned where that is the case. (author)

An analytical solution describing the shape of a yield stress material subjected to an overpressure

DEFF Research Database (Denmark)

Hovad, Emil; Spangenberg, Jon; Larsen, P.

2016-01-01

as well as the spread length and height of the material when deformed in a box due to gravity. In the present work, the analytical solution is extended with the addition of an overpressure that acts over the entire body of the material. This extension enables finding the shape of a yield stress material......Many fluids and granular materials are able to withstand a limited shear stress without flowing. These materials are known as yields stress materials. Previously, an analytical solution was presented to quantify the yield stress for such materials. The yields stress is obtained based on the density...... with known density and yield stress when for instance deformed under water or subjected to a forced air pressure....

Advanced Protection & Service Restoration for FREEDM Systems

Science.gov (United States)

Singh, Urvir

A smart electric power distribution system (FREEDM system) that incorporates DERs (Distributed Energy Resources), SSTs (Solid State Transformers - that can limit the fault current to two times of the rated current) & RSC (Reliable & Secure Communication) capabilities has been studied in this work in order to develop its appropriate protection & service restoration techniques. First, a solution is proposed that can make conventional protective devices be able to provide effective protection for FREEDM systems. Results show that although this scheme can provide required protection but it can be quite slow. Using the FREEDM system's communication capabilities, a communication assisted Overcurrent (O/C) protection scheme is proposed & results show that by using communication (blocking signals) very fast operating times are achieved thereby, mitigating the problem of conventional O/C scheme. Using the FREEDM System's DGI (Distributed Grid Intelligence) capability, an automated FLISR (Fault Location, Isolation & Service Restoration) scheme is proposed that is based on the concept of 'software agents' & uses lesser data (than conventional centralized approaches). Test results illustrated that this scheme is able to provide a global optimal system reconfiguration for service restoration.

Reactor protection systems of 500 MWe PHWRs

Energy Technology Data Exchange (ETDEWEB)

Mallik, G; Kelkar, M G; Apte, Ravindra [C and I Group, Nuclear Power Corporation, Mumbai (India)

1997-03-01

The 500 MWe PHWR has two totally independent, diverse, fast acting shutdown system called Shutdown System 1 (SDS 1) and Shutdown System 2 (SDS 2). The trip generation circuitry of SDS 1 and SDS 2 are known as Reactor Protection System 1 (RPS 1) and Reactor Protection System 2 (RPS 2) respectively. Some of the features specific to 500 MWe reactors are Core Over Power Protection System (COPPS) based upon in core Self Powered Neutron Detector (SPND) signals, use of local two out of three coincidence logic and adoption of overlap testing for RPS 2, use of Fine Impulse Testing (FIT) in RPS 2, testing of the final control elements namely electro-magnetic clutch of individual Shutoff Rods (SRs) of SDS 1 and all the fast acting valves of SDS 2, etc. The two shutdown systems have totally separate sets of sensors and associated signal processing circuitry as well as physical arrangements. A separate computerised test and monitoring unit is used for each of the two shutdown systems. Use of Programmable Digital Comparator (PDC) unit exclusively for reactor protection systems, has been adopted. The capability of PDC unit is enhanced and communication links are provided for its integration in over all system. The paper describes the design features of reactor protection systems. (author). 3 refs., 7 figs., 3 tabs.

Exploitation questions regarding channel type reactors: water graphite channel reactors (operation, reconstruction, advantages and disadvantages)

International Nuclear Information System (INIS)

Chichindaev, D.A.

2001-01-01

An overview of up-grade of the RBMK-type reactors is given. I this paper the core design and core monitoring, pressure boundary integrity, RBMK basic design and safety improvements emergency core cooling system (ECCS) as well as reactor cavity overpressure protection system (RCOPS) are discussed

Controls and Machine Protection Systems

CERN Document Server

Carrone, E.

2016-01-01

Machine protection, as part of accelerator control systems, can be managed with a 'functional safety' approach, which takes into account product life cycle, processes, quality, industrial standards and cybersafety. This paper will discuss strategies to manage such complexity and the related risks, with particular attention to fail-safe design and safety integrity levels, software and hardware standards, testing, and verification philosophy. It will also discuss an implementation of a machine protection system at the SLAC National Accelerator Laboratory's Linac Coherent Light Source (LCLS).

Foundations for Protecting Renewable-Rich Distribution Systems.

Energy Technology Data Exchange (ETDEWEB)

Ellis, Abraham [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brahma, Sukumar [New Mexico State Univ., Las Cruces, NM (United States); Ranade, Satish [New Mexico State Univ., Las Cruces, NM (United States)

2016-11-01

High proliferation of Inverter Interfaced Distributed Energy Resources (IIDERs) into the electric distribution grid introduces new challenges to protection of such systems. This is because the existing protection systems are designed with two assumptions: 1) system is single-sourced, resulting in unidirectional fault current, and (2) fault currents are easily detectable due to much higher magnitudes compared to load currents. Due to the fact that most renewables interface with the grid though inverters, and inverters restrict their current output to levels close to the full load currents, both these assumptions are no longer valid - the system becomes multi-sourced, and overcurrent-based protection does not work. The primary scope of this study is to analyze the response of a grid-tied inverter to different faults in the grid, leading to new guidelines on protecting renewable-rich distribution systems.

ADVANCED WORKER PROTECTION SYSTEM

International Nuclear Information System (INIS)

Judson Hedgehock

2001-01-01

From 1993 to 2000, OSS worked under a cost share contract from the Department of Energy (DOE) to develop an Advanced Worker Protection System (AWPS). The AWPS is a protective ensemble that provides the user with both breathing air and cooling for a NIOSH-rated duration of two hours. The ensemble consists of a liquid air based backpack, a Liquid Cooling Garment (LCG), and an outer protective garment. The AWPS project was divided into two phases. During Phase 1, OSS developed and tested a full-scale prototype AWPS. The testing showed that workers using the AWPS could work twice as long as workers using a standard SCBA. The testing also provided performance data on the AWPS in different environments that was used during Phase 2 to optimize the design. During Phase 1, OSS also performed a life-cycle cost analysis on a representative clean up effort. The analysis indicated that the AWPS could save the DOE millions of dollars on D and D activities and improve the health and safety of their workers. During Phase 2, OSS worked to optimize the AWPS design to increase system reliability, to improve system performance and comfort, and to reduce the backpack weight and manufacturing costs. To support this design effort, OSS developed and tested several different generations of prototype units. Two separate successful evaluations of the ensemble were performed by the International Union of Operation Engineers (IUOE). The results of these evaluations were used to drive the design. During Phase 2, OSS also pursued certifying the AWPS with the applicable government agencies. The initial intent during Phase 2 was to finalize the design and then to certify the system. OSS and Scott Health and Safety Products teamed to optimize the AWPS design and then certify the system with the National Institute of Occupational Health and Safety (NIOSH). Unfortunately, technical and programmatic difficulties prevented us from obtaining NIOSH certification. Despite the inability of NIOSH to certify

ADVANCED WORKER PROTECTION SYSTEM

Energy Technology Data Exchange (ETDEWEB)

Judson Hedgehock

2001-03-16

From 1993 to 2000, OSS worked under a cost share contract from the Department of Energy (DOE) to develop an Advanced Worker Protection System (AWPS). The AWPS is a protective ensemble that provides the user with both breathing air and cooling for a NIOSH-rated duration of two hours. The ensemble consists of a liquid air based backpack, a Liquid Cooling Garment (LCG), and an outer protective garment. The AWPS project was divided into two phases. During Phase 1, OSS developed and tested a full-scale prototype AWPS. The testing showed that workers using the AWPS could work twice as long as workers using a standard SCBA. The testing also provided performance data on the AWPS in different environments that was used during Phase 2 to optimize the design. During Phase 1, OSS also performed a life-cycle cost analysis on a representative clean up effort. The analysis indicated that the AWPS could save the DOE millions of dollars on D and D activities and improve the health and safety of their workers. During Phase 2, OSS worked to optimize the AWPS design to increase system reliability, to improve system performance and comfort, and to reduce the backpack weight and manufacturing costs. To support this design effort, OSS developed and tested several different generations of prototype units. Two separate successful evaluations of the ensemble were performed by the International Union of Operation Engineers (IUOE). The results of these evaluations were used to drive the design. During Phase 2, OSS also pursued certifying the AWPS with the applicable government agencies. The initial intent during Phase 2 was to finalize the design and then to certify the system. OSS and Scott Health and Safety Products teamed to optimize the AWPS design and then certify the system with the National Institute of Occupational Health and Safety (NIOSH). Unfortunately, technical and programmatic difficulties prevented us from obtaining NIOSH certification. Despite the inability of NIOSH to certify

Explosion-protected electric heating systems

Energy Technology Data Exchange (ETDEWEB)

Elsner, H

1984-02-01

Different constructions of explosion-protected heating systems are described concerning the different types of protection, the service conditions, the installation and the surveillance devices. Interpretations and regulations derived from the VDE Standards are discussed and their relation to the European Standards EN 50014 ... 50020 is considered in a survey.

The protection system to Brazilian Nuclear Program

International Nuclear Information System (INIS)

Andreuzza, Mario Giussepp Santezzi Bertottelli

1997-01-01

The Sistema de Protecao ao Programa Nuclear Brasileiro-SIPRON (Protection System to Brazilian Nuclear Program) was established in 1980. It is intended to accomplish in only one system, all the actions related to security and protection for Nuclear Facilities in Brazil. The author presents in detail the protection system SIPRON, describing the system structure and organization, the functions and obligations of the system involved main organizations, as well as, the system operation and behaviour during an postulated occurrence of a nuclear emergency. It is also described an Exercise that happened in June of 1997 at the Nuclear Power Plant (NPP) Angra I, after two simulated tests in December of 1996 and April of 1997. The NPP Angra I Emergency Plan Exercise was a good opportunity to test the SIPRON structure and preparedness program. It was verified, included by International Atomic Energy Agency observers, the system involved organizations effectiveness and the procedures efficacy to protect the public and the environmental. Finally, it is shown the SIPRON activities of routine, the system obstacles and the expected future performances. (author)

The APS machine protection system (MPS)

Energy Technology Data Exchange (ETDEWEB)

Fuja, R.; Berg, B.; Arnold, N. [and others

1996-08-01

The machine protection system (MPS) that protects the APS storage ring vacuum chamber from x-ray beams, is active. There are over 650 sensors monitored and networked through the MPS system. About the same number of other process variables are monitored by the much slower EPICS control system, which also has an input to the rf abort chain. The MPS network is still growing with the beam position limits detection system coming on-line. The network configuration, along with a limited description of individual subsystems, is presented.

The APS machine protection system (MPS)

International Nuclear Information System (INIS)

Fuja, R.; Berg, B.; Arnold, N.

1996-01-01

The machine protection system (MPS) that protects the APS storage ring vacuum chamber from x-ray beams, is active. There are over 650 sensors monitored and networked through the MPS system. About the same number of other process variables are monitored by the much slower EPICS control system, which also has an input to the rf abort chain. The MPS network is still growing with the beam position limits detection system coming on-line. The network configuration, along with a limited description of individual subsystems, is presented

46 CFR 154.1110 - Areas protected by system.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Areas protected by system. 154.1110 Section 154.1110... Firefighting § 154.1110 Areas protected by system. Each water spray system must protect: (a) All cargo tank... valves essential to cargo flow; (f) Each boundary facing the cargo area of each superstructure that...

Modern thyratron crowbar protection systems

International Nuclear Information System (INIS)

Judd, D.A.; Kettle, L.J.; Menown, H.; Newton, B.P.; Nicholls, N.S.; Sheldrake, R.

1992-01-01

Two thyratron crowbar systems for high-power klystrons used in linear accelerators are described. The first, contained in an oil filled tank, is a complete system to protect a klystron powered from a 100-kV, 20-A d.c. supply. In the second system a CX1722 glass thyratron, operating in air, has been retrofitted to a test equipment, in place of a spark gap, to protect an Inductive Output Tube (IOT). An important parameter in the choice of the crowbar thyratron is the total coulombs to be switched. Measurements of these follow-on currents are presented. (R.P.) 4 refs.; 10 figs

Standpipe systems for fire protection

CERN Document Server

Isman, Kenneth E

2017-01-01

This important new manual goes beyond the published NFPA standards on installation of standpipe systems to include the rules in the International Building Code, municipal fire codes, the National Fire Code of Canada, and information on inspection, testing, and maintenance of standpipe systems. Also covered are the interactions between standpipe and sprinkler systems, since these important fire protection systems are so frequently installed together. Illustrated with design examples and practical applications to reinforce the learning experience, this is the go-to reference for engineers, architects, design technicians, building inspectors, fire inspectors, and anyone that inspects, tests or maintains fire protection systems. Fire marshals and plan review authorities that have the responsibility for reviewing and accepting plans and hydraulic calculations for standpipe systems are also an important audience, as are firefighters who actually use standpipe systems. As a member of the committees responsible for s...

Aging assessment for active fire protection systems

International Nuclear Information System (INIS)

Ross, S.B.; Nowlen, S.P.; Tanaka, T.

1995-06-01

This study assessed the impact of aging on the performance and reliability of active fire protection systems including both fixed fire suppression and fixed fire detection systems. The experience base shows that most nuclear power plants have an aggressive maintenance and testing program and are finding degraded fire protection system components before a failure occurs. Also, from the data reviewed it is clear that the risk impact of fire protection system aging is low. However, it is assumed that a more aggressive maintenance and testing program involving preventive diagnostics may reduce the risk impact even further

Compaction of TOC-rich shales due to kerogen conversion. Implications for fluid flow and overpressure

International Nuclear Information System (INIS)

Hanebeck, D.; Krooss, B.M.; Leythaeuser, D.

1998-01-01

TOC-rich shales (10% TOC) have been artificially matured at temperatures between 200 and 350 deg C under controlled axial stress (20 - 40 MPa) for up to 350 hours. The volume change of the cylindrical samples was monitored continuously throughout the experiment. The performed experiments showed that the compaction associated with the thermal decomposition of the kerogen is significantly larger under hydrous than under dry pyrolysis conditions. This observation points at an important role of water in the conversion of kerogen. Semi quantitative permeability tests indicated that sample permeability had decreased at least one order of magnitude after the compaction pyrolysis experiments. This permeability reduction in combination with the observed compaction is the most probable mechanism for overpressure formation in TOC-rich source rock sequences. (author)

A New Protection System for Islanding Detection in LV Distribution Systems

Directory of Open Access Journals (Sweden)

Anna Rita Di Fazio

2015-04-01

Full Text Available The growth of penetration of Distributed Generators (DGs is increasing the risk of unwanted islanded operation in Low Voltage (LV distribution systems. In this scenario, the existing anti-islanding protection systems, installed at the DG premises and based on classical voltage and frequency relays, are no longer effective, especially in the cases of islands characterized by a close match between generation and load. In this paper, a new protection system for islanding detection in LV distribution systems is proposed. The classical voltage and frequency relays in the DG interface protections are enriched with an innovative Smart Islanding Detector, which adopts a new passive islanding detection method. The aim is to keep the advantages of the classical relays while overcoming the problem of their limited sensitivity in detecting balanced islands. In the paper, to define the requirements of the anti-islanding protection system, the events causing the islanded operation of the LV distribution systems are firstly identified and classified. Then, referring to proposed protection system, its architecture and operation are described and, eventually, its performance is analyzed and validated by experimental laboratory tests, carried out with a hardware-in-the-loop technique.

A protection system for picosecond accelerator

International Nuclear Information System (INIS)

Cao Hongping; Chinese Academy of Sciences, Beijing; Chen Huanguang; Xu Ruinian; Tang Junlong; Li Deming

2006-01-01

A personnel and machine protection system for the picosecond accelerator has been built. The key of the system is to send on/off of three triggering signals which are those of electron gun, 2856 MHz and 476 MHz, respectively, to ensure the safety of users and the accelerator. This paper describes the emergencies interlocked by ADAM5511 and timing trigger processor, and some secondary functions which improve the efficiency of the protection system completed in upper layer software. (authors)

An improved probit method for assessment of domino effect to chemical process equipment caused by overpressure.

Science.gov (United States)

Mingguang, Zhang; Juncheng, Jiang

2008-10-30

Overpressure is one important cause of domino effect in accidents of chemical process equipments. Damage probability and relative threshold value are two necessary parameters in QRA of this phenomenon. Some simple models had been proposed based on scarce data or oversimplified assumption. Hence, more data about damage to chemical process equipments were gathered and analyzed, a quantitative relationship between damage probability and damage degrees of equipment was built, and reliable probit models were developed associated to specific category of chemical process equipments. Finally, the improvements of present models were evidenced through comparison with other models in literatures, taking into account such parameters: consistency between models and data, depth of quantitativeness in QRA.

Design of the US-CRBRP sodium/water reaction pressure relief system

International Nuclear Information System (INIS)

Kruger, G.B.; Murdock, T.B.; Rodwell, E.; Sane, J.O.

1976-01-01

Protection against intermediate sodium system overpressure from the sodium/water reaction associated with large leaks within the CRBRP Steam Generators is provided by the sodium/water reaction pressure relief system (SWRPRS). This system consists of rupture disks connected to the intermediate sodium piping adjacent to the inlet to the superheater and outlet from the evaporator modules. The rupture discs relieve into piping that leads to reaction produce separator tanks, which in turn are vented to a centrifugal separator and flare stack arranged to burn hydrogen gas exhausting into the atmosphere. Analyses have been conducted using the TRANSWRAP Computer Code to predict the system pressures and flow rates during the large leak event. Experimental tests to be conducted in the large leak test rig (LLTR) will be used to confirm the analysis techniques used in the design

Advanced worker protection system

Energy Technology Data Exchange (ETDEWEB)

Caldwell, B.; Duncan, P.; Myers, J. [Oceaneering Space Systems, Houston, TX (United States)

1995-10-01

The Department of Energy (DOE) is in the process of defining the magnitude and diversity of Decontamination and Decommissioning (D&D) obligations at its numerous sites. The DOE believes that existing technologies are inadequate to solve many challenging problems such as how to decontaminate structures and equipment cost effectively, what to do with materials and wastes generated, and how to adequately protect workers and the environment. Preliminary estimates show a tremendous need for effective use of resources over a relatively long period (over 30 years). Several technologies are being investigated which can potentially reduce D&D costs while providing appropriate protection to DOE workers. The DOE recognizes that traditional methods used by the EPA in hazardous waste site clean up activities are insufficient to provide the needed protection and worker productivity demanded by DOE D&D programs. As a consequence, new clothing and equipment which can adequately protect workers while providing increases in worker productivity are being sought for implementation at DOE sites. This project describes the development of an Advanced Worker Protection System (AWPS) which will include a life-support backpack with liquid air for cooling and as a supply of breathing gas, protective clothing, respirators, communications, and support equipment.

Advanced worker protection system

International Nuclear Information System (INIS)

Caldwell, B.; Duncan, P.; Myers, J.

1995-01-01

The Department of Energy (DOE) is in the process of defining the magnitude and diversity of Decontamination and Decommissioning (D ampersand D) obligations at its numerous sites. The DOE believes that existing technologies are inadequate to solve many challenging problems such as how to decontaminate structures and equipment cost effectively, what to do with materials and wastes generated, and how to adequately protect workers and the environment. Preliminary estimates show a tremendous need for effective use of resources over a relatively long period (over 30 years). Several technologies are being investigated which can potentially reduce D ampersand D costs while providing appropriate protection to DOE workers. The DOE recognizes that traditional methods used by the EPA in hazardous waste site clean up activities are insufficient to provide the needed protection and worker productivity demanded by DOE D ampersand D programs. As a consequence, new clothing and equipment which can adequately protect workers while providing increases in worker productivity are being sought for implementation at DOE sites. This project describes the development of an Advanced Worker Protection System (AWPS) which will include a life-support backpack with liquid air for cooling and as a supply of breathing gas, protective clothing, respirators, communications, and support equipment

The Philosophy of the New Radiation Protection System

Energy Technology Data Exchange (ETDEWEB)

Wikman, P.

2004-07-01

The International Commission on Radiological Protection has proposed a new philosophy of radiation protection. An important component in the proposed system of protection is the principle ''If the individual is sufficiently protected from a source, then society is also protected from that source''. This principle is here analysed and found to be subject to several problems. The principle reflects the controversial ethical position that the likely harm to several people can be ignored as long as the individual risk is small. The ICRP states that the new system involves a change from a previous utilitarian ethics to an individual-oriented philosophy. It is argued that a rights-based or a duty-based ethic requires a more risk avert interpretation of when an individual is sufficiently protected than what the proposal suggests. It is concluded that the proposed principle contradicts the other important principle in the new system - the optimisation principle. Due to these problems it is suggested that the ICRP ought to discard the proposed principle from the new system of radiation protection. (Author) 7 refs.

The Philosophy of the New Radiation Protection System

International Nuclear Information System (INIS)

Wikman, P.

2004-01-01

The International Commission on Radiological Protection has proposed a new philosophy of radiation protection. An important component in the proposed system of protection is the principle I f the individual is sufficiently protected from a source, then society is also protected from that source . This principle is here analysed and found to be subject to several problems. The principle reflects the controversial ethical position that the likely harm to several people can be ignored as long as the individual risk is small. The ICRP states that the new system involves a change from a previous utilitarian ethics to an individual-oriented philosophy. It is argued that a rights-based or a duty-based ethic requires a more risk avert interpretation of when an individual is sufficiently protected than what the proposal suggests. It is concluded that the proposed principle contradicts the other important principle in the new system - the optimisation principle. Due to these problems it is suggested that the ICRP ought to discard the proposed principle from the new system of radiation protection. (Author) 7 refs

Televison assessment and identification system for the plutonium protection system

International Nuclear Information System (INIS)

Greenwoll, D.A.

1979-02-01

This report covers the selection, description, and use of the components comprising the Television Assessment and Identification System in the Hanford Plutonium Protection System. This work was sponsored by the Department of Energy/Office of Safeguards and Security (DOE/OSS) as part of the overall Sandia Fixed Facility Physical Protection Program

Dynamic structural response of reactor-core subassemblies (hexcans) due to accident overpressurization

International Nuclear Information System (INIS)

Pfeiffer, P.A.; Kulak, R.F.

1993-01-01

This paper presents a two-dimensional structural analysis for the evaluation of a single core subassembly due to internal overpressure associated with possible failure of fuel pins having high fission gas plenum pressure. Structural models are developed for the subassemblies and their surroundings with emphasis on the critical physical aspects of the problem. With these models the strains, deformations and the extent of permanent damage (plastic strain) to the subassemblies can be assessed. The nonlinear structural analyses was performed with a finite element program called STRAW (Structural Transient Response of Assembly Wrappers). This finite element program is applicable to nonlinear large displacement problems. The results of this study indicate that the permanent deformation (damage) is strongly influenced by the rise time (time to reach peak pressure) of the pressure pulse and the pressure in the fuel pin. The rise time is influenced by the opening time of the flow path for release of gas from the fuel pin plenum. Several examples are illustrated with various rise times and pressure magnitudes and the resulting permanent deformation of the hexcan wall. (author)

Dynamic structural response of reactor-core subassemblies (hexcans) due to accident overpressurization

International Nuclear Information System (INIS)

Pfeiffer, P.A.; Kulak, R.F.

1993-01-01

This paper presents a two-dimensional structural analysis for the evaluation of a single core subassembly due to internal overpressure associated with possible failure of fuel pins having high fission gas plenum pressure. Structural models are developed for the subassemblies and their surroundings with emphasis on the critical physical aspects of the problem. With these models the strains, deformations and the extent of permanent damage (plastic strain) to the subassemblies can be assessed. The nonlinear structural analyses was performed with a finite element program called STRAW (Structural Transient Response of Assembly Wrappers). This finite element program is applicable to nonlinear large displacement problems. The results of this study indicate that the permanent deformation (damage) is strongly influenced by the rise time (time to reach peak pressure) of the pressure pulse and the pressure in the fuel pin. The rise time is influenced by the opening time of the flow path for release of gas from the fuel pin plenum. Several examples are illustrated with various rise times and pressure magnitudes and the resulting permanent deformation of the hexcan wall

Establishing an Information Security System related to Physical Protection

International Nuclear Information System (INIS)

Jang, Sung Soon; Yoo, Ho Sik

2009-01-01

A physical protection system (PPS) integrates people, procedures and equipment for the protection of assets or facilities against theft, sabotage or other malevolent attacks. In the physical protection field, it is important the maintain confidentiality of PPS related information, such as the alarm system layout, detailed maps of buildings, and guard schedules. In this abstract, we suggest establishing a methodology for an information security system. The first step in this methodology is to determine the information to protect and possible adversaries. Next, system designers should draw all possible paths to the information and arrange appropriate protection elements. Finally he/she should analyze and upgrade their information security system

Machine Protection System response in 2011

CERN Document Server

Zerlauth, M; Wenninger, J

2012-01-01

The performance of the machine protection system during the 2011 run is summarized in this paper. Following an analysis of the beam dump causes in comparison to the previous 2010 run, special emphasis will be given to analyse events which risked to exposed parts of the machine to damage. Further improvements and mitigations of potential holes in the protection systems as well as in the change management will be evaluated along with their impact on the 2012 run. The role of the restricted Machine Protection Panel ( rMPP ) during the various operational phases such as commissioning, the intensity ramp up and Machine Developments is being discussed.

Measured air overpressures, soil-particle pressures, and slumps during the pre-ASIAGO U2Ar stemming experiment

Energy Technology Data Exchange (ETDEWEB)

Freynik, H.S. Jr.; Roach, D.R.; Dittbenner, G.R.

1978-01-04

On November 15, 1976, Lawrence Livermore Laboratory completed its first comprehensive stemming experiment for measuring downhole parameters while varying fill material and rate. Stemming can be defined as backfilling a hole in which a device has been placed to prevent leakage of radioactive materials or gases to the surface. A computer code is being developed for stemming operations, and this experiment was designed to measure parameters under different stemming conditions so the code could be verified and modified. The experiment was conducted in the lower half of a steel-cased, 4-ft-diam, 2000-ft-deep hole at Nevada Test Site. The two stemming materials used in the experiment, Overton sand and LLL II mix, were tested at three fill rates. Significant results of this experiment included successful measurement of downhole air overpressures, vertical and horizontal soil-particle pressures, and temperature. Vertical soil-particle pressures were higher than expected. All surface measurements were valid. The slump-displacement measurements system provided a timing mark to indicate the occurrence of a slump. A major slump occurred on the third day of stemming; a minor slump occurred on the fourth day.

Measured air overpressures, soil-particle pressures, and slumps during the pre-ASIAGO U2Ar stemming experiment

International Nuclear Information System (INIS)

Freynik, H.S. Jr.; Roach, D.R.; Dittbenner, G.R.

1978-01-01

On November 15, 1976, Lawrence Livermore Laboratory completed its first comprehensive stemming experiment for measuring downhole parameters while varying fill material and rate. Stemming can be defined as backfilling a hole in which a device has been placed to prevent leakage of radioactive materials or gases to the surface. A computer code is being developed for stemming operations, and this experiment was designed to measure parameters under different stemming conditions so the code could be verified and modified. The experiment was conducted in the lower half of a steel-cased, 4-ft-diam, 2000-ft-deep hole at Nevada Test Site. The two stemming materials used in the experiment, Overton sand and LLL II mix, were tested at three fill rates. Significant results of this experiment included successful measurement of downhole air overpressures, vertical and horizontal soil-particle pressures, and temperature. Vertical soil-particle pressures were higher than expected. All surface measurements were valid. The slump-displacement measurements system provided a timing mark to indicate the occurrence of a slump. A major slump occurred on the third day of stemming; a minor slump occurred on the fourth day

Control rod blow out protection system

International Nuclear Information System (INIS)

Dietrich, J.R.; Flinn, W.S.; Groves, M.D.

1979-01-01

An absorber element blow-out protection system for a nuclear reactor having a pressure vessel through which a coolant is circulated. The blow-out protection system includes devices which hydraulically couple groups of guide tubes in which the absorber elements move, the coupling devices limiting coolant lift flow rate to a level commensurate with the raising of individual absorber elements but insufficient to raise a plurality of absorber elements simultaneously

Evaluation of several corrosion protective coating systems on aluminum

Science.gov (United States)

Higgins, R. H.

1981-01-01

A study of several protective coating systems for use on aluminum in seawater/seacoast environments was conducted to review the developments made on protective coatings since early in the Space Shuttle program and to perform comparative studies on these coatings to determine their effectiveness for providing corrosion protection during exposure to seawater/seacoast environments. Panels of 2219-T87 aluminum were coated with 21 different systems and exposed to a 5 percent salt spray for 4000 hr. Application properties, adhesion measurements, heat resistance and corrosion protection were evaluated. For comparative studies, the presently specified Bostik epoxy system used on the SRB structures was included. Results of these tests indicate four systems with outstanding performance and four additional systems with protection almost as good. These systems are based on a chromated pretreatment, a chromate epoxy primer, and a polyurethane topcoat. Consideration for one of these systems should be included for those applications where superior corrosion protection for aluminum surfaces is required.

Incipient fault detection and power system protection for spaceborne systems

Science.gov (United States)

Russell, B. Don; Hackler, Irene M.

1987-01-01

A program was initiated to study the feasibility of using advanced terrestrial power system protection techniques for spacecraft power systems. It was designed to enhance and automate spacecraft power distribution systems in the areas of safety, reliability and maintenance. The proposed power management/distribution system is described as well as security assessment and control, incipient and low current fault detection, and the proposed spaceborne protection system. It is noted that the intelligent remote power controller permits the implementation of digital relaying algorithms with both adaptive and programmable characteristics.

The information protection level assessment system implementation

Science.gov (United States)

Trapeznikov, E. V.

2018-04-01

Currently, the threat of various attacks increases significantly as automated systems become more widespread. On the basis of the conducted analysis the information protection level assessment system establishing objective was identified. The paper presents the information protection level assessment software implementation in the information system by applying the programming language C #. In conclusions the software features are identified and experimental results are represented.

Problems of safety and protection posed during overpressures in radioactive waste incinerator combustion chambers

International Nuclear Information System (INIS)

Chevalier, G.; Caramelle, D.

1987-01-01

The incineration of radioactive spent fuel is a method of preserving these wastes offering a substantial reduction in volume (from 20 to 50), and the solid residue (ash, etc.) can be packaged and stored more safely than the initial wastes. However, these advantages should not be acquired to the detriment of safety and protection of personnel and of the environment during and after operation. Our recommendations are aimed to define the conditions to be satisfied so that the equipment to be constructed, as well as their method of use: - ensure the correct operation of the installation under the stipulated conditions - limit the consequences of an incident with respect to the installations, the personnel and the environment

Blast overpressure and fallout radiation dose models for casualty assessment and other purposes. Rev. ed.

International Nuclear Information System (INIS)

Bentley, P.R.

1981-12-01

The determination of blast overpressures and fallout radiation doses at points on a sufficiently fine grid, for any part or for the whole of the UK, and for any postulated attack, is an essential element in the systematic assessment of casualties, the estimation of numbers of homeless, and the evaluation of life-saving measures generally. Models are described which provide the required blast and dose values and which are intended to supersede existing models which were introduced in 1971. The factors which affect blast and, more particularly, dose values are discussed, and the way in which various factors are modelled is described. The models are incorporated into separate computer programs which are described, the outputs of which are stored on magnetic tape for subsequent use as required. (author)

Annexes to the lecture on reactor protection system including engineered features actuation system

International Nuclear Information System (INIS)

Palmaers, W.

1982-01-01

The present paper deals with the fundamentals for a reactor protection system and discusses the following topics: - System lay-out - Analog measured data acquisition - Analog measured data processing - Limit value generation and logical gating - Procesing of the reactor protection actuation signals - Decoupling of the reactor protection system - Mechanical lay-out - Monitoring system and - Emergency control station. (orig./RW)

Operational test report - Project W-320 cathodic protection systems

International Nuclear Information System (INIS)

Bowman, T.J.

1998-01-01

Washington Administrative Code (WAC) 173-303-640 specifies that corrosion protection must be designed into tank systems that treat or store dangerous wastes. Project W-320, Waste Retrieval Sluicing System (WRSS), utilizes underground encased waste transfer piping between tanks 241-C-106 and 241-AY-102. Corrosion protection is afforded to the encasements of the WRSS waste transfer piping through the application of earthen ionic currents onto the surface of the piping encasements. Cathodic protection is used in conjunction with the protective coatings that are applied upon the WRSS encasement piping. WRSS installed two new two rectifier systems (46 and 47) and modified one rectifier system (31). WAC 173-303-640 specifies that the proper operation of cathodic protection systems must be confirmed within six months after initial installation. The WRSS cathodic protection systems were energized to begin continuous operation on 5/5/98. Sixteen days after the initial steady-state start-up of the WRSS rectifier systems, the operational testing was accomplished with procedure OTP-320-006 Rev/Mod A-0. This operational test report documents the OTP-320-006 results and documents the results of configuration testing of integrated piping and rectifier systems associated with the W-320 cathodic protection systems

Validation of reactor core protection system

International Nuclear Information System (INIS)

Lee, Sang-Hoon; Bae, Jong-Sik; Baeg, Seung-Yeob; Cho, Chang-Ho; Kim, Chang-Ho; Kim, Sung-Ho; Kim, Hang-Bae; In, Wang-Kee; Park, Young-Ho

2008-01-01

Reactor COre Protection System (RCOPS), an advanced core protection calculator system, is a digitized one which provides core protection function based on two reactor core operation parameters, Departure from Nucleate Boiling Ratio (DNBR) and Local Power Density (LPD). It generates a reactor trip signal when the core condition exceeds the DNBR or LPD design limit. It consists of four independent channels adapted a two-out-of-four trip logic. System configuration, hardware platform and an improved algorithm of the newly designed core protection calculator system are described in this paper. One channel of RCOPS was implemented as a single channel facility for this R and D project where we performed final integration software testing. To implement custom function blocks, pSET is used. Software test is performed by two methods. The first method is a 'Software Module Test' and the second method is a 'Software Unit Test'. New features include improvement of core thermal margin through a revised on-line DNBR algorithm, resolution of the latching problem of control element assembly signal and addition of the pre-trip alarm generation. The change of the on-line DNBR calculation algorithm is considered to improve the DNBR net margin by 2.5%-3.3%. (author)

Electrical Power Systems Protection and Interdependencies with ICT

OpenAIRE

Milis, George; Kyriakides, Elias; Hadjiantonis, Antonis

2017-01-01

The present chapter discusses the issue of protection of the electrical power systems, addressing all dimensions, from the need of protection to the identified faults and disturbances to the available protection schemes and further considerations, also looking at the challenges brought by recognizing the interdependent nature of the today’s electrical power systems.

Fire protection in ventilation systems and in case of fire operating ventilation systems

International Nuclear Information System (INIS)

Zitzelsberger, J.

1983-01-01

The fire risks in ventilation systems are discussed. It follows a survey of regulations on fire prevention and fire protection in ventilation systems and smoke and heat exhaust systems applicable to nuclear installations in the Federal Republic of Germany. Fire protection concepts for normal systems and for systems operating also in case of fire will be given. Several structural elements for fire protection in those systems will be illustrated with regard to recent research findings

Angle Control-Based Multi-Terminal Out-of-Step Protection System

OpenAIRE

Antans Sauhats; Andrejs Utans; Dmitrijs Antonovs; Andrejs Svalovs

2017-01-01

From time to time a sequence of unexpected and overlapping contingencies may lead to power system angular instability and even blackouts if not addressed adequately by means of an out-of-step (OOS) protection system. The motivation of the paper is an attempt to develop a workable prototype of the OOS protection system. The deficiencies of the protection currently used in the Latvian Power System network are highlighted and a new protection structure is proposed. The protection system comprise...

DLP-systems: Protection from Insiders

Directory of Open Access Journals (Sweden)

Ivan Sergeevich Boridko

2013-02-01

Full Text Available In the paper the necessity of further introduction of modern systems of information protection against internal leaks, including DLP-systems, is justified. The issues of development of training specialists in the field of information security is considered.

14 CFR 25.954 - Fuel system lightning protection.

Science.gov (United States)

2010-01-01

... AIRCRAFT AIRWORTHINESS STANDARDS: TRANSPORT CATEGORY AIRPLANES Powerplant Fuel System § 25.954 Fuel system lightning protection. The fuel system must be designed and arranged to prevent the ignition of fuel vapor... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Fuel system lightning protection. 25.954...

14 CFR 27.954 - Fuel system lightning protection.

Science.gov (United States)

2010-01-01

... AIRCRAFT AIRWORTHINESS STANDARDS: NORMAL CATEGORY ROTORCRAFT Powerplant Fuel System § 27.954 Fuel system lightning protection. The fuel system must be designed and arranged to prevent the ignition of fuel vapor... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Fuel system lightning protection. 27.954...

14 CFR 29.954 - Fuel system lightning protection.

Science.gov (United States)

2010-01-01

... AIRCRAFT AIRWORTHINESS STANDARDS: TRANSPORT CATEGORY ROTORCRAFT Powerplant Fuel System § 29.954 Fuel system lightning protection. The fuel system must be designed and arranged to prevent the ignition of fuel vapor... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Fuel system lightning protection. 29.954...

Kevlar Vest Protection against Blast Overpressure Brain Injury: Systemic Contributions to Injury Etiology

Science.gov (United States)

2015-07-01

et al ., 1973; Saivin and Houin, 1988 ). Similar to its tetracycline analogs, the side...neuroinflammation and elevated CORT levels are known inhibitors of hippocampal de novo neurogen- esis (Cameron and Gould , 1994; Yu et al ., 2004; Montaron et al ...memory problems, increased anxi- ety, and depression (Gentilini et al ., 1985; Schoenhuber and Gentilini, 1988 ; Ponsford et al ., 1995). Blast

14 CFR 23.954 - Fuel system lightning protection.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Fuel system lightning protection. 23.954... Fuel System § 23.954 Fuel system lightning protection. The fuel system must be designed and arranged to prevent the ignition of fuel vapor within the system by— (a) Direct lightning strikes to areas having a...

Advanced nuclear control and protection system ANCAP-80

International Nuclear Information System (INIS)

Asai, Takashi; Okano, Michihiko; Ishibashi, Kengo; Hasegawa, Masakoto; Fukuda, Hiroyoshi; Hosomichi, Renichi.

1983-01-01

Advanced reactor protection systems were developed to improve operational reliability and availability and to ease the burden of operators of Mitsubishi PWR Nuclear Power Stations. (Called ANCAP-80; Advanced Nuclear Control And Protection System) For the PWR plants now being planned and in future plans, Mitsubishi will adopt these systems with the following functional features; (1) Four channel protection logic, (2) Automatic bypass logic, (3) Automatic test provision, (4) Optical isolators. (author)

A protection system of low temperature thermo-supply nuclear reactor

International Nuclear Information System (INIS)

Jiang Binsen

1988-09-01

A Protection system of low temperature thermo-supply nuclear reactor is introduced. It is the first protection system, which is designed and manufactred on the basis of Chinese National Standard GB 4083-83 'General Safety Principle of Nuclear Reactor Protection System', to be considered under the circumstances of industry level in China. Advantages of the protection system are as follows: 1)The single failure criteria can fully be fulfilled by the protection system. 2) On-line testing system can be used for detecting all of failure components and quick identifying the failure points in the system. 3) It is convenience for maintenacnce of the system. To complete this project is very important and helpful in promoting the development of the protection system and safety operation of nuclear reactor in China

Reactor protection system including engineered features actuation system

International Nuclear Information System (INIS)

Palmaers, W.

1982-01-01

The safety concept requires to ensure that - the reactor protection system - the active engineered safeguard - and the necessary auxiliary systems are so designed and interfaced in respect of design and mode of action that, in the event of single component failure reliable control of the consequences of accidents remains ensured at all times and that the availability of the power plant is not limited unnecessarily. In order to satisfy these requirements due, importance was attached to a consistent spacial separation of the mutually redundant subsystems of the active safety equipment. The design and layout of the reactor protection system, of the power supply (emergency power supply), and of the auxiliary systems important from the safety engineering point of view, are such that their subsystems also largely satisfy the requirements of independence and spacial separation. (orig./RW)

Programmed system for nuclear power plant protection

International Nuclear Information System (INIS)

Jover, Pierre.

1980-06-01

The progress in the field of microprocessors and large scale integration circuits, have incited to introduce this new technologies into nuclear power plant protection system. The hardware and software design principles are briefly listed; then, a quad-redundant protection system for 1300 MWe PWR, developed in France is described [fr

NSTX Protection And Interlock Systems For Coil And Powers Supply Systems

International Nuclear Information System (INIS)

Zhao, X.; Ramakrishnan, S.; Lawson, J.; Neumeyer, C.; Marsala, R.; Schneider, H.

2009-01-01

NSTX at Princeton Plasma Physics Laboratory (PPPL) requires sophisticated plasma positioning control system for stable plasma operation. TF magnetic coils and PF magnetic coils provide electromagnetic fields to position and shape the plasma vertically and horizontally respectively. NSTX utilizes twenty six coil power supplies to establish and initiate electromagnetic fields through the coil system for plasma control. A power protection and interlock system is utilized to detect power system faults and protect the TF coils and PF coils against excessive electromechanical forces, overheating, and over current. Upon detecting any fault condition the power system is restricted, and it is either prevented from initializing or suppressed to de-energize coil power during pulsing. Power fault status is immediately reported to the computer system. This paper describes the design and operation of NSTX's protection and interlocking system and possible future expansion.

System and method for quench protection of a superconductor

Science.gov (United States)

Huang, Xianrui; Sivasubramaniam, Kiruba Haran; Bray, James William; Ryan, David Thomas

2008-03-11

A system and method for protecting a superconductor from a quench condition. A quench protection system is provided to protect the superconductor from damage due to a quench condition. The quench protection system comprises a voltage detector operable to detect voltage across the superconductor. The system also comprises a frequency filter coupled to the voltage detector. The frequency filter is operable to couple voltage signals to a control circuit that are representative of a rise in superconductor voltage caused by a quench condition and to block voltage signals that are not. The system is operable to detect whether a quench condition exists in the superconductor based on the voltage signal received via the frequency filter and to initiate a protective action in response.

Digital signal processing in power system protection and control

CERN Document Server

Rebizant, Waldemar; Wiszniewski, Andrzej

2011-01-01

Digital Signal Processing in Power System Protection and Control bridges the gap between the theory of protection and control and the practical applications of protection equipment. Understanding how protection functions is crucial not only for equipment developers and manufacturers, but also for their users who need to install, set and operate the protection devices in an appropriate manner. After introductory chapters related to protection technology and functions, Digital Signal Processing in Power System Protection and Control presents the digital algorithms for signal filtering, followed

A New Physical Protection System Design and Evaluation Process

Energy Technology Data Exchange (ETDEWEB)

Lim, Heoksoon; Kim, Myungsu; Bae, Yeongkyoung; Na, Janghwan [KHNP-CRI, Daejeon (Korea, Republic of)

2014-10-15

International Atomic Energy Agency(IAEA) had established security-related department and has been strengthening security measures against possible sabotage. IAEA enforces the recommendations for the physical protection of NPPs in the INFCIRC/ 225/Rev.5 to the member states and U.S. NRC also enforces the similar requirements in 10 CFR 73.55. Thus, in order to let Korean NPPs meet the new requirements in INFCIRC/225/Rev.5 or U.S. NRC requirements, Korea nuclear licensee should develop or establish appropriate physical protection system (PPS) design methods for the physical protection of the operating NPPs and new NPPs. KHNP is doing the project of 'Development of APR1400 Physical Protection System Design (2012- 2015, KHNP/KAERI /KEPCO E-C)'. This paper describes overview of a physical protection system (PPS) design and evaluation for an advanced nuclear power plant. It found that a new physical protection system (PPS)design and evaluation. KHNP is doing the project of Physical Protection System design according to U.S. NRC requirements and IAEA requirements in INFCIRC /225 /Rev.5 and will complete by 7.31, 2015 for development of APR1400 Physical Protection System. After completing this project, the results of project are expected to apply new NPPs.

Management information system applied to radiation protection services

International Nuclear Information System (INIS)

Grossi, Pablo Andrade; Souza, Leonardo Soares de; Figueiredo, Geraldo Magela; Figueiredo, Arthur

2013-01-01

An effective management information system based on technology, information and people is necessary to improve the safety on all processes and operations subjected to radiation risks. The complex and multisource information flux from all radiation protection activities on nuclear organizations requires a robust tool/system to highlight the strengths and weaknesses and identify behaviors and trends on the activities requiring radiation protection programs. Those organized and processed data are useful to reach a successful management and to support the human decision-making on nuclear organization. This paper presents recent improvements on a management information system based on the radiation protection directives and regulations from Brazilian regulatory body. This radiation protection control system is applied to any radiation protection services and research institutes subjected to Brazilian nuclear regulation and is a powerful tool for continuous management, not only indicating how the health and safety activities are going, but why they are not going as well as planned showing up the critical points. (author)

Management information system applied to radiation protection services

Energy Technology Data Exchange (ETDEWEB)

Grossi, Pablo Andrade; Souza, Leonardo Soares de; Figueiredo, Geraldo Magela; Figueiredo, Arthur, E-mail: pabloag@cdtn.br, E-mail: lss@cdtn.br, E-mail: gmf@cdtn.br, E-mail: arthurqof@gmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2013-07-01

An effective management information system based on technology, information and people is necessary to improve the safety on all processes and operations subjected to radiation risks. The complex and multisource information flux from all radiation protection activities on nuclear organizations requires a robust tool/system to highlight the strengths and weaknesses and identify behaviors and trends on the activities requiring radiation protection programs. Those organized and processed data are useful to reach a successful management and to support the human decision-making on nuclear organization. This paper presents recent improvements on a management information system based on the radiation protection directives and regulations from Brazilian regulatory body. This radiation protection control system is applied to any radiation protection services and research institutes subjected to Brazilian nuclear regulation and is a powerful tool for continuous management, not only indicating how the health and safety activities are going, but why they are not going as well as planned showing up the critical points. (author)

Future Interoperability of Camp Protection Systems (FICAPS)

Science.gov (United States)

Caron, Sylvie; Gündisch, Rainer; Marchand, Alain; Stahl, Karl-Hermann

2013-05-01

The FICAPS Project has been established as a Project of the European Defence Agency based on an initiative of Germany and France. Goal of this Project was to derive Guidelines, which by a proper implementation in future developments improve Camp Protection Systems (CPS) by enabling and improving interoperability between Camp Protection Systems and its Equipments of different Nations involved in multinational missions. These Guidelines shall allow for: • Real-time information exchange between equipments and systems of different suppliers and nations (even via SatCom), • Quick and easy replacement of equipments (even of different Nations) at run-time in the field by means of plug and play capability, thus lowering the operational and logistic costs and making the system highly available, • Enhancement of system capabilities (open and modular systems) by adding new equipment with new capabilities (just plug-in, automatic adjustment of the HMI Human Machine Interface) without costly and time consuming validation and test on system level (validation and test can be done on Equipment level), Four scenarios have been identified to summarize the interoperability requirements from an operational viewpoint. To prove the definitions given in the Guideline Document, a French and a German Demonstration System, based on existing national assets, were realized. Demonstrations, showing the capabilities given by the defined interoperability requirements with respect to the operational scenarios, were performed. Demonstrations included remote control of a CPS by another CPS, remote sensor control (Electro-Optic/InfraRed EO/IR) and remote effector control. This capability can be applied to extend the protection area or to protect distant infrastructural assets Demonstrations have been performed. The required interoperability functionality was shown successfully. Even if the focus of the FICAPS project was on camp protection, the solution found is also appropriate for other

Implementation of FPGA-Based Diverse Protection System

International Nuclear Information System (INIS)

Hwang, Soo Yun; Lee, Yoon Hee; Shon, Se Do; Baek, Seung Min

2015-01-01

Obsolete analog and digital hardware platforms in NPPs are commonly replaced with programmable logic controller (PLC) and distributed control system (DCS). Field programmable gate arrays (FPGAs) are highlighted as an alternative to obsolete hardware platforms. FPGAs are digital integrated circuits (ICs) that contain the configurable (programmable) blocks of logic along with configurable interconnections among these blocks. Designers can configure (program) such devices to perform a tremendous variety of tasks. FPGAs have been evolved from the technology of programmable logic device (PLD). Nowadays, they can contain millions of logic gates by nanotechnology and can be used to implement extremely large and complex functions that previously could be realized only using application specific integrated circuits (ASICs). This paper presents the implementation of an FPGA-based diverse protection system (DPS) which executes the protective functions in NPP when the protective functions of the plant protection system (PPS) fails

Implementation of FPGA-Based Diverse Protection System

Energy Technology Data Exchange (ETDEWEB)

Hwang, Soo Yun; Lee, Yoon Hee; Shon, Se Do; Baek, Seung Min [KEPCO Engineering and Construction Company Inc., Daejeon (Korea, Republic of)

2015-10-15

Obsolete analog and digital hardware platforms in NPPs are commonly replaced with programmable logic controller (PLC) and distributed control system (DCS). Field programmable gate arrays (FPGAs) are highlighted as an alternative to obsolete hardware platforms. FPGAs are digital integrated circuits (ICs) that contain the configurable (programmable) blocks of logic along with configurable interconnections among these blocks. Designers can configure (program) such devices to perform a tremendous variety of tasks. FPGAs have been evolved from the technology of programmable logic device (PLD). Nowadays, they can contain millions of logic gates by nanotechnology and can be used to implement extremely large and complex functions that previously could be realized only using application specific integrated circuits (ASICs). This paper presents the implementation of an FPGA-based diverse protection system (DPS) which executes the protective functions in NPP when the protective functions of the plant protection system (PPS) fails.

Risk analysis update of the LHC cryogenic system following the 19th September 2008 incident

CERN Document Server

Chorowski, M; Modlinski, Z; Polinski, J; Tavian, L; Wach, J

2011-01-01

On 19th September 2008, during powering tests of the main dipole circuit of the Large Hadron Collider, an electrical fault occurred producing an electrical arc and resulting in mechanical and electrical damage, release of helium from the magnet cold mass to the insulation vacuum enclosure and consequently to the tunnel, via the spring-loaded relief discs on the vacuum enclosure. The pressurization of the vacuum space exceeded significantly the allowed design value. Mathematical modeling based on a thermodynamic approach has enabled the revision of the helium discharge system protecting the vacuum enclosure against the over-pressurization in case of a redefined maximum credible incident (MCI) occurrence.

Power system EMP protection. Final report

International Nuclear Information System (INIS)

Marable, J.H.; Barnes, P.R.; Nelson, D.B.

1975-05-01

Voltage transients induced in electric power lines and control circuits by the electromagnetic pulse (EMP) from high-altitude nuclear detonations may cause widespread power failure and damage in electric power systems. This report contains a parametric study of EMP power line surges and discusses protective measures to minimize their effects. Since EMP surges have considerably greater rates of rise than lightning surges, recommended standards and test procedures are given to assure that surge arresters protect equipment from damage by EMP. Expected disturbances and damage to power systems are reviewed, and actions are presented which distribution companies can take to counter them. These include backup communications methods, stockpiling of vulnerable parts, repair procedures, and dispatcher actions to prevent blackout from EMP-caused instabilities. A long-range program is presented for improving distributors' protection against EMP. This involves employee training, hardware protection for power and control circuits, and improvement of plans for emergency action. (U.S.)

A Cause-Consequence Chart of a Redundant Protection System

DEFF Research Database (Denmark)

Nielsen, Dan Sandvik; Platz, O.; Runge, B.

1975-01-01

A cause-consequence chart is applied in analysing failures of a redundant protection system (a core spray system in a nuclear power plant). It is shown how the diagram provides a basis for calculating two probability measures for malfunctioning of the protection system. The test policy of compone...... of components is taken into account. The possibility of using parameter variation as a basis for the choice of test policy is indicated.......A cause-consequence chart is applied in analysing failures of a redundant protection system (a core spray system in a nuclear power plant). It is shown how the diagram provides a basis for calculating two probability measures for malfunctioning of the protection system. The test policy...

Angle Control-Based Multi-Terminal Out-of-Step Protection System

Directory of Open Access Journals (Sweden)

Antans Sauhats

2017-03-01

Full Text Available From time to time a sequence of unexpected and overlapping contingencies may lead to power system angular instability and even blackouts if not addressed adequately by means of an out-of-step (OOS protection system. The motivation of the paper is an attempt to develop a workable prototype of the OOS protection system. The deficiencies of the protection currently used in the Latvian Power System network are highlighted and a new protection structure is proposed. The protection system comprises of several strategically located terminals, exchanging information in real time by means of a communication network. The OOS condition detection method is based on system-wide generation sources, electromotive forces, vectors, and angle control. The network splitting decision is based on generator coherence evaluation. Protection terminals determine online the groups of coherent generators and choose the splitting boundary from a predefined transmission lines (TLs cut sets list. The protection system structure, algorithm of operation, and possible IEC 61850 communication standard-based implementation are described.

Integrated crop protection as a system approach

OpenAIRE

Haan, de, J.J.; Wijnands, F.G.; Sukkel, W.

2005-01-01

New farming systems in vegetable production are required as demands for high quality products that do not pollute the environment are rising, and production risks are large and incomes low. The methodology of prototyping new systems is described, especially the themes, parameters and target values connected to integrated crop protection. The role of integrated crop protection in prototyping new systems is discussed. The results of twenty years working with this prototyping methodology are pre...

The Protective Arm of the Renin Angiotensin System (RAS)

DEFF Research Database (Denmark)

understanding of the protective side of the Renin Angiotensin System (RAS) involving angiotensin AT2 receptor, ACE2, and Ang(1-7)/Mas receptor Combines the knowledge of editors who pioneered research on the protective renin angiotensin system including; Dr. Thomas Unger, one of the founders of AT2 receptor......The Protective Arm of the Renin Angiotensin System: Functional Aspects and Therapeutic Implications is the first comprehensive publication to signal the protective role of a distinct part of the renin-angiotensin system (RAS), providing readers with early insight into a complex system which...... will become of major medical importance in the near future. Focusing on recent research, The Protective Arm of the Renin Angiotensin System presents a host of new experimental studies on specific components of the RAS, namely angiotensin AT2 receptors (AT2R), the angiotensin (1-7) peptide with its receptor...

75 FR 972 - Nomination of Existing Marine Protected Areas to the National System of Marine Protected Areas

Science.gov (United States)

2010-01-07

... Marine Protected Areas to the National System of Marine Protected Areas AGENCY: NOAA, Department of... Federal, State and territorial marine protected area programs to join the National System of Marine Protected Areas. SUMMARY: NOAA and the Department of the Interior (DOI) invited Federal, State, commonwealth...

Discussion on radiation protection system from ethical issues

International Nuclear Information System (INIS)

Li, Xutong; Guo, Qiuju

2002-01-01

This paper discussed the relationship between radiation protection system and ethical principle, viz. equity and efficiency. According to the authors' opinions, the main problem that the system of radiation protection facing now is the dose-limitation principle cannot incarnate the equity principle completely. Even though the distinguishing between practice and intervention is no other than solving the problem, but the scheme is not perfect still. Ethical issues should be given more attention and be more researched when we try to modify the radiation protection system today

Novel Directional Protection Scheme for the FREEDM Smart Grid System

Science.gov (United States)

Sharma, Nitish

This research primarily deals with the design and validation of the protection system for a large scale meshed distribution system. The large scale system simulation (LSSS) is a system level PSCAD model which is used to validate component models for different time-scale platforms, to provide a virtual testing platform for the Future Renewable Electric Energy Delivery and Management (FREEDM) system. It is also used to validate the cases of power system protection, renewable energy integration and storage, and load profiles. The protection of the FREEDM system against any abnormal condition is one of the important tasks. The addition of distributed generation and power electronic based solid state transformer adds to the complexity of the protection. The FREEDM loop system has a fault current limiter and in addition, the Solid State Transformer (SST) limits the fault current at 2.0 per unit. Former students at ASU have developed the protection scheme using fiber-optic cable. However, during the NSF-FREEDM site visit, the National Science Foundation (NSF) team regarded the system incompatible for the long distances. Hence, a new protection scheme with a wireless scheme is presented in this thesis. The use of wireless communication is extended to protect the large scale meshed distributed generation from any fault. The trip signal generated by the pilot protection system is used to trigger the FID (fault isolation device) which is an electronic circuit breaker operation (switched off/opening the FIDs). The trip signal must be received and accepted by the SST, and it must block the SST operation immediately. A comprehensive protection system for the large scale meshed distribution system has been developed in PSCAD with the ability to quickly detect the faults. The validation of the protection system is performed by building a hardware model using commercial relays at the ASU power laboratory.

Power system protection 1 principles and components

CERN Document Server

Association, Electricity Training

1995-01-01

The worldwide growth in demand for electricity has forced the pace of developments in electrical power system design to meet consumer needs for reliable, secure and cheap supplies. Power system protection, as a technology essential to high quality supply, is widely recognised as a specialism of growing and often critical importance, in which power system needs and technological progress have combined to result in rapid developments in policy and practice in recent years. In the United Kingdom, the need for appropriate training in power system protection was recognised in the early 1960s with t

78 FR 44475 - Protection System Maintenance Reliability Standard

Science.gov (United States)

2013-07-24

... that the performance or product has some reliability-related value, then the requirement will have...] Protection System Maintenance Reliability Standard AGENCY: Federal Energy Regulatory Commission, Energy... Commission proposes to approve a revised Reliability Standard, PRC-005- 2--Protection System Maintenance, to...

Automatic coordination of protection devices in distribution system

International Nuclear Information System (INIS)

Comassetto, L.; Bernardon, D.P.; Canha, L.N.; Abaide, A.R.

2008-01-01

Among the several components of distribution systems, protection devices present a fundamental importance, since they aim at keeping the physical integrity not only of the system equipment, but also of the electricians' team and the population in general. The existing tools today in the market that carry out the making of protection studies basically draw curves, and need direct user's interference for the protection devices adjustment and coordination analyses of selectivity, being susceptible to the user's mistakes and not always considering the best technical and economical application. In Brazil, the correct application of the protection devices demand a high amount of time, being extremely laborious due to the great number of devices (around 200 devices), besides the very dynamic behaviour of distribution networks and the need for constant system expansion. This article presents a computational tool developed with the objective of automatically determining the adjustments of all protection devices in the distribution networks to obtain the best technical application, optimizing its performance and making easier protection studies. (author)

Regulatory System of Radiation Protection in Taiwan

International Nuclear Information System (INIS)

Tang, F. T.; Huang, C. C.

2004-01-01

After the radioactive contaminated buildings incident occurred in Taiwan in 1993, the competent authority for radiation protection the Atomic Energy Council (AEC) started to review the structured problem of radiation protection regulatory system. Through several years' investigation and study, the AEC has improved two important tools in radiation protection regulatory system, i.e., control regulations and actual practice, and made them more rigorous and efficient. This paper will make a brief introduction of the efforts that Taiwan has made in this respect. Taiwan's radiation protection control was based on the Atomic Energy Law promulgated in 1968, but the control idea and authorization scope were not sufficient to appropriately respond to the highly developed economy and democracy in Taiwan. After several years' legislative process, the Ionizing Radiation Protection Law (IRP Law) was promulgated and entered into force on February 1, 2003. This IRP Law specifically emphasizes categorized risk management of radiation sources, establishment of personnel licenses and training system, enhancement of public safety control, and implementation of quality assurance program for medical exposure. The Legislative Yuan (Congress) fully authorized the competent authority to establish various technological control regulations according to control necessity without prior review by the Legislative Yuan in advance. As to the penalties of the violations of the IRP Law, the AEC adopts high-rated administrative fines and applies the Criminal Law to those who seriously contaminate the environment. In actual practice, the AEC has constructed a Radiation Protection Control Information System compatible with the IRP Law that fully combines the functions of computers and Internet. The information of facility operators who own radiation sources, radiation protection specialists, and operating personnel are entered into this system, starting from the submission of application of the

Modern tools to evaluate and optimize fire protection systems

International Nuclear Information System (INIS)

Alvares, N.J.; Hasegawa, H.K.

1980-01-01

Modern techniques, such as fault tree analysis, can be used to obtain engineering descriptions of specific fire protection systems. The analysis allows establishment of an optimum level of fire protection, and evaluates the level of protection provided by various systems. A prime example: the application to fusion energy experiments

Design and evaluation of physical protection systems of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

An, Jin Soo; Lee, Hyun Chul; Hwang, In Koo; Kwack, Eun Ho; Choi, Yung Myung

2001-06-01

Nuclear material and safety equipment of nuclear facilities are required to be protected against any kind of theft or sabotage. Physical protection is one of the measures to prevent such illegally potential threats for public security. It should cover all the cases of use, storage, and transportation of nuclear material. A physical protection system of a facility consists of exterior intrusion sensors, interior intrusion sensors, an alarm assessment and communication system, entry control systems, access delay equipment, etc. The design of an effective physical protection system requires a comprehensive approach in which the designers define the objective of the system, establish an initial design, and evaluate the proposed design. The evaluation results are used to determine whether or not the initial design should be modified and improved. Some modelling techniques are commonly used to analyse and evaluate the performance of a physical protection system. Korea Atomic Energy Research Institute(KAERI) has developed a prototype of software as a part of a full computer model for effectiveness evaluation for physical protection systems. The input data elements for the prototype, contain the type of adversary, tactics, protection equipment, and the attributes of each protection component. This report contains the functional and structural requirements defined in the development of the evaluation computer model.

Criminal law repercussions on the Civil Protection System

Science.gov (United States)

Altamura, M.; Musso, L.

2009-09-01

The legal systems of our Countries provide the citizenship with a high level of protection. Personal safety and the protection of property are guaranteed by the State through organized structures among which we can include the Civil Protection. The progress of science and technology has greatly improved monitoring tools, currently used by the Civil Protection, which allow, to a certain extent, to predict and prevent risk and natural hazards. The assertion of an individual right, which in some cases has reached a constitutional rank, to benefit from Civil Protection services and the widespread perception throughout the citizenship of the competence of the system to prevent disasters, often causes people to take legal action against Civil Protection authorities should they fail in their duties to protect. However, the attempt of having both recognized an economic compensation for the suffered loss and the punishment of those whom misled, frequently undergoes criminal law. This process could have results that may jeopardize the effectiveness of Civil Protection service without meeting citizens’ demands. A dual effort is thus necessary in order to solve such a problem. On the one hand, an interdisciplinary knowledge needs to pervade criminal law in an attempt to relieve its self-referentiality and pretended supremacy. On the other hand an alternative, and more agile, system -such as civil or administrative law- has to be identified in order to respond to the legitimate requests for protection in the case of a faulty behaviour of the authorities.

Distributed systems for protecting nuclear power stations

International Nuclear Information System (INIS)

Jover, P.

1980-05-01

The advantages of distributed control systems for the control of nuclear power stations are obviously of great interest. Some years ago, EPRI, (Electric Power Research Institute) showed that multiplexing the signals is technically feasible, that it enables the availability specifications to be met and costs to be reduced. Since then, many distributed control systems have been proposed by the manufacturers. This note offers some comments on the application of the distribution concept to protection systems -what should be distributed- and ends with a brief description of a protection system based on microprocessors for the pressurized power stations now being built in France [fr

Distributed systems for the protection of nuclear stations

International Nuclear Information System (INIS)

Jover, P.

1980-01-01

The advantages of distributed control systems usually mentioned are improved exploitation, cost reduction, and adaptation to changes in technology. These advantages are obviously very interesting for nuclear power plant applications, and many such systems have been proposed. This note comments on the application of the distributed system concept to protection systems - what should be distributed - and closes with a brief description of a protection system based on microprocessors for pressurized water stations being built in France. (auth) [fr

Evolution of the system of radiological protection

International Nuclear Information System (INIS)

2005-11-01

One of the main challenges facing radiological protection experts is how to integrate radiological protection within modern concepts of and approaches to risk governance. It is within this context that the International Commission on Radiological Protection (ICRP) decided to develop new general recommendations to replace its Publication 60 recommendations of 1990. In the process of developing these new recommendations, the views of the ICRP have evolved significantly, largely due to stakeholder involvement that has been actively solicited by the ICRP. In this regard, it was upheld during the First Asian Regional Conference organised by the NEA in October 2002 that the implementation of the new system must allow for regional, societal and cultural differences. In order to ensure appropriate consideration of these differences, the NEA organised the Second Asian Regional Conference on the Evolution of the System of Radiological Protection. Held in Tokyo on 28-29 July 2004, the conference included presentations by the ICRP Chair as well as by radiological experts from Australia, China, Japan and Korea. Within their specific cultural and socio-political milieu, Asia-Pacific and western ways of thought on how to improve the current system of radiological protection were presented and discussed. These ways of thinking, along with a summary of the conference results, are described in these proceedings. (author)

Decentralized Adaptive Overcurrent Protection for Medium Voltage Maritime Power Systems

DEFF Research Database (Denmark)

Ciontea, Catalin-Iosif; Bak, Claus Leth; Blaabjerg, Frede

2016-01-01

the entire electrical network and changes the relay settings accordingly, but this approach is not adequate for the maritime power systems. This paper propose a decentralized adaptive protection method, where each protection relay is able to identify by itself the network status without the need of a central...... control unit. The new adaptive protection method is based on communication between the overcurrent relays and the equipment that could affect the protection system, such as circuit breakers and generators. Using PSCAD, the proposed method is implemented in a test medium voltage maritime power system......More and more maritime applications as marine vessels and offshore platforms need an adaptive protection power system. However, the adaptive protection is yet to be implemented in the maritime sector. Usually, the adaptive protection implies the existence of a central control unit that monitors...

Displacements of Metallic Thermal Protection System Panels During Reentry

Science.gov (United States)

Daryabeigi, Kamran; Blosser, Max L.; Wurster, Kathryn E.

2006-01-01

Bowing of metallic thermal protection systems for reentry of a previously proposed single-stage-to-orbit reusable launch vehicle was studied. The outer layer of current metallic thermal protection system concepts typically consists of a honeycomb panel made of a high temperature nickel alloy. During portions of reentry when the thermal protection system is exposed to rapidly varying heating rates, a significant temperature gradient develops across the honeycomb panel thickness, resulting in bowing of the honeycomb panel. The deformations of the honeycomb panel increase the roughness of the outer mold line of the vehicle, which could possibly result in premature boundary layer transition, resulting in significantly higher downstream heating rates. The aerothermal loads and parameters for three locations on the centerline of the windward side of this vehicle were calculated using an engineering code. The transient temperature distributions through a metallic thermal protection system were obtained using 1-D finite volume thermal analysis, and the resulting displacements of the thermal protection system were calculated. The maximum deflection of the thermal protection system throughout the reentry trajectory was 6.4 mm. The maximum ratio of deflection to boundary layer thickness was 0.032. Based on previously developed distributed roughness correlations, it was concluded that these defections will not result in tripping the hypersonic boundary layer.

78 FR 50455 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Changes to...

Science.gov (United States)

2013-08-19

... Purification Return Line in order to maintain overpressure protection, replaces an isolation check valve in the CVS with an air operated globe valve, and separates the zinc and hydrogen injection lines. Part of the... modification which provides a spring-assisted check valve to the Reactor Coolant System Purification Return...

Localization of equipment for digital plant protection system

Energy Technology Data Exchange (ETDEWEB)

Koo, I. S.; Park, H. Y.; Lee, C. K. and others

2000-10-01

The objective of this project lies on the development of design requirements, establishment of structure and manufacture procedures, development of the software verification and validation(V and V) techniques of the digital plant protection system. The functional requirements based on the analog protection system and digital design requirements are introduced, the processor and system bus for safety grade equipment are selected and the interface requirements and the design specification have been developed in order to manufacture the quick prototype of the digital plant protection system. The selection guidelines of parts, software development and coding and testing for digital plant protection system have been performed through manufacturing the quick prototype based on the developed design specification. For the software verification and validation, the software review plan and techniques of verification and validation have been researched. The digital validation system is developed in order to verify the quick prototype. The digital design requirements are reviewed by the software safety plan and V and V plans. The formal methods for verifying the safety-grade software are researched, then the methodology of formal analysis and testing have been developed.

Localization of equipment for digital plant protection system

International Nuclear Information System (INIS)

Koo, I. S.; Park, H. Y.; Lee, C. K. and others

2000-10-01

The objective of this project lies on the development of design requirements, establishment of structure and manufacture procedures, development of the software verification and validation(V and V) techniques of the digital plant protection system. The functional requirements based on the analog protection system and digital design requirements are introduced, the processor and system bus for safety grade equipment are selected and the interface requirements and the design specification have been developed in order to manufacture the quick prototype of the digital plant protection system. The selection guidelines of parts, software development and coding and testing for digital plant protection system have been performed through manufacturing the quick prototype based on the developed design specification. For the software verification and validation, the software review plan and techniques of verification and validation have been researched. The digital validation system is developed in order to verify the quick prototype. The digital design requirements are reviewed by the software safety plan and V and V plans. The formal methods for verifying the safety-grade software are researched, then the methodology of formal analysis and testing have been developed

Outer skin protection of columbium Thermal Protection System (TPS) panels

Science.gov (United States)

Culp, J. D.

1973-01-01

A coated columbium alloy material system 0.04 centimeter thick was developed which provides for increased reliability to the load bearing character of the system in the event of physical damage to and loss of the exterior protective coating. The increased reliability to the load bearing columbium alloy (FS-85) was achieved by interposing an oxidation resistant columbium alloy (B-1) between the FS-85 alloy and a fused slurry silicide coating. The B-1 alloy was applied as a cladding to the FS-85 and the composite was fused slurry silicide coated. Results of material evaluation testing included cyclic oxidation testing of specimens with intentional coating defects, tensile testing of several material combinations exposed to reentry profile conditions, and emittance testing after cycling of up to 100 simulated reentries. The clad material, which was shown to provide greater reliability than unclad materials, holds significant promise for use in the thermal protection system of hypersonic reentry vehicles.

44 CFR 65.14 - Remapping of areas for which local flood protection systems no longer provide base flood protection.

Science.gov (United States)

2010-10-01

... local flood protection systems no longer provide base flood protection. 65.14 Section 65.14 Emergency... § 65.14 Remapping of areas for which local flood protection systems no longer provide base flood... process of restoring a flood protection system that was: (i) Constructed using Federal funds; (ii...

Protective relaying of power systems using mathematical morphology

CERN Document Server

Wu, QH; Ji, TY

2009-01-01

Discusses the development of novel protective relaying algorithms, using Mathematical Morphology (MM). This book introduces the fundamental principles of MM, and brings together the applications of MM to develop different protective relaying algorithms for the protection of a variety of power system components.

New measuring and protection system at VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Jurickova, M.

2006-01-01

The contribution describes the new measuring and protection system of the VR-1 training reactor. The measuring and protection system upgrade is an integral part of the reactor I and C upgrade. The new measuring and protection system of the VR-1 reactor consists of the operational power measuring and the independent power protection systems. Both systems measure the reactor power and power rate, initiate safety action if safety limits are exceeded and send data (power, power rate, status, etc.) to the reactor control system. The operational power measuring system is a full power range system that receives signal from a fission chamber. The signal is evaluated according to the reactor power either in the pulse or current mode. The current mode utilizes the DC current and Campbell techniques. The new independent power protection system operates in the two highest reactor power decades. It receives signals from a boron chamber and evaluates it in the pulse mode. Both systems are computer based. The operational power measuring and independent power protection systems are diverse - different types and location of chambers, completely different hardware, software algorithms for the power and power rate calculations, software development tools and teems for the software manufacturing. (author)

Report on task I: fire protection system study

International Nuclear Information System (INIS)

Bernard, E.A.; Cano, G.L.

1977-02-01

This study (1) evaluates, on a comparative basis, the national and international regulatory and insurance standards that serve as guidance for fire protection within the nuclear power industry; (2) analyzes the recommendations contained in the major reports on the Browns Ferry Fire; (3) proposes quantitative safety goals and evaluation methods for Nuclear Power Plant Fire Protection Systems (NPPFPS); (4) identifies potential improvements that may be incorporated into NPPFPS; and (5) recommends a plan of action for continuation of the fire protections systems study

Illustration of distributed generation effects on protection system coordination

Science.gov (United States)

Alawami, Hussain Adnan

Environmental concerns, market forces, and emergence of new technologies have recently resulted in restructuring electric utility from vertically integrated networks to competitive deregulated entities. Distributed generation (DG) is playing a major role in such deregulated markets. When they are installed in small amounts and small sizes, their impacts on the system may be negligible. When their penetration levels increase as well as their sizes, however, they may start affecting the system performance from more than one aspect. Power system protection needs to be re-assessed after the emergence of DG. This thesis attempts to illustrate the impact of DG on the power system protection coordination. It will study the operation of the impedance relays, fuses, reclosers and overcurrent relays when a DG is added to the distribution network. Different DG sizes, distances from the network and locations within the distribution system will be considered. Power system protection coordination is very sensitive to the DG size where it is not for the DG distance. DG location has direct impact on the operation of the protective devices especially when it is inserted in the middle point of the distribution system. Key Words, Distributed Generation, Impedance relay, fuses, reclosers, overcurrent relays, power system protection coordination.

An integrated numerical protection system (SPIN)

International Nuclear Information System (INIS)

Savornin, J.L.; Bouchet, J.M.; Furet, J.L.; Jover, P.; Sala, A.

1978-01-01

Developments in technology have now made it possible to perform more sophisticated protection functions which follow more closely the physical phenomena to be monitored. For this reason the Commissariat a l'energie atomique, Merlin-Gerin, Cerci and Framatome have embarked on the joint development of an Integrated Numerical Protection System (SPIN) which will fulfil this objective and will improve the safety and availability of power stations. The system described involves the use of programmed numerical techniques and a structure based on multiprocessors. The architecture has a redundancy of four. Throughout the development of the project the validity of the studies was confirmed by experiments. A first numerical model of a protection function was tested in the laboratory and is now in operation in a power station. A set of models was then introduced for checking the main components of the equipment finally chosen prior to building and testing a prototype. (author)

SNAP: a tool for nuclear physical protection system modeling

International Nuclear Information System (INIS)

Engi, D.; Grant, F.H. III.

1979-10-01

Nuclear safeguards systems are concerned, in part, with the physical protection of nuclear materials. The function of a physical protection system is to define the facility against adversary activities which could lead to theft of nuclear material or sabotage resulting in a radiological release. The Safeguards Network Analysis Procedure (SNAP) provides a convenient and standard analysis methodology for the evaluation of physical protection system analysis. This paper describes a detailed application of SNAP to a hypothetical nuclear facility

Development of In-Core Protection System

International Nuclear Information System (INIS)

Cho, J. H; Kim, C. H.; Kim, J. H.; Jeong, S. H.; Sohn, S. D.; BaeK, S. M.; YOON, J. H.

2016-01-01

In-core Protection System (ICOPS) is an on-line digital computer system which continuously calculates Departure from Nucleate Boiling Ratio (DNBR) and Local Power Density (LPD) based on plant parameters to make trip decisions based on the computations. The function of the system is the same as that of Core Protection Calculator System (CPCS) and Reactor Core Protection System (RCOPS) which are applied to Optimized Power Reactor 1000 (OPR1000) and Advanced Power Reactor 1400 (APR1400). The ICOPS has been developed to overcome the algorithm related obstacles in overseas project. To achieve this goal, several algorithms were newly developed and hardware and software design was updated. The functional design requirements document was developed by KEPCO-NF and the component design was conducted by Doosan. System design and software implementation were performed by KEPCO-E and C, and software Verification and Validation (V and V) was performed by KEPCO-E and C and Sure Softtech. The ICOPS has been developed to overcome the algorithm related obstacles in overseas project. The function of I/O simulator was improved even though the hardware platform is the same as that of RCOPS for Shin-Hanul 1 and 2. SCADE was applied to the implementation of ICOPS software, and the V and V system for ICOPS which satisfies international standards was developed. Although several further detailed design works remain, the function of ICOPS has been confirmed. The ICOPS will be applied to APR+ project, and the further works will be performed in following project

Development of In-Core Protection System

Energy Technology Data Exchange (ETDEWEB)

Cho, J. H; Kim, C. H.; Kim, J. H.; Jeong, S. H.; Sohn, S. D.; BaeK, S. M.; YOON, J. H. [KEPCO Engineering and Construction Co., Deajeon (Korea, Republic of)

2016-10-15

In-core Protection System (ICOPS) is an on-line digital computer system which continuously calculates Departure from Nucleate Boiling Ratio (DNBR) and Local Power Density (LPD) based on plant parameters to make trip decisions based on the computations. The function of the system is the same as that of Core Protection Calculator System (CPCS) and Reactor Core Protection System (RCOPS) which are applied to Optimized Power Reactor 1000 (OPR1000) and Advanced Power Reactor 1400 (APR1400). The ICOPS has been developed to overcome the algorithm related obstacles in overseas project. To achieve this goal, several algorithms were newly developed and hardware and software design was updated. The functional design requirements document was developed by KEPCO-NF and the component design was conducted by Doosan. System design and software implementation were performed by KEPCO-E and C, and software Verification and Validation (V and V) was performed by KEPCO-E and C and Sure Softtech. The ICOPS has been developed to overcome the algorithm related obstacles in overseas project. The function of I/O simulator was improved even though the hardware platform is the same as that of RCOPS for Shin-Hanul 1 and 2. SCADE was applied to the implementation of ICOPS software, and the V and V system for ICOPS which satisfies international standards was developed. Although several further detailed design works remain, the function of ICOPS has been confirmed. The ICOPS will be applied to APR+ project, and the further works will be performed in following project.

'H-Bahn' - Dortmund demonstration system. Automatic vehicle protection system

Energy Technology Data Exchange (ETDEWEB)

Rosenkranz

1984-01-01

The automatic vehicle protection system of the H-Bahn at the Universtiy of Dortmund is responsible for fail-safe operating of the automatic vehicles. Its functions are protection of vehicle operation and protection of passengers boarding and leaving the vehicles. These functions are managed decentrally by two fail-safe operating controllers. Besides the well-known relay-techniques of railway-fail-safe systems, electronics are applied which are based on safe operating URTL-microcontrollers. These are controlled by software stored in EPROMs. A connection link using glass-fibres serves for safe data-exchange between the two fail-safe operating controllers. The experts' favourable reports on 'train protection and safety during passenger processing' were completed in March 84; thus, transportation of passengers could start in April 84.

Systems and methods for photovoltaic string protection

Science.gov (United States)

Krein, Philip T.; Kim, Katherine A.; Pilawa-Podgurski, Robert C. N.

2017-10-25

A system and method includes a circuit for protecting a photovoltaic string. A bypass switch connects in parallel to the photovoltaic string and a hot spot protection switch connects in series with the photovoltaic string. A first control signal controls opening and closing of the bypass switch and a second control signal controls opening and closing of the hot spot protection switch. Upon detection of a hot spot condition the first control signal closes the bypass switch and after the bypass switch is closed the second control signal opens the hot spot protection switch.

Architecture and Fault Identification of Wide-area Protection System

Directory of Open Access Journals (Sweden)

Yuxue Wang

2012-09-01

Full Text Available Wide-area protection system (WAPS is widely studied for the purpose of improvng the performance of conventional backup protection. In this paper, the system architecture of WAPS is proposed and its key technologies are discussed in view of engineering projects. So a mixed structurecentralized-distributed structure which is more suitable for WAPS in limited power grid region, is obtained based on the advantages of the centralized structure and distributed structure. Furthermore, regional distance protection algorithm was taken as an example to illustrate the functions of the constituent units. Faulted components can be detected based on multi-source imformation fuse in the algorithm. And the algorithm cannot only improve the selectivity, the rapidity, and the reliability of relaying protection but also has high fault tolerant capability. A simulation of 220 kV grid systems in Easter Hubei province shows the effectiveness of the wide-area protection system presented by this paper.

A critical review of the system of radiation protection

International Nuclear Information System (INIS)

2000-01-01

Our modern, information society is increasingly interested in transparency and participation in many aspects of government, and this is particularly true in areas involving public health and environmental protection. Radiation protection is no exception to this trend. Scientific rationale that was once sufficient to explain radiation protection theory and practice is no longer adequate. The need to address and communicate theory, practice and the decision-making process to a wider audience has given rise to numerous debates and led the radiation protection community to revisit the framework of the system of radiation protection. The very fundamentals of the system of radiation protection continue to be questioned in a healthy fashion, and many aspects have been identified which could better serve stakeholders given some additional thought in the light of modern societal needs. This report is the summary of the NEA's first reflections in this area, and describes those aspects of the current international system of radiation protection that could be improved. Suggested directions for improvement are provided. (author)

Dependability Evaluation of Advanced Diverse Protection System

International Nuclear Information System (INIS)

Oh, Yang Gyun; Lee, Yoon Hee; Sohn, Se Do; Baek, Seung Min; Lee, Sang Jeong

2014-01-01

For the mitigation of anticipated transients without scram (ATWS) as well as common cause failure (CCF) within the plant protection system (PPS) and the emergency safety feature . component control system (ESF-CCS), the diverse protection system (DPS) has been designed by KEPCO Engineering and Construction Company. Recently KEPCO E and C has developed the advanced diverse protection system (ADPS), which has four redundant channels, in an attempt to enhance a fault-tolerant capability of the system. For the evaluation of overall system improvement effects of the ADPS compared with the DPS, the dependability evaluation results are described herein. For all dependability attributes, this paper suggests a practical dependability evaluation method which uses quantitative dependability scores and indices. An overall dependability evaluation index (DEI) for the ADPS is evaluated with the average value of reliability/ security/maintainability/safety indices (i.e., RID, SID, MID, and SID') for dependability. The evaluation results show that the DEI value of ADPS can be improved by approximately 23% compared with that of the DPS, thanks to its fault-tolerant system architecture, software design changes, and external interface design features. Several suggestions have been made, in this paper, of an overall quantitative dependability evaluation method for the nuclear instrumentation and control (I and C) systems including the DPS and ADPS, and the usefulness of dependability evaluation on nuclear I and C systems has been confirmed

The protection of photovoltaic power systems from lightning

Science.gov (United States)

Rogers, C. B.

Lightning protection techniques at nine prototype photovoltaic power system sites with outputs from 18-225 kW are described. Noting that protection schemes are devised to fit isokeraunic data for specific sites, grounding is cited as a common feature for all systems. The grounds are, in separate instances, connected to junction boxes, frames of the solar cell panels, lead from the dc center, from the dc negative terminal, from the frames and equipment, at the array turntable, or from the building rebar frames. The dc power cables are protected by either metal conduit, metal conduit ground wire, direct burial, by rigid metal conduit, ground conductors, or by ground conductors at the ends of the conduit run. Costs run from 0.01-0.28$/W, with all the systems outfitted with bypass and blocking diodes. Direct stroke protection is viewed as less important than isokeraunic data.

78 FR 30870 - Nomination of Existing Marine Protected Areas to the National System of Marine Protected Areas

Science.gov (United States)

2013-05-23

... Marine Protected Areas to the National System of Marine Protected Areas AGENCY: National Marine Protected...) invited federal, state, commonwealth, and territorial marine protected area (MPA) programs with... of Marine Protected Areas of the United States (Framework), developed in response to Executive Order...

System architecture for microprocessor based protection system

International Nuclear Information System (INIS)

Gallagher, J.M. Jr.; Lilly, G.M.

1976-01-01

This paper discusses the architectural design features to be employed by Westinghouse in the application of distributed digital processing techniques to the protection system. While the title of the paper makes specific reference to microprocessors, this is only one (and the newest) of the building blocks which constitutes a distributed digital processing system. The actual system structure (as realized through utilization of the various building blocks) is established through considerations of reliability, licensability, and cost. It is the intent of the paper to address these considerations licenstions as they relate to the architectural design features. (orig.) [de

Fracture assessment of the Oskarshamn 1 reactor pressure vessel under cold over-pressurization

International Nuclear Information System (INIS)

Sattari-Far, I.

2001-03-01

The major motivation of this study was to develop a methodology for fracture assessment of surface defects in the 01 reactor pressure vessel under cold loading scenarios, particularly the cold over-pressurization event. According to a previous study, the FENIX project, the cold over-pressurization of the O1 reactor is a limiting loading case, as the ductile/brittle transition temperature (RT NDT ) of certain welds in the O1 beltline region may be over 100 deg C at the-end-of-life condition. The FENIX project gave values of the acceptable and critical crack depth to be equal to the thickness of the cladding layer (about 6 mm) under this load case using the ASME K Ic reference curve methodology. This study is aimed to develop a methodology to give a more precise fracture assessment of the O1 reactor under cold loading scenarios. Some of the main objectives of this study have been as below: To prepare a material which can simulate the mechanical properties and RT NDT of the O1 reactor at the end-of-life conditions. To conduct a fracture mechanics test program to cover the essential influencing factors, such as crack geometry (shallow and deep cracks) and loading condition (uniaxial and biaxial) on the cleavage fracture toughness. To perform fracture mechanics analyses to identify a suitable methodology for assessment of the experimental results. To study the responses of engineering fracture assessment methods to the experimental results from the clad specimens. To propose a fracture assessment procedure for determination of the acceptable and critical flaw sizes in the 01 reactor under the cold loading events. A test program consisted of experiments on standard SEN(B) specimens and clad beams, containing surface cracks was conducted during the course of this project. A total of nine clad beams and clad cruciform specimens were tested under uniaxial and biaxial loading. The test material is reactor steel of type A 508 Grade B, which is specially heat-treated to

Passive fire building protection system evaluation (case study: millennium ict centre)

Science.gov (United States)

Rahman, Vinky; Stephanie

2018-03-01

Passive fire protection system is a system that refers to the building design, both regarding of architecture and structure. This system usually consists of structural protection that protects the structure of the building and prevents the spread of fire and facilitate the evacuation process in case of fire. Millennium ICT Center is the largest electronic shopping center in Medan, Indonesia. As a public building that accommodates the crowd, this building needs a fire protection system by the standards. Therefore, the purpose of this study is to evaluate passive fire protection system of Millennium ICT Center building. The study was conducted to describe the facts of the building as well as direct observation to the research location. The collected data is then processed using the AHP (Analytical Hierarchy Process) method in its weighting process to obtain the reliability value of passive fire protection fire system. The results showed that there are some components of passive fire protection system in the building, but some are still unqualified. The first section in your paper

Enhancement of observability and protection of smart power system

Science.gov (United States)

Siddique, Abdul Hasib

It is important for a modern power grid to be smarter in order to provide reliable and sustainable supply of electricity. Traditional way of receiving data from the wired system is a very old and outdated technology. For a quicker and better response from the electric system, it is important to look at wireless systems as a feasible option. In order to enhance the observability and protection it is important to integrate wireless technology with the modern power system. In this thesis, wireless network based architecture for wide area monitoring and an alternate method for performing current measurement for protection of generators and motors, has been adopted. There are basically two part of this project. First part deals with the wide area monitoring of the power system and the second part focuses more on application of wireless technology from the protection point of view. A number of wireless method have been adopted in both the part, these includes Zigbee, analog transmission (Both AM and FM) and digital transmission. The main aim of our project was to propose a cost effective wide area monitoring and protection method which will enhance the observability and stability of power grid. A new concept of wireless integration in the power protection system has been implemented in this thesis work.

Structural response of reactor-core hexcan subassemblies subjected to dynamic overpressurization under accident conditions

International Nuclear Information System (INIS)

Pfeiffer, P.A.; Kulak, R.F.

1993-01-01

This paper presents a two-dimensional structural analysis for the evaluation of a single core subassembly due to internal overpressure associated with possible failure of fuel pins having high fission gas plenum pressure. Structural models are developed for the subassemblies and their surroundings with emphasis on the critical physical aspects of the problem. With these models the strains, deformations and the extent of permanent damage (plastic strain) to the subassemblies can be assessed. The nonlinear structural analyses was performed with a finite element program called STRAW (Structural Transient Response of Assembly Wrappers). This finite element program is applicable to nonlinear large displacement problems. The results of this study indicate that the permanent deformation (damage) is strongly influenced by the rise time (time to reach peak pressure) of the pressure pulse and the pressure in the fuel pin. The rise time is influenced by the opening time of the flow path for release of gas from the fuel pin plenum. Several examples are illustrated with various rise times and pressure magnitudes and the resulting permanent deformation of the hexcan wall

Beam loss monitor system for machine protection

CERN Document Server

Dehning, B

2005-01-01

Most beam loss monitoring systems are based on the detection of secondary shower particles which depose their energy in the accelerator equipment and finally also in the monitoring detector. To allow an efficient protection of the equipment, the likely loss locations have to be identified by tracking simulations or by using low intensity beams. If superconducting magnets are used for the beam guiding system, not only a damage protection is required but also quench preventions. The quench levels for high field magnets are several orders of magnitude below the damage levels. To keep the operational efficiency high under such circumstances, the calibration factor between the energy deposition in the coils and the energy deposition in the detectors has to be accurately known. To allow a reliable damage protection and quench prevention, the mean time between failures should be high. If in such failsafe system the number of monitors is numerous, the false dump probability has to be kept low to keep a high operation...

Assessment of physical protection systems: EVA method

International Nuclear Information System (INIS)

Bernard, J.-L.; Lamotte, C.; Jorda, A.

2001-01-01

CEA's missions in various sectors of activity such as nuclear, defence, industrial contracts and the associated regulatory requirements, make it necessary to develop a strategy in the field of physical protection. In particular, firms having nuclear materials are subject to the July 25, 1980 law no.80-572 on the protection and control of nuclear materials. A holding permit delivered by the regulatory authority is conditioned to the protection by the operator of the nuclear materials used. In France it is the nuclear operator who must demonstrate, in the form of a security study, that potential aggressors would be neutralised before they could escape with the material. To meet these requirements, we have developed methods to assess the vulnerability of our facilities. The EVA method, the French acronym for 'Evaluation de la vulnerabilite des Acces' (access vulnerability system) allows dealing with internal and external threats involving brutal actions. In scenarios relating to external threat, the intruders get past the various barriers of our protection system, attempting to steal a large volume of material in one swoop and then escape. In the case of internal threat, the goal is the same. However, as the intruder usually has access to the material in the scope of his activities, the action begins at the level of the target. Our protection system is based on in-depth defense where the intruders are detected and then delayed in their advance towards their target to allow time for intervention forces to intercept them

Design and fabrication of a 30 T superconducting solenoid using overpressure processed Bi2212 round wire

Energy Technology Data Exchange (ETDEWEB)

Flanagan, Gene [Muons, Inc., Batavia, IL (United States); Johnson, Rolland [Muons, Inc., Batavia, IL (United States)

2016-02-18

High field superconducting magnets are used in particle colliders, fusion energy devices, and spectrometers for medical imaging and advanced materials research. Magnets capable of generating fields of 20-30 T are needed by future accelerator facilities. A 20-30 T magnet will require the use of high-temperature superconductors (HTS) and therefore the challenges of high field HTS magnet development need to be addressed. Superconducting Bi₂Sr₂CaCu₂O_x (Bi2212) conductors fabricated by the oxide-powder-in-tube (OPIT) technique have demonstrated the capability to carry large critical current density of 10⁵ A/cm² at 4.2 K and in magnetic fields up to 45 T. Available in round wire multi-filamentary form, Bi2212 may allow fabrication of 20-50 T superconducting magnets. Until recently the performance of Bi2212 has been limited by challenges in realizing high current densities (J_c ) in long lengths. This problem now is solved by the National High Magnetic Field Lab using an overpressure (OP) processing technique, which uses external pressure to process the conductor. OP processing also helps remove the ceramic leakage that results when Bi-2212 liquid leaks out from the sheath material and reacts with insulation, coil forms, and flanges. Significant advances have also been achieved in developing novel insulation materials (TiO₂ coating) and Ag-Al sheath materials that have higher mechanical strengths than Ag-0.2wt.% Mg, developing heat treatment approaches to broadening the maximum process temperature window, and developing high-strength, mechanical reinforced Bi-2212 cables. In the Phase I work, we leveraged these new opportunities to prototype overpressure processed solenoids and test them in background fields of up to 14 T. Additionally a design of a fully superconducting 30 T solenoid was produced. This work in conjunction with the future path outlined in the Phase II proposal would

Fail-safe computer-based plant protection systems

International Nuclear Information System (INIS)

Keats, A.B.

1983-01-01

A fail-safe mode of operation for computers used in nuclear reactor protection systems was first evolved in the UK for application to a sodium cooled fast reactor. The fail-safe properties of both the hardware and the software were achieved by permanently connecting test signals to some of the multiplexed inputs. This results in an unambiguous data pattern, each time the inputs are sequentially scanned by the multiplexer. The ''test inputs'' simulate transient excursions beyond defined safe limits. The alternating response of the trip algorithms to the ''out-of-limits'' test signals and the normal plant measurements is recognised by hardwired pattern recognition logic external to the computer system. For more general application to plant protection systems, a ''Test Signal Generator'' (TSG) is used to compute and generate test signals derived from prevailing operational conditions. The TSG, from its knowledge of the sensitivity of the trip algorithm to each of the input variables, generates a ''test disturbance'' which is superimposed upon each variable in turn, to simulate a transient excursion beyond the safe limits. The ''tripped'' status yielded by the trip algorithm when using data from a ''disturbed'' input forms part of a pattern determined by the order in which the disturbances are applied to the multiplexer inputs. The data pattern formed by the interleaved test disturbances is again recognised by logic external to the protection system's computers. This fail-safe mode of operation of computer-based protection systems provides a powerful defence against common-mode failure. It also reduces the importance of software verification in the licensing procedure. (author)

Heat Exchange in “Human body - Thermal protection - Environment” System

Science.gov (United States)

Khromova, I. V.

2017-11-01

This article is devoted to the issues of simulation and calculation of thermal processes in the system called “Human body - Thermal protection - Environment” under low temperature conditions. It considers internal heat sources and convective heat transfer between calculated elements. Overall this is important for the Heat Transfer Theory. The article introduces complex heat transfer calculation method and local thermophysical parameters calculation method in the system called «Human body - Thermal protection - Environment», considering passive and active thermal protections, thermophysical and geometric properties of calculated elements in a wide range of environmental parameters (water, air). It also includes research on the influence that thermal resistance of modern materials, used in special protective clothes development, has on heat transfer in the system “Human body - Thermal protection - Environment”. Analysis of the obtained results allows adding of the computer research data to experiments and optimizing of individual life-support system elements, which are intended to protect human body from exposure to external factors.

A Fall Protection System for High-Rise Construction

Directory of Open Access Journals (Sweden)

Haluk Çeçen

2013-01-01

Full Text Available In construction industry, the number of fatal and nonfatal occupational injuries is higher than other industries. Among causes of these accidents, “falls” play a key role. This situation reveals the importance for carrying out research in fall protection systems. In this paper, a practical, economical, and functional fall protection system is introduced. Following determination and evaluation of existing solutions, weekly brainstorming meetings were held among the responsible project staff (general coordinator, project coordinator, project manager, site manager, and health and safety manager. As a result of these meetings, design criteria were developed. Based on these criteria, the fall protection system for high-rise construction (FPSFHC was developed which satisfied all the specified design criteria. Required materials were procured from local dealers. In this paper, criteria used in design and details of the final design are presented. Field performance of the system is evaluated, and recommendations for further development and standardization of the system are added.

Reactor protection systems for the Replacement Research Reactor, ANSTO

International Nuclear Information System (INIS)

Morris, C.R.

2003-01-01

The 20-MW Replacement Research Reactor Project which is currently under construction at ANSTO will have a combination of a state of the art triplicated computer based reactor protection system, and a fully independent, and diverse, triplicated analogue reactor protection system, that has been in use in the nuclear industry, for many decades. The First Reactor Protection System (FRPS) consists of a Triconex triplicated modular redundant system that has recently been approved by the USNRC for use in the USA?s power reactor program. The Second Reactor Protection System is a hardwired analogue system supplied by Foxboro, the Spec 200 system, which is also Class1E qualified. The FRPS is used to drop the control rods when its safety parameter setpoints have been reached. The SRPS is used to drain the reflector tank and since this operation would result in a reactor poison out due to the time it would take to refill the tank the FRPS trip setpoints are more limiting. The FRPS and SRPS have limited hardwired indications on the control panels in the main control room (MCR) and emergency control centre (ECC), however all FRPS and SRPS parameters are capable of being displayed on the reactor control and monitoring system (RCMS) video display units. The RCMS is a Foxboro Series I/A control system which is used for plant control and monitoring and as a protection system for the cold neutron source. This paper will provide technical information on both systems, their trip logics, their interconnections with each other, and their integration into the reactor control and monitoring system and control panels. (author)

Design of the interlock and protection system for the SPIDER experiment

International Nuclear Information System (INIS)

Pomaro, N.; Grando, L.; Luchetta, A.; Paolucci, F.; Sartori, F.

2013-01-01

Highlights: •A custom designed interlock and protection system for SPIDER experiment is described. •It includes two subsystems implementing slow and fast protection functions. •High reliability PLCs are adopted for slow protection. •Fiber-optic based, custom designed fast logic circuitry is proposed for fast protection. •Accelerators breakdown events are also managed by the fast subsystem. -- Abstract: Unprecedented levels of beam energy and power are required for ITER Neutral Beam Heating systems. SPIDER experiment is an experimental device aimed to test and optimize a full size beam source satisfying ITER requirements. SPIDER experiment operation involves high power, voltage, temperature, and gas pressure. All these critical conditions are present simultaneously, so that any failure if not properly detected and managed is likely to cause severe damage. The Interlock and Protection System is a high-reliability system devoted to the investment protection of SPIDER. Its main purpose is to manage abnormal events occurring in one or more plants in order to minimize adverse consequences. The Interlock System also manages the SPIDER Operating Modes, defining the set and status of the Plants used in the various possible experimental configurations. In addition, the Interlock and Protection System takes care of particular events occurring during normal SPIDER operation, i.e. electrical arcs between accelerator grids, named breakdowns. Their treatment is committed to the Interlock and Protection System, as they need to be managed timely and with absolute reliability like actual faults. To perform the required functions, the Interlock and Protection System is interfaced with most SPIDER plants and with the SPIDER Control and Data Acquisition System. The paper describes the rationale of the protection functions, their implementation in the design and the technical specifications of the system

Sub-assembly accident protection instrumentation systems

International Nuclear Information System (INIS)

Vaughan, G.J.; Lunt, A.R.W.; Evans, N.J.; Lawrence, L.A.J.

1982-01-01

The possibility of an incident in a sub-assembly progressing to the stage at which the whole core may be at hazard has to be guarded against. It is proposed that for CDFR specific instrumentation will be provided to protect against this incident. Three such systems are described, these are: Acoustic Boiling Noise Detection, Burst Pin Detection and Individual Sub-Assembly Thermocouple (ISAT) monitoring. In the ISAT case, multiplexers and microprocessors are employed, using novel techniques to ensure failure-to-safety. The role of these systems and the implementation of them in the reactor design are also considered. It is concluded that sufficient protection can be provided for both core and breeder sub-assemblies

On line protection systems for induction motors

International Nuclear Information System (INIS)

Colak, I.; Celik, H.; Sefa, I.; Demirbas, S.

2005-01-01

Protection of induction motors is very important since they are widely used in industry for many applications due to their high robustness, reliability, low cost and maintenance, high efficiency and long service life. So, protecting these motors is crucial for operations. This paper presents a combined protection approach for induction motors. To achieve this, the electrical values of the induction motor were measured with sensitivity ±1% through a data acquisition card and processed with software developed in Visual C++. An on line protection system for induction motors was achieved easily and effectively. The experimental results have shown that the induction motor was protected against the possible problems faced during the operation. The software developed for this protection provides flexible and reliable media for operators and their motors. It is expected that the motor protection achieved in this study might be faster than the classical techniques and also may be applied to larger motors easily after small modifications of the software

Safety Analysis for Power Reactor Protection System

International Nuclear Information System (INIS)

Eisawy, E.A.; Sallam, H.

2012-01-01

The main function of a Reactor Protection System (RPS) is to safely shutdown the reactor and prevents the release of radioactive materials. The purpose of this paper is to present a technique and its application for used in the analysis of safety system of the Nuclear Power Plant (NPP). A more advanced technique has been presented to accurately study such problems as the plant availability assessments and Technical Specifications evaluations that are becoming increasingly important. The paper provides the Markov model for the Reactor Protection System of the NPP and presents results of model evaluations for two testing policies in technical specifications. The quantification of the Markov model provides the probability values that the system will occupy each of the possible states as a function of time.

Problems in creating enviroment and health protection systems

International Nuclear Information System (INIS)

Vorob'ev, E.I.; Reznichenko, V.Yu.

1981-01-01

The problems in creating environmental and health protection systems are considered with relation to development of nuclear energetics facilities. A problem of transition from the system of detection and observation to the uniform system of environment and health protection and control is set. The objectives and problems of such a system are analyzed and the basic principles of their construction are outlined. A system conception for a fuel energetic complex is described. Usefulness of such systems in solving problems of sites of industrial objects including nuclear power industrial objects, of removal of these objects from service and etc. is shown. New requirements to medical-biological investigations on designing of such a system are discussed [ru

Protective systems and its protective switching elements on local failures of large slow-capacitor bank system

International Nuclear Information System (INIS)

Hasegawa, Mitsuo; Inoue, Kunikazu; Ueno, Isao.

1994-01-01

In various applications of pulsed power technologies, large capacitor bank systems are used to feed high current impulse to different experimental devices. The accidental electric breakdown in one of the capacitors in a parallel connection of the large bank may result in serious damages such as mechanical explosion and oil effusion or fire. In most fast banks, each unit capacitor has an output gap switch, which is expected to decouple the capacitors one another. However, no such special element is adopted usually in the slow bank system, partly because of the economical consideration. We have developed a novel and inexpensive protective element for these relatively slow capacitor banks, utilizing a concept of the enclosed type of the fast breakers. The principle of the operation of the protection elements is verified by a simulation experiment. Their practical effectiveness is also successfully demonstrated in the application to the system of the pulsed high magnetic field generator. (author)

Advanced physical protection systems for facilities and transportation

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

Sandia Laboratories is developing advanced physical protection safeguards in order to improve the security of special nuclear materials, facilities, and transportation. Computer models are being used to assess the cost-effectiveness of alternative systems for protecting facilities against external attack which may include internal assistance, and against internal theft or sabotage. Physical protection elements such as admittance controls, portals and detectors, perimeter and interior intrusion alarms, fixed and remotely activated barriers, and secure communications are being evaluated, adapted, and where required, developed. New facilities safeguards concepts which involve ''control loops'' between physical protection and materials control elements are being evolved jointly between Sandia Laboratories and Los Alamos Scientific Laboratory. Special vehicles and digital communications equipment have been developed for the ERDA safe-secure transportation system. The current status and direction of these activities are surveyed

Advanced physical protection systems for facilities and transportation

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

Sandia Laboratories is developing advanced physical protection safeguards in order to improve the security of special nuclear materials, facilities, and transportation. Computer models are being used to assess the cost-effectiveness of alternative systems for protecting facilities against external attack which may include internal assistance, and against internal theft or sabotage. Physical protection elements such as admittance controls, portals and detectors, perimeter and interior intrusion alarms, fixed and remotely-activated barriers, and secure communications are being evaluated, adapted, and where required, developed. New facilities safeguards concepts which involve (control loops) between physical protection and materials control elements are being evolved jointly between Sandia Laboratories and Los Alamos Scientific Laboratory. Special vehicles and digital communications equipment have been developed for the ERDA safe-secure transportation system. The current status and direction of these activities are surveyed

Railway automatic safety protection system based on GPS

Directory of Open Access Journals (Sweden)

Fu Hai Juan

2016-01-01

Full Text Available The automatic protection system of railway safety is designed for the railway construction workers to protect alarm, and the safety protection device by using GPS satellite positioning system to acquire location information of the operating point, through the CTC/TDCS system and computer monitoring system for the running of the train position and the arithmetic distance. Achieving timely and continuously forecasts about the distance of the train which is apart from the operating point to prompt the voice alarm of the approaching train. Using digital technology to realize the function of the traditional analog interphone, eliminates the quality problems of the call. With the GSM-R, mobile wireless transmission channel and terminal technology, it overcomes the restrictions of the analog interphone which influenced by communication distance and more problems of blind areas. Finally to achieve practical, convenient, applicable and adaptable design goals.

Large thermal protection system panel

Science.gov (United States)

Weinberg, David J. (Inventor); Myers, Franklin K. (Inventor); Tran, Tu T. (Inventor)

2003-01-01

A protective panel for a reusable launch vehicle provides enhanced moisture protection, simplified maintenance, and increased temperature resistance. The protective panel includes an outer ceramic matrix composite (CMC) panel, and an insulative bag assembly coupled to the outer CMC panel for isolating the launch vehicle from elevated temperatures and moisture. A standoff attachment system attaches the outer CMC panel and the bag assembly to the primary structure of the launch vehicle. The insulative bag assembly includes a foil bag having a first opening shrink fitted to the outer CMC panel such that the first opening and the outer CMC panel form a water tight seal at temperatures below a desired temperature threshold. Fibrous insulation is contained within the foil bag for protecting the launch vehicle from elevated temperatures. The insulative bag assembly further includes a back panel coupled to a second opening of the foil bag such that the fibrous insulation is encapsulated by the back panel, the foil bag, and the outer CMC panel. The use of a CMC material for the outer panel in conjunction with the insulative bag assembly eliminates the need for waterproofing processes, and ultimately allows for more efficient reentry profiles.

Seismic design criteria of fire protection systems for DOE facilities

International Nuclear Information System (INIS)

Hardy, G.; Cushing, R.; Driesen, G.

1991-01-01

Fire protection systems are critical to the safety of personnel and to the protection of inventory during any kind of emergency situation that involves a fire. The importance of these fire protection systems is hightened for DOE facilities which often house nuclear, chemical or scientific processes. Current research into the topic of open-quotes fires following earthquakesclose quotes has demonstrated that the risks of a fire starting as a result of a major earthquake can be significant. Thus, fire protection systems need to be designed to withstand the anticipated seismic event for the site in question

Fire protection countermeasures for containment ventilation systems

International Nuclear Information System (INIS)

Alvares, N.; Beason, D.; Bergman, V.; Creighton, J.; Ford, H.; Lipska, A.

1980-01-01

The goal of this project is to find countermeasures to protect High Efficiency Particulate Air (HEPA) filters, in exit ventilation ducts, from the heat and smoke generated by fire. Initially, methods were developed to cool fire-heated air by fine water spray upstream of the filters. It was recognized that smoke aerosol exposure to HEPA filters could also cause disruption of the containment system. Through testing and analysis, several methods to partially mitigate the smoke exposure to the HEPA filters were identified. A continuous, movable, high-efficiency prefilter using modified commercial equipment was designed. The technique is capable of protecting HEPA filters over the total time duration of the test fires. The reason for success involved the modification of the prefiltration media. Commercially available filter media has particle sorption efficiency that is inversely proportional to media strength. To achieve properties of both efficiency and strength, rolling filter media were laminated with the desired properties. The approach was Edisonian, but truncation in short order to a combination of prefilters was effective. The application of this technique was qualified, since it is of use only to protect HEPA filters from fire-generated smoke aerosols. It is not believed that this technique is cost effective in the total spectrum of containment systems, especially if standard fire protection systems are available in the space. But in areas of high-fire risk, where the potential fuel load is large and ignition sources are plentiful, the complication of a rolling prefilter in exit ventilation ducts to protect HEPA filters from smoke aerosols is definitely justified

Renovation of the cathodic protection system

NARCIS (Netherlands)

Schuten, G.; Leggedoor, J.; Polder, R.B.; Peelen, W.H.A.

2003-01-01

The first system for Cathodic Protection of concrete in the Netherlands was applied to a one bicycle lane of a bridge suffering corrosion due to de-icing salt penetration in 1986. This CP system was based on the Ferex 100S conducting polymer cable anode in a cementitious overlay. Its functioning was

Impact of Y2K problem on physical protection system

International Nuclear Information System (INIS)

Kumar, R.; Swadia, N.S.; Zanwar, P.S.; Mishra, G.P.; Salunke, A.S.; Nigam, R.K.

1999-01-01

Year 2000 related system failures/problems in Physical Protection System pose no threat to general safety and functioning of any nuclear facility. But there can be potential security threats having radiation safety and non-proliferation concern and hence should be given due importance. Reviewing and testing Physical Protection System for Y2K compliance are easier than other systems as it does not directly affect operation of the plant. The existing emergency response capability at the nuclear facilities should be utilizes effectively to mitigate any Y2K induced events on Physical Protection System with dedicated manpower and channeled efforts

Anode protection system for shutdown of solid oxide fuel cell system

Science.gov (United States)

Li, Bob X; Grieves, Malcolm J; Kelly, Sean M

2014-12-30

An Anode Protection Systems for a SOFC system, having a Reductant Supply and safety subsystem, a SOFC anode protection subsystem, and a Post Combustion and slip stream control subsystem. The Reductant Supply and safety subsystem includes means for generating a reducing gas or vapor to prevent re-oxidation of the Ni in the anode layer during the course of shut down of the SOFC stack. The underlying ammonia or hydrogen based material used to generate a reducing gas or vapor to prevent the re-oxidation of the Ni can be in either a solid or liquid stored inside a portable container. The SOFC anode protection subsystem provides an internal pressure of 0.2 to 10 kPa to prevent air from entering into the SOFC system. The Post Combustion and slip stream control subsystem provides a catalyst converter configured to treat any residual reducing gas in the slip stream gas exiting from SOFC stack.

Analog subsystem for the plutonium protection system

International Nuclear Information System (INIS)

Arlowe, H.D.

1978-12-01

An analog subsystem is described which monitors certain functions in the Plutonium Protection System. Rotary and linear potentiometer output signals are digitized, as are the outputs from thermistors and container ''bulge'' sensors. This work was sponsored by the Department of Energy/Office of Safeguards and Security (DOE/OSS) as part of the overall Sandia Fixed Facility Physical Protection Program

Adoption of digital safety protection system in Japan

International Nuclear Information System (INIS)

Ogiso, Z.

1998-01-01

The application of micro-processor-based digital controllers has been widely propagated among various industries in recent years. While in the nuclear power plant industry, the application of them has also been expanding gradually starting from non-safety related systems, taking advantage of their reliability and maintainability over the conventional analog devices. Based on the careful study of the feasibility of digital controllers to the safety protection system, the Tokyo Electric Power Company proposed on May 1989 the adoption of digital controllers to the safety protection system in the Application for Permission of Establishment of Kashiwazaki-Kariwa units 6 and 7 (ABWR-1350Mwe each). MITI, Ministry of International Trade and Industry, the Japanese regulatory body for electric power generating facilities, had approved this application after careful review. This paper describes a series of supporting activities leading to the MITI's approval of the digital safety protection system and the MITI's licensing activities. (author)

Joint Service Chemical and Biological Defense Program FY 08-09 Overview

Science.gov (United States)

2007-10-01

of human plasma-derived butyrylcholinesterase Electronmicrograph of bacillus spores adhering to cell membrane processes Jo i n t Se rv i c e ch e m i...human performance within CB-protective systems. Carbon monolith for electro-swing adsorption Bacillus globigii spores collecting on an...integrated with the ship’s heating, ventilation, and air-conditioning ( HVAC ) systems and provides a filter air supply air for overpressurization of

14 CFR 25.1316 - System lightning protection.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false System lightning protection. 25.1316... AIRCRAFT AIRWORTHINESS STANDARDS: TRANSPORT CATEGORY AIRPLANES Equipment General § 25.1316 System lightning... systems to perform these functions are not adversely affected when the airplane is exposed to lightning...

NSTX-U Digital Coil Protection System Software Detailed Design

Energy Technology Data Exchange (ETDEWEB)

None

2014-06-01

The National Spherical Torus Experiment (NSTX) currently uses a collection of analog signal processing solutions for coil protection. Part of the NSTX Upgrade (NSTX-U) entails replacing these analog systems with a software solution running on a conventional computing platform. The new Digital Coil Protection System (DCPS) will replace the old systems entirely, while also providing an extensible framework that allows adding new functionality as desired.

Fault Identification Algorithm Based on Zone-Division Wide Area Protection System

OpenAIRE

Xiaojun Liu; Youcheng Wang; Hub Hu

2014-01-01

As the power grid becomes more magnified and complicated, wide-area protection system in the practical engineering application is more and more restricted by the communication level. Based on the concept of limitedness of wide-area protection system, the grid with complex structure is divided orderly in this paper, and fault identification and protection action are executed in each divided zone to reduce the pressure of the communication system. In protection zone, a new wide-area...

Microsoft System Center Data Protection Manager 2012

CERN Document Server

Buchannan, Steve; Gomaa, Islam

2013-01-01

This book is a Packt tutorial, walking the administrator through the steps needed to create real solutions to the problems and tasks faced when ensuring that their data is protected. This book is for network administrators, system administrators, backup administrators, or IT consultants who are looking to expand their knowledge on how to utilize DPM to protect their organization's data.

78 FR 66384 - Membership of the Merit Systems Protection Board's Performance Review Board

Science.gov (United States)

2013-11-05

... MERIT SYSTEMS PROTECTION BOARD Membership of the Merit Systems Protection Board's Performance Review Board AGENCY: Merit Systems Protection Board. ACTION: Notice. SUMMARY: Notice is hereby given of the members of the Merit Systems Protection Board's Performance Review Board. DATES: November 5, 2013...

Design and implementation based on the classification protection vulnerability scanning system

International Nuclear Information System (INIS)

Wang Chao; Lu Zhigang; Liu Baoxu

2010-01-01

With the application and spread of the classification protection, Network Security Vulnerability Scanning should consider the efficiency and the function expansion. It proposes a kind of a system vulnerability from classification protection, and elaborates the design and implementation of a vulnerability scanning system based on vulnerability classification plug-in technology and oriented classification protection. According to the experiment, the application of classification protection has good adaptability and salability with the system, and it also approves the efficiency of scanning. (authors)

Magnetic field generated by lightning protection system

Science.gov (United States)

Geri, A.; Veca, G. M.

1988-04-01

A lightning protection system for today's civil buildings must be electromagnetically compatible with the electronic equipment present in the building. This paper highlights a mathematic model which analyzes the electromagnetic effects in the environment in which the lightning protection system is. This model is developed by means of finite elements of an electrical circuit where each element is represented by a double pole circuit according to the trapezoidal algorithm developed using the finite difference method. It is thus possible to analyze the electromagnetic phenomena associated with the transient effects created by the lightning stroke even for a high-intensity current. Referring to an elementary system comprised of an air terminal, a down conductor, and a ground terminal, numerical results are here laid out.

Practical Approach on Lightning and Grounding Protection System

OpenAIRE

Shan Jose Varghese

2015-01-01

Lightning Protection and Grounding of Electrical and Mechanical equipment’s for the Protection of the Human Beings, Structure of the building and equipment protection, safe working of the Worker at Industry as per my latest practical knowledge in the site environment in extreme climatic condition of low lying areas of the Gulf Region in the challenging projects. All the conductor calculation, Lightning Risk Factor calculations, all the system information regarding the ...

Wireless device for activation of an underground shock wave absorber

Science.gov (United States)

Chikhradze, M.; Akhvlediani, I.; Bochorishvili, N.; Mataradze, E.

2011-10-01

The paper describes the mechanism and design of the wireless device for activation of energy absorber for localization of blast energy in underground openings. The statistics shows that the greatest share of accidents with fatal results associate with explosions in coal mines due to aero-methane and/or air-coal media explosion. The other significant problem is terrorist or accidental explosions in underground structures. At present there are different protective systems to reduce the blast energy. One of the main parts of protective Systems is blast Identification and Registration Module. The works conducted at G. Tsulukidze Mining Institute of Georgia enabled to construct the wireless system of explosion detection and mitigation of shock waves. The system is based on the constant control on overpressure. The experimental research continues to fulfill the system based on both threats, on the constant control on overpressure and flame parameters, especially in underground structures and coal mines. Reaching the threshold value of any of those parameters, the system immediately starts the activation. The absorber contains a pyrotechnic device ensuring the discharge of dispersed water. The operational parameters of wireless device and activation mechanisms of pyrotechnic element of shock wave absorber are discussed in the paper.

Study on pulsed current cathodic protection in a simulated system

Energy Technology Data Exchange (ETDEWEB)

Yan, Milin; Li, Helin [Xi' an Jiao Tong Universitiy (China)]|[Tubular Goods Research Center of China National Petroleum Corp. (China); Qiu, Yubing; Guo, Xingpeng [Hua Zhong University of Science and Techonology (China)

2004-07-01

The pulsed current cathodic protection (PCCP) is a new cathodic protection (CP) technology and shows more advantages over the conventional DC cathodic protection (DCCP) in oil well casing system. However, little information about PCCP is reported. In this research, a simulated CP system was set up in a pool of 3.5 m x 2.0 m x 3.0 m size, in which the effects of the square wave pulsed current (SWPC) parameters (amplitude: IA, frequency: f, duty cycle: P), auxiliary anode distance (d) and media conductivity ({mu}) on the cathodic potential (E) distribution were studied, and the protection effects of PCCP and DCCP were compared. The results show that with increase of the square wave parameters (IA, f, P), the E distribution becomes more negative and the effects of each current parameter are relate closely to the cathode polarizing state. Only with suitable square wave parameters can the whole cathode be effectively protected. With increase of d and {mu}, the E distribution becomes more uniform. Compared with DCCP system, PCCP system has much more uniform E distribution, costs less average current, and gains much better protection effects. Further, the mechanism of PCCP was analyzed. (authors)

Distance Protection for Microgrids in Distribution System

DEFF Research Database (Denmark)

Lin, Hengwei; Liu, Chengxi; Guerrero, Josep M.

2015-01-01

protection decreased. This paper adopts distance protection for one mid-voltage level microgrid in Aalborg, Denmark. Different operation modes of the network are analyzed and tested in the paper. The simulation results show that the variations of the fault currents seen by the forward relays are much larger...... than the backward relays. Meanwhile, the fault currents change little with the randomness of renewable energy except the intermittence. Finally, it shows that the designed distance protection has satisfactory performance to clear the various faults.......Owing to the increasing penetration of distributed generation, there are some challenges for the conventional protection in distribution system. Bidirectional power flow and variable fault current because of the various operation modes may lead to the selectivity and sensitivity of the overcurrent...

Nuclear whistleblower protection system in U.S. and its implication to Japanese regulatory system

International Nuclear Information System (INIS)

Tanabe, Tomoyuki; Suzuki, Tatsujiro

2003-01-01

The nuclear whistleblower protection system in U.S.A consists of two programs: 1) allegation program and 2) whistleblower protection system. The former is explained by basic act, definition of allegation, anonymous allegation, direct allegation to NRC (Nuclear Regulatory Commission), number of allegation from 1997 to 2001, procedure and period of investigation and notice of allegation to licensees. The latter is explained by basis act, outline of the system, enforcement by NRC and DOL (Department of Labor), number of discrimination compliant and anxiety of licensees. The system is good conditions in U.S.A depend on 1) prevent of illegal act and increase, 2) preparation of procedure and its transparency and 3) enforcement system. However, a hostile act to licensees is found in the whistleblower protection system. There are many problems in Japanese regulatory system. The improvement points of Japanese system are proposed. (S.Y.)

Circuit protection of ehv power systems from 150 to 765 kV

Energy Technology Data Exchange (ETDEWEB)

Geise, F; Jaeger, J

1965-11-01

Short tripping times required for all faults in ehv transmission systems are obtained by means of differential and comparative protection arrangements. It is essential that protection and communication systems be closely integrated and that special current transformers with linearized cores supply protective devices with correct measured values. By arranging filters between transformer and directional relay, it is possible to use capacitive voltage transformers for high speed protection. A description of power system with backup protection devices is presented.

ICRP Publication 138: Ethical Foundations of the System of Radiological Protection.

Science.gov (United States)

Cho, K-W; Cantone, M-C; Kurihara-Saio, C; Le Guen, B; Martinez, N; Oughton, D; Schneider, T; Toohey, R; ZöLzer, F

2018-02-01

Despite a longstanding recognition that radiological protection is not only a matter of science, but also ethics, ICRP publications have rarely addressed the ethical foundations of the system of radiological protection explicitly. The purpose of this publication is to describe how the Commission has relied on ethical values, either intentionally or indirectly, in developing the system of radiological protection with the objective of presenting a coherent view of how ethics is part of this system. In so doing, it helps to clarify the inherent value judgements made in achieving the aim of the radiological protection system as underlined by the Commission in Publication 103. Although primarily addressed to the radiological protection community, this publication is also intended to address authorities, operators, workers, medical professionals, patients, the public, and its representatives (e.g. NGOs) acting in the interest of the protection of people and the environment. This publication provides the key steps concerning the scientific, ethical, and practical evolutions of the system of radiological protection since the first ICRP publication in 1928. It then describes the four core ethical values underpinning the present system: beneficence/ non-maleficence, prudence, justice, and dignity. It also discusses how these core ethical values relate to the principles of radiological protection, namely justification, optimisation, and limitation. The publication finally addresses key procedural values that are required for the practical implementation of the system, focusing on accountability, transparency, and inclusiveness. The Commission sees this publication as a founding document to be elaborated further in different situations and circumstances.

Glacially-derived overpressure in the northeastern Alaskan subduction zone: combined tomographic and morphometric analysis of shallow sediments on the Yakutat shelf and slope, Gulf of Alaska

Science.gov (United States)

Clary, W. A.; Worthington, L. L.; Scuderi, L. A.; Daigle, H.; Swartz, J. M.

2017-12-01

The Pamplona zone fold and thrust belt is the offshore expression of convergence and shallow subduction of the Yakutat microplate beneath North America in the northeastern Alaska subduction zone. The combination of convergent tectonics and glaciomarine sedimentary processes create patterns of deformation and deposition resulting in a shallow sedimentary sequence with varying compaction, fluid pressure, and fault activity. We propose that velocity variations observed in our tomographic analysis represent long-lived fluid overpressure due to loading by ice sheets and sediments. Regions with bathymetric and stratigraphic evidence of recent ice sheets and associated sedimentation should be collocated with evidence of overpressure (seismic low velocity zones) in the shallow sediments. Here, we compare a velocity model with shelf seismic stratigraphic facies and modern seafloor morphology. To document glacially derived morphology we use high resolution bathymetry to identify channel and gully networks on the western Yakutat shelf-slope then analyze cross-channel shape indices across the study area. We use channel shape index measurements as a proxy of recent ice-proximal sedimentation based on previously published results that proposed a close correlation. Profiles taken at many locations were fitted with a power function and assigned a shape - U-shape channels likely formed proximal to recent ice advances. Detailed velocity models were created by a combination of streamer tomography and pre-stack depth migration velocities with seismic data including: a 2008 R/V Langseth dataset from the St. Elias Erosion and Tectonics Project (STEEP); and a 2004 high-resolution R/V Ewing dataset. Velocity-porosity-permeability relationships developed using IODP Expedition 341 drilling data inform interpretation and physical properties analyses of the shallow sediments. Initial results from a 35 km profile extending SE seaward of the Bering glacier and subparallel to the Bering trough

Protective garment ventilation system

Science.gov (United States)

Lang, R. (Inventor)

1970-01-01

A method and apparatus for ventilating a protective garment, space suit system, and/or pressure suits to maintain a comfortable and nontoxic atmosphere within is described. The direction of flow of a ventilating and purging gas in portions of the garment may be reversed in order to compensate for changes in environment and activity of the wearer. The entire flow of the ventilating gas can also be directed first to the helmet associated with the garment.

Integration of the environment into the system of radiation protection

International Nuclear Information System (INIS)

Higley, K.

2018-01-01

In 2005 the International Commission on Radiological Protection (ICRP) embarked on an effort to ensure that the system for environmental radiological protection would be reconcilable with that for radiological protection of man, and with the approaches used for protection of the environment from other potential hazards

System Protection Schemes in Eastern Denmark

DEFF Research Database (Denmark)

Rasmussen, Joana

outages in the southern part of the 132-kV system introduce further stress in the power system, eventually leading to a voltage collapse. The local System Protection Scheme against voltage collapse is designed as a response-based scheme, which is dependent on local indication of reactive and active power...... effective measures, because they are associated with large reactive power losses in the transmission system. Ordered reduction of wind generation is considered an effective measure to maintain voltage stability in the system. Reactive power in the system is released due to tripping of a significant amount...... system. In that way, the power system capability could be extended beyond normal limits....

Distance Protection of Cross-Bonded Transmission Cable-Systems

DEFF Research Database (Denmark)

Bak, Claus Leth; F. Jensen, Christian

2014-01-01

In this paper the problems of protecting a cross-bonded cable system using distance protection are analysed. The combination of the desire to expand the high voltage transmission grid and the public's opinion towards new installations of overhead lines (OHL), more and more transmission cable syst...

Structural dynamic and resistance to nuclear air blast

International Nuclear Information System (INIS)

Qureshi, S.M.

2003-01-01

A need exists to design protective shelters attached to specialized facilities against nuclear airbursts, explosive shocks and impacting projectiles. Designing such structures against nuclear and missile impact is a challenging task that needs to be looked into for design methodology formulation and practicability. Structures can be designed for overpressure pulsed generated by a nuclear explosion as well as the scabbing and perforation/punching of an impacting projectile. This paper discuses and formulates the methods of dynamic analysis and design required to undertake such a task. Structural resistance to peak overpressure pulse for a 20 KT weapons and smaller tactical nuclear weapons of 1 KT (16 psi, overpressure) size as a direct air blast overpressure has been considered in design of walls, beams and slabs of a special structure under review. The design of shear reinforcement as lacing is also carried out. Adopting the philosophy of strengthening and hardening can minimize the effect of air blast overpressure and projectile impact. The objective is to avoid a major structural failure. The structure then needs to be checked against ballistic penetration by a range of weapons or be required to resist explosive penetration from the charge detonated in contact with the structure. There is also a dire need to formulate protective guidelines for all existing and future critical facilities. (author)

Evolution of the system of radiological protection

International Nuclear Information System (INIS)

2004-01-01

The development of new radiological protection recommendations by the International Commission on Radiological Protection (ICRP) continues to be a strategically important undertaking, both nationally and internationally. With the growing recognition of the importance of stakeholder aspects in radiological protection decision making, regional and cultural aspects have also emerged as having potentially significant influence on how protection of the public, workers and the environment are viewed. Differing cultural aspects should therefore be considered by the ICRP in its development of new recommendations. Based on this assumption, the NEA organised the Asian Regional Conference on the Evolution of the System of Radiological Protection to express and explore views from the Far East. Held in Tokyo on 24-25 October 2002, the conference included presentations by the ICRP Chair as well as by radiological protection experts from Japan, the Republic of Korea, China and Australia. The distinct views and needs of these countries were discussed in the context of their regional and cultural heritages. These views, along with a summary of the conference results, are presented in these proceedings. (author)

Fault Identification Algorithm Based on Zone-Division Wide Area Protection System

Directory of Open Access Journals (Sweden)

Xiaojun Liu

2014-04-01

Full Text Available As the power grid becomes more magnified and complicated, wide-area protection system in the practical engineering application is more and more restricted by the communication level. Based on the concept of limitedness of wide-area protection system, the grid with complex structure is divided orderly in this paper, and fault identification and protection action are executed in each divided zone to reduce the pressure of the communication system. In protection zone, a new wide-area protection algorithm based on positive sequence fault components directional comparison principle is proposed. The special associated intelligent electronic devices (IEDs zones which contain buses and transmission lines are created according to the installation location of the IEDs. When a fault occurs, with the help of the fault information collecting and sharing from associated zones with the fault discrimination principle defined in this paper, the IEDs can identify the fault location and remove the fault according to the predetermined action strategy. The algorithm will not be impacted by the load changes and transition resistance and also has good adaptability in open phase running power system. It can be used as a main protection, and it also can be taken into account for the back-up protection function. The results of cases study show that, the division method of the wide-area protection system and the proposed algorithm are effective.

Fracture assessment of the Oskarshamn 1 reactor pressure vessel under cold over-pressurization

Energy Technology Data Exchange (ETDEWEB)

Sattari-Far, I. [DNV Technical Consulting AB, Stockholm (Sweden)

2001-03-01

The major motivation of this study was to develop a methodology for fracture assessment of surface defects in the 01 reactor pressure vessel under cold loading scenarios, particularly the cold over-pressurization event. According to a previous study, the FENIX project, the cold over-pressurization of the O1 reactor is a limiting loading case, as the ductile/brittle transition temperature (RT{sub NDT}) of certain welds in the O1 beltline region may be over 100 deg C at the-end-of-life condition. The FENIX project gave values of the acceptable and critical crack depth to be equal to the thickness of the cladding layer (about 6 mm) under this load case using the ASME K{sub Ic} reference curve methodology. This study is aimed to develop a methodology to give a more precise fracture assessment of the O1 reactor under cold loading scenarios. Some of the main objectives of this study have been as below: To prepare a material which can simulate the mechanical properties and RT{sub NDT} of the O1 reactor at the end-of-life conditions. To conduct a fracture mechanics test program to cover the essential influencing factors, such as crack geometry (shallow and deep cracks) and loading condition (uniaxial and biaxial) on the cleavage fracture toughness. To perform fracture mechanics analyses to identify a suitable methodology for assessment of the experimental results. To study the responses of engineering fracture assessment methods to the experimental results from the clad specimens. To propose a fracture assessment procedure for determination of the acceptable and critical flaw sizes in the 01 reactor under the cold loading events. A test program consisted of experiments on standard SEN(B) specimens and clad beams, containing surface cracks was conducted during the course of this project. A total of nine clad beams and clad cruciform specimens were tested under uniaxial and biaxial loading. The test material is reactor steel of type A 508 Grade B, which is specially heat

Mucosal wave characteristics in three voice modes (fry, hiss & overpressure) produced by a female speaker: a preliminary study using stroboscopy, HSDI and analyzed by kymography, P-FFT & Nyquist plots

Science.gov (United States)

Izdebski, Krzysztof; Ward, Ronald R.; Yan, Yuling

2012-02-01

HSDI provides a whole new way to investigate visually intra-laryngeal behavior and posturing during phonation by providing detailed real-time information about laryngeal biomechanics that include observations about mucosal wave, wave motion directionality, glottic area wave form, asymmetry of vibrations within and across vocal folds and contact area of the glottis including posterior commissure closure. These observations are fundamental to our understanding and modeling of both normal and disordered phonation. In this preliminary report we focus on direct HSDI in vivo observations of not only the glottic region, but also on the entire supraglottic laryngeal posturing during fry, breathy/hiss and over-pressured phonation modes produced in a non-pathological settings. Analysis included spatio-temporal vibration patterns of vocal folds, multi-line kymograms, spectral PFFT analysis, and Nyquist spatio-temporal plots. The presented examples reveal that supraglottic contraction assists in prolonged closed phase of the vibratory cycle, and that prolonged closed phase is longest in fry and overpressure and shortest albeit complex in hiss. Hiss also allows for vocal fold vibration despite glottis separation. These findings need to be compared to pathologic phonation representing the three voice modes to derive at better differential diagnosis.

Enhanced personal protection system for the PS

CERN Multimedia

Caroline Duc

2013-01-01

During the first long shutdown (LS1) a new safety system will be installed in the primary beam areas of the PS complex in order to bring the standard of personnel radiation protection at the PS into line with that of the LHC.   Pierre Ninin, deputy group leader of GS-ASE and responsible for the installation of the new PS complex safety system, in front of a new access control system. The LHC access control systems are state-of-the-art, whereas those of the injection chain accelerators were running the risk of becoming obsolete. For the past two years a project to upgrade the access and safety systems of the first links in the LHC accelerator chain has been underway to bring them into compliance with nuclear safety standards. These systems provide the personnel with automatic protection by limiting access to hazardous areas and by ensuring that nobody is present in the areas when the accelerator is in operation. By the end of 2013, the project teams will ha...

Reliability Analysis Study of Digital Reactor Protection System in Nuclear Power Plant

International Nuclear Information System (INIS)

Guo, Xiao Ming; Liu, Tao; Tong, Jie Juan; Zhao, Jun

2011-01-01

The Digital I and C systems are believed to improve a plants safety and reliability generally. The reliability analysis of digital I and C system has become one research hotspot. Traditional fault tree method is one of means to quantify the digital I and C system reliability. Review of advanced nuclear power plant AP1000 digital protection system evaluation makes clear both the fault tree application and analysis process to the digital system reliability. One typical digital protection system special for advanced reactor has been developed, which reliability evaluation is necessary for design demonstration. The typical digital protection system construction is introduced in the paper, and the process of FMEA and fault tree application to the digital protection system reliability evaluation are described. Reliability data and bypass logic modeling are two points giving special attention in the paper. Because the factors about time sequence and feedback not exist in reactor protection system obviously, the dynamic feature of digital system is not discussed

Protection of Distribution Systems with Distributed Energy Resources

DEFF Research Database (Denmark)

Bak-Jensen, Birgitte; Browne, Matthew; Calone, Roberto

of 17 months of work of the Joint Working Group B5/C6.26/CIRED “Protection of Distribution Systems with Distributed Energy Resources”. The working group used the CIGRE report TB421 “The impact of Renewable Energy Sources and Distributed Generation on Substation Protection and Automation”, published...... by WG B5.34 as the entry document for the work on this report. In doing so, the group aligned the content and the scope of this report, the network structures considered, possible islanding, standardized communication and adaptive protection, interface protection, connection schemes and protection...... are listed (chapter 3). The first main part of the report starts with a summary of the backgrounds on DER and current practices in protection at the distribution level (chapter 4). This chapter contains an analysis of CIGRE TB421, protection relevant characteristics of DER, a review of current practices...

Distribution system protection with communication technologies

DEFF Research Database (Denmark)

Wei, Mu; Chen, Zhe

2010-01-01

Due to the communication technologies’ involvement in the distribution power system, the time-critical protection function may be implemented more accurately, therefore distribution power systems’ stability, reliability and security could be improved. This paper presents an active distribution...

Advanced worker protection system. Topical report, Phase I

Energy Technology Data Exchange (ETDEWEB)

Myers, J.

1995-07-01

The Department of Energy (DOE) is in the process of defining the magnitude and diversity of Decontamination and Decommissioning (D&D) obligations at its numerous sites. The DOE believes that existing technologies are inadequate to solve many challenging problems such as how to decontaminate structures and equipment cost effectively, what to do with materials and wastes generated, and how to adequately protect workers and the environment. Preliminary estimates show a tremendous need for effective use of resources over a relatively long period (over 30 years). Several technologies are being investigated which can potentially reduce D&D costs while providing appropriate protection to DOE workers. The DOE recognizes that traditional methods used by the EPA in hazardous waste site clean up activities are insufficient to provide the needed protection and worker productivity demanded by DOE D&D programs. As a consequence, new clothing and equipment which can adequately protect workers while providing increases in worker productivity are being sought for implementation at DOE sites. This project will result in the development of an Advanced Worker Protection System (AWPS). The AWPS will be built around a life support backpack that uses liquid air to provide cooling as well as breathing gas to the worker. The backpack will be combined with advanced protective garments, advanced liquid cooling garment, respirator, communications, and support equipment to provide improved worker protection, simplified system, maintenance, and dramatically improve worker productivity through longer duration work cycles.

OPTIMIZING THE DESIGN OF THE SYSTEMS OF INFORMATION PROTECTION IN AUTOMATED INFORMATIONAL SYSTEMS OF INDUSTRIAL ENTERPRISES

Directory of Open Access Journals (Sweden)

I. E. L'vovich

2014-01-01

Full Text Available Summary. Now to increase of indicators of efficiency and operability of difficult systems apply an automation equipment. The increasing role of information which became universal goods for relationship between various structures is noted. The question of its protection becomes the most actual. Special value is allocated for optimum design at creation of systems of the protection, allowing with the greatest probability to choose the best decisions on a set of alternatives. Now it becomes actual for the majority of the industrial enterprises as correctly designed and introduced system of protection will be pledge of successful functioning and competitiveness of all organization. Stages of works on creation of an information security system of the industrial enterprise are presented. The attention is focused on one of the most important approaches to realization of optimum design – multialternative optimization. In article the structure of creation of system of protection from the point of view of various models is considered, each of which gives an idea of features of design of system as a whole. The special attention is paid to a problem of creation of an information security system as it has the most difficult structure. Tasks for processes of automation of each of design stages of system of information security of the industrial enterprises are designated. Idea of each of stages of works is given at design of system of protection that allows to understand in the best way internal structure of creation of system of protection. Therefore, it is given the chance of evident submission of necessary requirements to creation of a reliable complex of information security of the industrial enterprise. Thereby it is given the chance of leveling of risks at early design stages of systems of protection, the organization and definition of necessary types of hardware-software complexes for future system.

Fire protection system operating experience review for fusion applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1995-12-01

This report presents a review of fire protection system operating experiences from particle accelerator, fusion experiment, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of fire protection system component failure rates and fire accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with these systems are discussed, including spurious operation. This information should be useful to fusion system designers and safety analysts, such as the team working on the Engineering Design Activities for the International Thermonuclear Experimental Reactor

Fire protection system operating experience review for fusion applications

Energy Technology Data Exchange (ETDEWEB)

Cadwallader, L.C.

1995-12-01

This report presents a review of fire protection system operating experiences from particle accelerator, fusion experiment, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of fire protection system component failure rates and fire accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with these systems are discussed, including spurious operation. This information should be useful to fusion system designers and safety analysts, such as the team working on the Engineering Design Activities for the International Thermonuclear Experimental Reactor.

Simulation of overpressure events with a Laguna Verde model for the RELAP code to conditions of extended power up rate; Simulacion de eventos de sobrepresion con un modelo de Laguna Verde para el codigo RELAP a condiciones de aumento de potencia extendido

Energy Technology Data Exchange (ETDEWEB)

Rodriguez H, A.; Araiza M, E.; Fuentes M, L.; Ortiz V, J., E-mail: andres.rodriguez@inin.gob.mx [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2012-10-15

In this work the main results of the simulation of overpressure events are presented using a model of the nuclear power plant of Laguna Verde developed for the RELAP/SCDAPSIM code. As starting point we have the conformation of a Laguna Verde model that represents a stationary state to similar conditions to the operation of the power station with Extended Power Up rate (EPU). The transitory of simulated pressure are compared with those documented in the Final Safety Analysis Report of Laguna Verde (FSAR). The results of the turbine shot transitory with and without by-pass of the main turbine are showed, and the event of closes of all the valves of main vapor isolation. A preliminary simulation was made and with base in the results some adjustments were made for the operation with EPU, taking into account the Operation Technical Specifications of the power station. The results of the final simulations were compared and analyzed with the content in the FSAR. The response of the power station to the transitory, reflected in the model for RELAP, was satisfactory. Finally, comments about the improvement of the model are included, for example, the response time of the protection and mitigation systems of the power station. (Author)

A New GPS-based Digital Protection System for Smart Grids in Loop Structure

Directory of Open Access Journals (Sweden)

X. Liu

2014-12-01

Full Text Available This paper presents a new digital protection system to solve the protection challenges in future smart grids, i.e., fast protection and fault isolation in a loop-structured system with limited magnitude of fault current. The new system combines two protection algorithms, i.e., a differential protection as the primary algorithm and an overcurrent protection as the backup one. The new system uses real-time Ethernet and digital data acquisition techniques to overcome the restriction on data transmission over large grids. The current measurements at different locations are time-synchronized by GPS clocks, and then transmitted to a central computer via the Ethernet. As opposed to digital relays which often contain PMU functionality nowadays, this approach uses time stamps on the instantaneous current values. We build a prototype of the new system on a test-bed. The results from simulations and experiments have demonstrated that the protection system achieves fast and accurate protection.

Design and operation of the quench protection system for the Fermilab tevatron

International Nuclear Information System (INIS)

Martin, P.S.

1989-01-01

The operation of a superconducting accelerator, in addition to cryogenic requirements, introduces a new complexity not present in a conventional accelerator. A method is required for protecting the magnets from possible overheating or overvoltage conditions in the event that some magnets quench, that is, are elevated in temperature so that they are no longer superconducting. The development of that system is the topic of this chapter. Any quench protection system has two very important ingredients. First, it must be designed with sufficient integrity to remain functional even under abnormal circumstances. The magnets must be protected during power failures, for example. Quenches involving a large number of components can also be hazardous because of the redistribution of voltages during the quench. Some of the system integrity can be achieved through redundancy. Frequent testing of critical elements of the system also assures the overall integrity. Second, the quench protection system must protect against damage from quenches regardless of their location or the excitation current at the time. It is not sufficient to protect just the magnet coils; either the leads between magnets must be fully stabilized or the quench protection system must protect them. The next section presents a brief discussion of the basic properties of superconductors and the phenomenon of quench propagation. 10 references, 13 figures

New evaluation system for antisabotage physical protection

International Nuclear Information System (INIS)

Itakura, Shuichiro; Nakagome, Yoshihiro

2008-01-01

The discussion on an appropriate level of physical protection has not been elaborated so far because of the confidentiality of its nature, thus resulting in a lack of consensus on this issue. In view of this context, a new system for the evaluation of antisabotage physical protection systems is proposed in this paper, in which we introduce openness to a certain extent in the process of the evaluation. The proposed system is composed of the following three elements; (1) establishment of an evaluation basis threat (EBT), which should be less strong but more likely to occur than the design basis threat (DBT); (2) employment of realistic standard scenarios in the process of evaluation; (3) disclosure of results of evaluation implemented based on the above EBT and standard scenarios. It is expected that this considerably open system will foment peace of mind among citizens as well as create a deterrent effect that would minimize the occurrence of sabotage on nuclear facilities. (author)

Quantitative evaluation of physical protection system in nuclear power plant

International Nuclear Information System (INIS)

Sun Yahua; Li Bin; Li Shiju

2009-01-01

Based on the prompt detection analysis, this paper introduced one analysis model of intrusion path in nuclear power plant by means of morphology analysis and developed the evaluation software for path model analysis of physical protection system. Quantitative analysis on three elements (detection, delay, and response) of physical protection system was presented with an imaginary intrusion event example in Mac Arthur nuclear center. The results indicated that the path prompt detection analysis worked effectively to find the weak point of the physical protection system in NPP, and meantime we can also get the high cost-effectiveness improved measures. It is an effective approach to evaluate the overall performance of the system. (authors)

Preliminary Uncertainty Analysis for SMART Digital Core Protection and Monitoring System

International Nuclear Information System (INIS)

Koo, Bon Seung; In, Wang Kee; Hwang, Dae Hyun

2012-01-01

The Korea Atomic Energy Research Institute (KAERI) developed on-line digital core protection and monitoring systems, called SCOPS and SCOMS as a part of SMART plant protection and monitoring system. SCOPS simplified the protection system by directly connecting the four RSPT signals to each core protection channel and eliminated the control element assembly calculator (CEAC) hardware. SCOMS adopted DPCM3D method in synthesizing core power distribution instead of Fourier expansion method being used in conventional PWRs. The DPCM3D method produces a synthetic 3-D power distribution by coupling a neutronics code and measured in-core detector signals. The overall uncertainty analysis methodology which is used statistically combining uncertainty components of SMART core protection and monitoring system was developed. In this paper, preliminary overall uncertainty factors for SCOPS/SCOMS of SMART initial core were evaluated by applying newly developed uncertainty analysis method

Multi Agent System Based Adaptive Protection for Dispersed Generation Integrated Distribution Systems

DEFF Research Database (Denmark)

Liu, Leo; Rather, Zakir Hussain; Bak, Claus Leth

2013-01-01

The increasing penetration of dispersed generation (DG) brings challenges to conventional protection approaches of distribution system, mainly due to bi-directional power flow and variable fault current contribution from different generation technology-based DG units. Moreover, the trend......) is proposed. The adaptive protection intelligently adopts suitable settings for the variation of fault current from diversified DG units. Furthermore, the structure of mobile MAS with additional flexibility is capable of adapting the changes of system topology in a short period, e.g. radial/meshed, grid...

Europe's contribution to implementation of a radiation protection system

International Nuclear Information System (INIS)

Lecomte, J.F.

2010-01-01

What is commonly referred to as a radiation protection system is a range of scientific considerations, principles and rules, the aim of which is to contribute to an appropriate level of protection of individuals and the environment against the harmful effects of exposure to ionising radiation, without excessively limiting desirable human activities which can be associated with such exposure (see ICRP Publication 103). This system is essentially based on an international consensus. The European level only concerns the Member States of the Union but it is crucial that it constitute the final, legally binding step prior to the definition of national regulations. The European radiation protection system (the EURATOM Treaty and its derived legislation) is presented below, not from the legal perspective but from a contextual viewpoint. Research activities are not discussed here. (author)

The capacity of Australia's protected-area system to represent threatened species.

Science.gov (United States)

Watson, James E M; Evans, Megan C; Carwardine, Josie; Fuller, Richard A; Joseph, Liana N; Segan, Dan B; Taylor, Martin F J; Fensham, R J; Possingham, Hugh P

2011-04-01

The acquisition or designation of new protected areas is usually based on criteria for representation of different ecosystems or land-cover classes, and it is unclear how well-threatened species are conserved within protected-area networks. Here, we assessed how Australia's terrestrial protected-area system (89 million ha, 11.6% of the continent) overlaps with the geographic distributions of threatened species and compared this overlap against a model that randomly placed protected areas across the continent and a spatially efficient model that placed protected areas across the continent to maximize threatened species' representation within the protected-area estate. We defined the minimum area needed to conserve each species on the basis of the species' range size. We found that although the current configuration of protected areas met targets for representation of a given percentage of species' ranges better than a random selection of areas, 166 (12.6%) threatened species occurred entirely outside protected areas and target levels of protection were met for only 259 (19.6%) species. Critically endangered species were among those with the least protection; 12 (21.1%) species occurred entirely outside protected areas. Reptiles and plants were the most poorly represented taxonomic groups, and amphibians the best represented. Spatial prioritization analyses revealed that an efficient protected-area system of the same size as the current protected-area system (11.6% of the area of Australia) could meet representation targets for 1272 (93.3%) threatened species. Moreover, the results of these prioritization analyses showed that by protecting 17.8% of Australia, all threatened species could reach target levels of representation, assuming all current protected areas are retained. Although this amount of area theoretically could be protected, existing land uses and the finite resources available for conservation mean land acquisition may not be possible or even effective

Robotic system for the servicing of the orbiter thermal protection system

Science.gov (United States)

Graham, Todd; Bennett, Richard; Dowling, Kevin; Manouchehri, Davoud; Cooper, Eric; Cowan, Cregg

1994-01-01

This paper describes the design and development of a mobile robotic system to process orbiter thermal protection system (TPS) tiles. This work was justified by a TPS automation study which identified tile rewaterproofing and visual inspection as excellent applications for robotic automation.

Blast overpressure induced axonal injury changes in rat brainstem and spinal cord

Directory of Open Access Journals (Sweden)

Srinivasu Kallakuri

2015-01-01

Full Text Available Introduction: Blast induced neurotrauma has been the signature wound in returning soldiers from the ongoing wars in Iraq and Afghanistan. Of importance is understanding the pathomechansim(s of blast overpressure (OP induced axonal injury. Although several recent animal models of blast injury indicate the neuronal and axonal injury in various brain regions, animal studies related to axonal injury in the white matter (WM tracts of cervical spinal cord are limited. Objective: The purpose of this study was to assess the extent of axonal injury in WM tracts of cervical spinal cord in male Sprague Dawley rats subjected to a single insult of blast OP. Materials and Methods: Sagittal brainstem sections and horizontal cervical spinal cord sections from blast and sham animals were stained by neurofilament light (NF-L chain and beta amyloid precursor protein immunocytochemistry and observed for axonal injury changes. Results: Observations from this preliminary study demonstrate axonal injury changes in the form of prominent swellings, retraction bulbs, and putative signs of membrane disruptions in the brainstem and cervical spinal cord WM tracts of rats subjected to blast OP. Conclusions: Prominent axonal injury changes following the blast OP exposure in brainstem and cervical spinal WM tracts underscores the need for careful evaluation of blast induced injury changes and associated symptoms. NF-L immunocytochemistry can be considered as an additional tool to assess the blast OP induced axonal injury.

The UK nuclear programme: The Sizewell experience

International Nuclear Information System (INIS)

Salter, W.B.

1990-01-01

The current status of the Sizewell 'B' PWR programme and the effect on it of the proposed privatisation of U.K electricity generation is reviewed. Departures from and additions to the Standard Nuclear Unit Power Plant System (SNUPPS) reference plant design are given. These include Reactor Coolant System overpressure protection and the addition of an Emergency Charging System and an Emergency Boration System. Improvements in monitoring Reactor Coolant System water level during refuelling and maintenance shutdown operations are presented. (author)

Expert systems for protective monitoring of facilities

International Nuclear Information System (INIS)

Carr, K.R.

1987-01-01

In complex plants, the possibility of serious operator error always exists to some extent, but, this can be especially true during an experiment or some other unusual exercise. Possible contributing factors to operational error include personnel fatigue, misunderstanding in communication, mistakes in executing orders, uncertainty about the delegated authority, pressure to meet a demanding schedule, and a lack of understanding of the possible consequences of deliberate violations of the facility's established operating procedures. Authoritative reports indicate that most of these factors were involved in the disastrous Russian Chernobyl-4 nuclear reactor accident in April 1986, which, ironically, occurred when a safety experiment was being conducted. Given the computer hardware and software now available for implementing expert systems together with integrated signal monitoring and communications, plant protection could be enhanced by an expert system with extended features to monitor the plant. The system could require information from the operators on a rigidly enforced schedule and automatically log in and report on a scheduled time basis to authorities at a central remote site during periods of safe operation. Additionally, the system could warn an operator or automatically shut down the plant in case of dangerous conditions, while simultaneously notifying independent, responsible, off-site personnel of the action taken. This approach would provide protection beyond that provided by typical facility scram circuits. This paper presents such an approach to implementing an expert system for plant protection, together with specific hardware and software configurations. The Chernobyl accident is used as the basis of discussion

Joint force protection advanced security system (JFPASS) "the future of force protection: integrate and automate"

Science.gov (United States)

Lama, Carlos E.; Fagan, Joe E.

2009-09-01

The United States Department of Defense (DoD) defines 'force protection' as "preventive measures taken to mitigate hostile actions against DoD personnel (to include family members), resources, facilities, and critical information." Advanced technologies enable significant improvements in automating and distributing situation awareness, optimizing operator time, and improving sustainability, which enhance protection and lower costs. The JFPASS Joint Capability Technology Demonstration (JCTD) demonstrates a force protection environment that combines physical security and Chemical, Biological, Radiological, Nuclear, and Explosive (CBRNE) defense through the application of integrated command and control and data fusion. The JFPASS JCTD provides a layered approach to force protection by integrating traditional sensors used in physical security, such as video cameras, battlefield surveillance radars, unmanned and unattended ground sensors. The optimization of human participation and automation of processes is achieved by employment of unmanned ground vehicles, along with remotely operated lethal and less-than-lethal weapon systems. These capabilities are integrated via a tailorable, user-defined common operational picture display through a data fusion engine operating in the background. The combined systems automate the screening of alarms, manage the information displays, and provide assessment and response measures. The data fusion engine links disparate sensors and systems, and applies tailored logic to focus the assessment of events. It enables timely responses by providing the user with automated and semi-automated decision support tools. The JFPASS JCTD uses standard communication/data exchange protocols, which allow the system to incorporate future sensor technologies or communication networks, while maintaining the ability to communicate with legacy or existing systems.

Study on aging management of fire protection system in nuclear power plant

International Nuclear Information System (INIS)

Fang Huasong; Du Yu; Li Jianwen; Shi Haining; Tu Fengsheng

2010-01-01

Fire prevention, fire fighting and fire automatic alarms are three aspects which be included in fire protection system in nuclear power plants. The fire protection system can protect personnel, equipment etc in the fire, so their performance will have a direct influence on the safe operation in nuclear power plants. The disabled accidents caused by aging have happened continuously with the extension of time in the fire protection system, which is the major security risk during the running time in nuclear power plants. In view of the importance of fire protection system and the severity of aging problems, the aging are highly valued by the plant operators and related organizations. Though the feedback of operating experience in nuclear power plant, the impact of the fire-fighting equipment aging on system performance and reliability be assessed, the aging sensitive equipment be selected to carry out the aging analysis and to guide the management and maintenance to guarantee the healthy operation in life time of fire protection system in nuclear power plant. (authors)

Fire protection countermeasures for containment ventilation systems

International Nuclear Information System (INIS)

Alvares, N.J.; Beason, D.G.; Bergman, W.; Ford, H.W.; Lipska, A.E.

1980-01-01

The goal of this project is to find countermeasures to protect HEPA filters in exit ventilation ducts from the heat and smoke generated by fire. Several methods for partially mitigating the smoke exposure to the HEPA filters were identified through testing and analysis. These independently involve controlling the fuel, controlling the fire, and intercepting the smoke aerosol prior to its sorption on the HEPA filter. Exit duct treatment of aerosols is not unusual in industrial applications and involves the use of scrubbers, prefilters, and inertial impaction, depending on the size, distribution, and concentration of the subject aerosol. However, when these unmodified techniques were applied to smoke aerosols from fires on materials, common to experimental laboratories of LLNL, it was found they offered minimal protection to the HEPA filters. Ultimately, a continuous, movable, high-efficiency prefilter using modified commercial equipment was designed. This technique is capable of protecting HEPA filters over the total duration of the test fires. The reason for success involved the modificaton of the prefiltration media. Commercially available filter media has a particle sorption efficiency that is inversely proportional to media strength. To achieve properties of both efficiency and strength, we laminated rolling filter media with the desired properties. It is not true that the use of rolling prefilters solely to protect HEPA filters from fire-generated smoke aerosols is cost effective in every type of containment system, especially if standard fire-protection systems are available in the space. But in areas of high fire risk, where the potential fuel load is large and ignition sources are plentiful, the complication of a rolling prefilter in exit ventilation ducts to protect HEPA filters from smoke aerosols is definitely justified

Response of Soviet VVER-440 accident localization systems to overpressurization

International Nuclear Information System (INIS)

Kulak, R.F.; Fiala, C.; Sienicki, J.J.

1989-01-01

The Soviet designed VVER-440 model V230 and VVER-440 model V213 reactors do not use full containments to mitigate the effects of accidents. Instead, these VVER-440 units employ a sealed set of interconnected compartments, collectively called the accident localization system (ALS), to reduce the release of radionuclides to the atmosphere during accidents. Descriptions of the VVER accident localization structures may be found in the report DOE NE-0084. The objective of this paper is to evaluate the structural integrity of the VVER-440 ALS at the Soviet design pressure, and to determine their response to pressure loadings beyond the design value. Complex, three-dimensional, nonlinear, finite element models were developed to represent the major structural components of the localization systems of the VVER-440 models V230 and V213. The interior boundary of the localization system was incrementally pressurized in the calculations until the prediction of gross failure. 6 refs., 9 figs

Technological measures of protection in the copyright system

Directory of Open Access Journals (Sweden)

Radovanović Sanja

2011-01-01

Full Text Available Digital exploitation of works often exceed the limit to which the holder can control the exploitation of their intellectual creations, and the protection provided by legal norms are, in the era of a fast exchange of information, may prove to be insufficiently effective. For these reasons, the rights holders are increasingly opting for preventive care through placement of physical obstacles to the exploitation of copyright works, generic called technological protection measures (known as digital right management (DRM. Simultaneously with the development of the application of these measures flows the process of finding ways to circumvent them. Therefore, the effectiveness of technological measures depends on exactly the question of their legal protection, which now exists in most of modern legal systems. However, in the normative solutions there are differences, which reflect the problems in finding adequate forms of protection. They mostly stem from the fact that the sanctioning of circumvention (or preparatory actions of technological measures put into the question the purpose of copyright protection in general. Hence, in this paper we tried to point out the normative solutions accepted in modern legal systems and practical implications of what they have. Conclusion that arises is that the legal shaping of technological measures is not completed and that further technological developments open new dilemmas.

Mechanisms of protection of information in computer networks and systems

Directory of Open Access Journals (Sweden)

Sergey Petrovich Evseev

2011-10-01

Full Text Available Protocols of information protection in computer networks and systems are investigated. The basic types of threats of infringement of the protection arising from the use of computer networks are classified. The basic mechanisms, services and variants of realization of cryptosystems for maintaining authentication, integrity and confidentiality of transmitted information are examined. Their advantages and drawbacks are described. Perspective directions of development of cryptographic transformations for the maintenance of information protection in computer networks and systems are defined and analyzed.

Evaluation of road-transit physical protection systems

International Nuclear Information System (INIS)

Gallagher, R.J.; Keeton, S.C.; Stimmell, K.G.; DeLaquil, P. III.

1978-05-01

To assess the overall effectiveness of a transportation physical protection system, computer codes which simulate armed attacks have been developed and are being used to examine a range of issues associated with road transportation systems. The paper discusses the purpose and features of three of these codes, SOURCE (which simulates the initial ambush), SABRES I (which covers the battle) and BARS (which treats the penetration of protective cargo barriers). The use of these methodologies to evaluate the value of additional vehicles, guards, armor and alternative tactics or equipment as a means of improving convoy security has recently been completed. The results which are presented demonstrate that the protection offered by the present commercial regulations for guards and vehicles is probably marginal. This could be substantially increased by the addition of armor to close escort vehicles instead of just the transporter and the use of appropriate tactics. Against the baseline threat of adversaries armed with M-16's, observation and harassment from a modest distance until re-enforcements arrive appears preferable to aggressive assault by the ambushed guard force

Addressing Circuitous Currents MVDC Power Systems Protection

Science.gov (United States)

2017-12-31

Addressing Circuitous Currents MVDC Power Systems Protection 5b. GRANT NUMBER N00014-16-1-3113 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR($) Sd. PROJECT NUMBER...efficiency. A challenge with DC distribution is electrical protection . Z-source DC breakers alt! an pti n b&i g cvr.sidcrcd and this w rk ~xplores...zonal distribution, electric ship 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF a. REPORT b. ABSTRACT c. THIS PAGE ABSTRACT u u u uu 18. NUMBER

A demonstrator for an integrated subway protection system

Science.gov (United States)

Detoma, E.; Capetti, P.; Casati, G.; Billington, S.

2008-04-01

In 2006 SEPA has carried on the installation and tests of a demonstrator for an integrated subway protection system at a new subway station in the Naples, Italy) metropolitan area. Protection of a subway system is a difficult task given the amount of passengers transported every day. The demonstrator has been limited to non-intrusive detection techniques not to impair the passenger flow into the station. The demonstrator integrates several technologies and products that have been developed by SEPA or are already available on the market (MKS Instruments,...). The main purpose is to provide detection capabilities for attempts to introduce radioactive substances in the subway station, in order to foil possible attempts to place a dirty bomb, and threat detection and identification following release of chemical agents. The system integrates additional sensors such as video surveillance cameras and air flow sensing to complement the basic sensors suite. The need to protect sensitive installations such as subway stations has been highlighted by the series of terroristics actions carried out in recent years in the subway in London. However, given the number of passengers of a metro system, it is impossible to propose security techniques operating in ways similar to the screening of passengers in airports. Passengers screening and threat detection and identification must be quick, non-intrusive and capable of screening a large number of passengers to be applicable to mass transit systems. In 2005 SEPA, a small company operating in the field of trains video-surveillance systems and radiation detectors, started developing an integrated system to provide a comprehensive protection to subway stations, based on ready available or off-the-shelf components in order to quickly develop a reliable system with available technology. We ruled out at the beginning any new development in order to speed up the fielding of the system in less than one year. The system was developed with

Modernization of the physical protection system of IPEN-CNEN/SP

International Nuclear Information System (INIS)

Suzuki, F.F.

2001-01-01

Full text: The plans of physical protection of nuclear facilities must be reviewed and updated every two years. A general study of the physical protection system was carried out in order to review and to update the plan of physical protection of IPEN-CNEN/SP. Important alterations accomplished at the institute were considered in the study, as the installation of a cyclotron 30 MeV and the new operation conditions for the nuclear research reactor IEA-RI, that include the increase of its operation power from two to five megawatts and the establishment of the continuous operation by 72 hours weekly. The area of IPEN-CNEN/SP is 478,000 m 2 (101,850 m 2 built area of 107 constructions). The group responsible for the study investigated the performance of the physical protection system and detected some points that could be reinforced at inner and protected areas. The initial step was the evaluation, in loco, of the constructions and physical barriers of inner and protected areas. The performance of the security force personnel on the conventional procedures, as access control to the facilities, control of material flow, area monitoring and patrol, as well as its response for special situation procedures in the case of a physical protection emergency, were evaluated too. The study also focused the communication means used by the security force, as the extension phone lines that are located in each entrance area and in the huts, and the portable VHP radios that are used by the guards. In order to elaborate a programme of modernization of the physical protection system, using the results of the study as basis, an internal committee composed of specialists in physical protection, nuclear safety, operation of reactors and engineering areas was created. The programme elaborated by the committee strengthens the physical protection system by applying the defense in depth concept. At the same time, it attempts to propitiate a balanced protection to minimize the consequences for

Seabed Protection Systems to prevent Scour from High-Speed Ships

OpenAIRE

Evans, G

2010-01-01

This document reviews the scour protection systems required around port structures where these are to be used for the berthing of vessels powered by water jet systems. The development of a scour protection system at Poole Harbour in Dorset has been documented and reviewed and a series of laboratory investigations were then undertaken. This has enabled a greater understanding of the scour mechanisms from the water jet propulsion systems of High Speed Ships. This work has shown t...

The role of privacy protection in healthcare information systems adoption.

Science.gov (United States)

Hsu, Chien-Lung; Lee, Ming-Ren; Su, Chien-Hui

2013-10-01

Privacy protection is an important issue and challenge in healthcare information systems (HISs). Recently, some privacy-enhanced HISs are proposed. Users' privacy perception, intention, and attitude might affect the adoption of such systems. This paper aims to propose a privacy-enhanced HIS framework and investigate the role of privacy protection in HISs adoption. In the proposed framework, privacy protection, access control, and secure transmission modules are designed to enhance the privacy protection of a HIS. An experimental privacy-enhanced HIS is also implemented. Furthermore, we proposed a research model extending the unified theory of acceptance and use of technology by considering perceived security and information security literacy and then investigate user adoption of a privacy-enhanced HIS. The experimental results and analyses showed that user adoption of a privacy-enhanced HIS is directly affected by social influence, performance expectancy, facilitating conditions, and perceived security. Perceived security has a mediating effect between information security literacy and user adoption. This study proposes several implications for research and practice to improve designing, development, and promotion of a good healthcare information system with privacy protection.

A Simple Adaptive Overcurrent Protection of Distribution Systems With Distributed Generation

DEFF Research Database (Denmark)

Mahat, Pukar; Chen, Zhe; Bak-Jensen, Birgitte

2011-01-01

current when the system is connected to the grid and when it is islanded. This paper proposes the use of adaptive protection, using local information, to overcome the challenges of the overcurrent protection in distribution systems with distributed generation. The trip characteristics of the relays...... are updated by detecting operating states (grid connected or island) and the faulted section. The paper also proposes faulted section detection using the time over-current characteristics of the protective relays. Simulation results show that the operating state and faulted section can be correctly identified......A significant increase in the penetration of distributed generation has resulted in a possibility of operating distribution systems with distributed generation in islanded mode. However, over-current protection of an islanded distribution system is still an issue due to the difference in fault...

Protected areas as social-ecological systems: perspectives from resilience and social-ecological systems theory.

Science.gov (United States)

Cumming, Graeme S; Allen, Craig R

2017-09-01

Conservation biology and applied ecology increasingly recognize that natural resource management is both an outcome and a driver of social, economic, and ecological dynamics. Protected areas offer a fundamental approach to conserving ecosystems, but they are also social-ecological systems whose ecological management and sustainability are heavily influenced by people. This editorial, and the papers in the invited feature that it introduces, discuss three emerging themes in social-ecological systems approaches to understanding protected areas: (1) the resilience and sustainability of protected areas, including analyses of their internal dynamics, their effectiveness, and the resilience of the landscapes within which they occur; (2) the relevance of spatial context and scale for protected areas, including such factors as geographic connectivity, context, exchanges between protected areas and their surrounding landscapes, and scale dependency in the provision of ecosystem services; and (3) efforts to reframe what protected areas are and how they both define and are defined by the relationships of people and nature. These emerging themes have the potential to transform management and policy approaches for protected areas and have important implications for conservation, in both theory and practice. © 2017 by the Ecological Society of America.

Protected areas as social-ecological systems: perspectives from resilience and social-ecological systems theory

Science.gov (United States)

Cumming, Graeme S.; Allen, Craig R.

2017-01-01

Conservation biology and applied ecology increasingly recognize that natural resource management is both an outcome and a driver of social, economic, and ecological dynamics. Protected areas offer a fundamental approach to conserving ecosystems, but they are also social-ecological systems whose ecological management and sustainability are heavily influenced by people. This editorial, and the papers in the invited feature that it introduces, discuss three emerging themes in social-ecological systems approaches to understanding protected areas: (1) the resilience and sustainability of protected areas, including analyses of their internal dynamics, their effectiveness, and the resilience of the landscapes within which they occur; (2) the relevance of spatial context and scale for protected areas, including such factors as geographic connectivity, context, exchanges between protected areas and their surrounding landscapes, and scale dependency in the provision of ecosystem services; and (3) efforts to reframe what protected areas are and how they both define and are defined by the relationships of people and nature. These emerging themes have the potential to transform management and policy approaches for protected areas and have important implications for conservation, in both theory and practice.

Interfacing systems LOCAs [Loss of Coolant Accidents] at boiling water reactors

International Nuclear Information System (INIS)

Chu, Tsong-Lun; Fitzpatrick, R.; Stoyanov, S.

1987-01-01

The work presented in this paper was performed by Brookhaven National Laboratory (BNL) in support of Nuclear Regulatory Commission's (NRC) effort towards the resolution of Generic Issue 105 ''Interfacing System Loss of Coolant Accidents (LOCAs) at Boiling Water Reactors (BWRs).'' For BWRs, intersystem LOCA have typically either not been considered in probabilistic risk analyses, or if considered, were judged to contribute little to the risk estimates because of their perceived low frequency of occurrence. However, recent operating experience indicates that the pressure isolation valves (PIVs) in BWRs may not adequately protect against overpressurization of low pressure systems. The objective of this paper is to present the results of a study which analyzed interfacing system LOCA at several BWRs. The BWRs were selected to best represent a spectrum of BWRs in service using industry operating event experience and plant-specific information/configurations. The results presented here include some possible changes in test requirements/practices as well as an evaluation of their reduction potential in terms of core damage frequency

Kinetic Integrated Thermal Protection System (KnITPS)

Data.gov (United States)

National Aeronautics and Space Administration — Use the flexibility and shape formation possibilities inherent in knitting to form thermal protection systems that can be custom fitted to a heat shield carrier...

Fuzzy control applied to nuclear power plant pressurizer system

International Nuclear Information System (INIS)

Oliveira, Mauro V.; Almeida, Jose C.S.

2011-01-01

In a pressurized water reactor (PWR) nuclear power plants (NPPs) the pressure control in the primary loop is very important for keeping the reactor in a safety condition and improve the generation process efficiency. The main component responsible for this task is the pressurizer. The pressurizer pressure control system (PPCS) utilizes heaters and spray valves to maintain the pressure within an operating band during steady state conditions, and limits the pressure changes, during transient conditions. Relief and safety valves provide overpressure protection for the reactor coolant system (RCS) to ensure system integrity. Various protective reactor trips are generated if the system parameters exceed safe bounds. Historically, a proportional-integral derivative (PID) controller is used in PWRs to keep the pressure in the set point, during those operation conditions. The purpose of this study has two main goals: first is to develop a pressurizer model based on artificial neural networks (ANNs); second is to develop a fuzzy controller for the PWR pressurizer pressure, and compare its performance with the P controller. Data from a simulator PWR plant was used to test the ANN and the controllers as well. The reference simulator is a Westinghouse 3-loop PWR plant with a total thermal output of 2785 MWth. The simulation results show that the pressurizer ANN model response are in reasonable agreement with the simulated power plant, and the fuzzy controller built in this study has better performance compared to the P controller. (author)

Fuzzy control applied to nuclear power plant pressurizer system

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Mauro V.; Almeida, Jose C.S., E-mail: mvitor@ien.gov.b, E-mail: jcsa@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2011-07-01

In a pressurized water reactor (PWR) nuclear power plants (NPPs) the pressure control in the primary loop is very important for keeping the reactor in a safety condition and improve the generation process efficiency. The main component responsible for this task is the pressurizer. The pressurizer pressure control system (PPCS) utilizes heaters and spray valves to maintain the pressure within an operating band during steady state conditions, and limits the pressure changes, during transient conditions. Relief and safety valves provide overpressure protection for the reactor coolant system (RCS) to ensure system integrity. Various protective reactor trips are generated if the system parameters exceed safe bounds. Historically, a proportional-integral derivative (PID) controller is used in PWRs to keep the pressure in the set point, during those operation conditions. The purpose of this study has two main goals: first is to develop a pressurizer model based on artificial neural networks (ANNs); second is to develop a fuzzy controller for the PWR pressurizer pressure, and compare its performance with the P controller. Data from a simulator PWR plant was used to test the ANN and the controllers as well. The reference simulator is a Westinghouse 3-loop PWR plant with a total thermal output of 2785 MWth. The simulation results show that the pressurizer ANN model response are in reasonable agreement with the simulated power plant, and the fuzzy controller built in this study has better performance compared to the P controller. (author)

A new hybrid protection system for high-field superconducting magnets

CERN Document Server

Ravaioli, E; Kirby, G; ten Kate, H H J; Verweij, A P

2014-01-01

The new generation of high-field superconducting accelerator magnets poses a challenge concerning the protection of the magnet coil in the case of a quench. The very high stored energy per unit volume requires a fast and efficient quench heating system in order to avoid damage due to overheating. A new protection system for superconducting magnets is presented, comprising a combination of a novel coupling-loss induced quench (CLIQ) system and conventional quench heaters. CLIQ can provoke a very fast transition to the normal state in coil windings by introducing coupling loss and thus heat in the coil's conductor. The advantage of the hybrid protection system is a global transition, resulting in a much faster current decay, a significantly lower hot-spot temperature, and a more homogeneous temperature distribution in the magnet's coil.

Probability analysis of MCO over-pressurization during staging

International Nuclear Information System (INIS)

Pajunen, A.L.

1997-01-01

The purpose of this calculation is to determine the probability of Multi-Canister Overpacks (MCOs) over-pressurizing during staging at the Canister Storage Building (CSB). Pressurization of an MCO during staging is dependent upon changes to the MCO gas temperature and the build-up of reaction products during the staging period. These effects are predominantly limited by the amount of water that remains in the MCO following cold vacuum drying that is available for reaction during staging conditions. Because of the potential for increased pressure within an MCO, provisions for a filtered pressure relief valve and rupture disk have been incorporated into the MCO design. This calculation provides an estimate of the frequency that an MCO will contain enough water to pressurize beyond the limits of these design features. The results of this calculation will be used in support of further safety analyses and operational planning efforts. Under the bounding steady state CSB condition assumed for this analysis, an MCO must contain less than 1.6 kg (3.7 lbm) of water available for reaction to preclude actuation of the pressure relief valve at 100 psid. To preclude actuation of the MCO rupture disk at 150 psid, an MCO must contain less than 2.5 kg (5.5 lbm) of water available for reaction. These limits are based on the assumption that hydrogen generated by uranium-water reactions is the sole source of gas produced within the MCO and that hydrates in fuel particulate are the primary source of water available for reactions during staging conditions. The results of this analysis conclude that the probability of the hydrate water content of an MCO exceeding 1.6 kg is 0.08 and the probability that it will exceed 2.5 kg is 0.01. This implies that approximately 32 of 400 staged MCOs may experience pressurization to the point where the pressure relief valve actuates. In the event that an MCO pressure relief valve fails to open, the probability is 1 in 100 that the MCO would experience

Bubble-vacuum system of accident localization of reference nuclear power plant with two WWER's

International Nuclear Information System (INIS)

Sykora, D.; Sykorova, I.

1988-01-01

Higher efficiency of the safety system for removing the consequences of project design accidents and higher radiation safety of a nuclear power plant with two WWER-440 units is the subject of Czechoslovak patent document 243961. The principle consists in interconnecting air chambers which are the end parts of safety systems for the two units. The air chamber is separated from the other parts of the safety system by double swing-check valves or closures. The connecting pipes of the two air chambers do not in any way reduce the reliability of the safety system thanks to their high technical safety and totally passive function. The benefits of the interconnection of the air chambers are given by the fact that it reduces maximum accident overpressure both in the air chambers and in the airtight zones. The reduction of the overpressure reduces the total leakage of radioactive substances and the radiation burden of the environment in case of a nuclear power plant accident. (Z.M.). 2 figs

Flight envelope protection system for unmanned aerial vehicles

KAUST Repository

Claudel, Christian G.; Shaqura, Mohammad

2016-01-01

Systems and methods to protect the flight envelope in both manual flight and flight by a commercial autopilot are provided. A system can comprise: an inertial measurement unit (IMU); a computing device in data communication with the IMU

PG BN 1600 sodium fire protection system

International Nuclear Information System (INIS)

Bar, J.; Urbancik, L.

1978-12-01

A design was developed of a fire protection system for steam generator of a 1600 MW sodium cooled fast reactor (BN-1600). Chemical reactions are described of liquid sodium with atmospheric components and solid materials coming into contact with sodium in its release from the steam generator, and in safeguarding protection against sodium fires. The requirements for the purity of nitrogen as an atmosphere inert to liquid sodium are given. Characteristics and basic parameters are shown of level and spray fires, elementary terms are explained concerning the properties of aerosols formed during fires, the methods and means of release signalling and fire alarm are described as are fire precautions using fire-fighting equipment, modifying the support tank and the cell bottom and building sewage pits. The design of the system comprises an alarm system for liquid sodium using point and line electric contact sensors and flame photometer based aerosol sensors as well as a fire-fighting system based on the system of channelling liquid sodium into emergency discharge tanks filled with an inert gas, a set of fire extinguishers and other fire fighting material, and measures for the elimination of sodium fire consequences. (J.B.)

Fault-tolerant reactor protection system

International Nuclear Information System (INIS)

Gaubatz, D.C.

1997-01-01

A reactor protection system is disclosed having four divisions, with quad redundant sensors for each scram parameter providing input to four independent microprocessor-based electronic chassis. Each electronic chassis acquires the scram parameter data from its own sensor, digitizes the information, and then transmits the sensor reading to the other three electronic chassis via optical fibers. To increase system availability and reduce false scrams, the reactor protection system employs two levels of voting on a need for reactor scram. The electronic chassis perform software divisional data processing, vote 2/3 with spare based upon information from all four sensors, and send the divisional scram signals to the hardware logic panel, which performs a 2/4 division vote on whether or not to initiate a reactor scram. Each chassis makes a divisional scram decision based on data from all sensors. Each division performs independently of the others (asynchronous operation). All communications between the divisions are asynchronous. Each chassis substitutes its own spare sensor reading in the 2/3 vote if a sensor reading from one of the other chassis is faulty or missing. Therefore the presence of at least two valid sensor readings in excess of a set point is required before terminating the output to the hardware logic of a scram inhibition signal even when one of the four sensors is faulty or when one of the divisions is out of service. 16 figs

Overvoltage protection for magnetic system during disruption in tokamak

International Nuclear Information System (INIS)

Zhang, Ming; Li, Xiaolong; He, Yang; Zhang, Jun; Chen, Zhongyong; Yu, Kexun

2015-01-01

Highlights: • We investigate the way to limit the plasma disruption overvoltage by using the MOVs. • An overvoltage model of plasma disruption is introduced. • The overvoltage protection scheme has been verified by disruption experiments. • The overvoltage during plasma disruption can be limited to 330 V. - Abstract: During a plasma disruption the magnetic flux in the tokamak changes rapidly, which in most cases will cause high-voltage surges among the magnetic systems and may bring severe damage to the components if there is no overvoltage protection. This paper investigates the way to limit the plasma disruption overvoltage and absorb the energy with the use of metal oxide varistors (MOVs). An overvoltage model of plasma disruption is introduced which can be used for the simulation of plasma disruption and the analysis of the overvoltage. The effectiveness of the overvoltage protection system is validated with disruption experiments. It shows that by optimizing the varistors voltage, the overvoltage during plasma disruption can be limited to an ideal low value. Now the overvoltage protection system has been deployed in J-TEXT tokamak and serves well for daily experiments.

Relay Protection and Automation Systems Based on Programmable Logic Integrated Circuits

International Nuclear Information System (INIS)

Lashin, A. V.; Kozyrev, A. V.

2015-01-01

One of the most promising forms of developing the apparatus part of relay protection and automation devices is considered. The advantages of choosing programmable logic integrated circuits to obtain adaptive technological algorithms in power system protection and control systems are pointed out. The technical difficulties in the problems which today stand in the way of using relay protection and automation systems are indicated and a new technology for solving these problems is presented. Particular attention is devoted to the possibility of reconfiguring the logic of these devices, using programmable logic integrated circuits

Advanced digital instrumentation and control system for nuclear power plant protection

International Nuclear Information System (INIS)

Sabino, D.

1997-01-01

The Diverse Protection System (DPS) is described. The DPS is a state-of-the-art digital protection system developed as a back-up to the primary reactor protection system at the Temelin nuclear power plant, featuring a compact hardware design based on VMEbus technology. This technology allows for ease in adding or modifying the number and type of input modules and processors. The DPS software is written in a high level language suitable for safety critical applications. The software is both modular and configurable allowing for potential future modifications and software reuse

Safety analysis of the CSTR-1 bench-scale coal liquefaction unit

Energy Technology Data Exchange (ETDEWEB)

Hulburt, D.A.

1981-05-01

The objective of the program reported herein was to provide a Safety Analysis of the CSTR-1 bench scale unit located in Building 167 at the Pittsburgh Energy Technology Center. It was apparent that considerable effort was expended in the design and construction of the unit, and in the development of operating procedures, with regard to safety. Exhaust ventilation, H/sub 2/ and H/sub 2/S monitoring, overpressure protection, overtemperature protection, and interlock systems have been provided. Present settings on the pressure and temperature safety systems are too high, however, to insure prevention of vessel deformation or damage in all cases. While the occurrence of catastrophic rupture of a system pressure vessel (e.g., reactor, high pressure separators) is unlikely, the potential consequences to personnel are severe. Feasibility of providing shielding for these components should be considered. A more probable mode of vessel failure in the event of overpressure or overtemperature and failure of the safety system is yielding of the closure bolts followed by high pressure flow across the mating surfaces. As a minimum, shielding should be designed to restrict travel of resultant spray. The requirements for personal protective equipment are presently stated in rather broad and general terms in the operating procedures. Safe practices and procedures would be more assured if specific requirements were stated and included for each operational step. Recommendations were developed for all hazards triggered by the guidelines.

Information support systems for cultural heritage protection against flooding

Directory of Open Access Journals (Sweden)

K. Nedvedova

2015-08-01

Full Text Available The goal of this paper is to present use of different kind of software applications to create complex support system for protection of cultural heritage against flooding. The project is very complex and it tries to cover the whole area of the problem from prevention to liquidation of aftermath effects. We used GIS for mapping the risk areas, ontology systems for vulnerability assessment application and the BORM method (Business Object Relation Modelling for flood protection system planning guide. Those modern technologies helped us to gather a lot of information in one place and provide the knowledge to the broad audience.

Political problems in the system of radiation protection laws of Japan

International Nuclear Information System (INIS)

Nakagawa, Haruo

2008-01-01

The lack of hierarchy and multiple restrictions by the radiation protection laws in Japan, causes multiple dose records of individual and scattering dose records. To solve the problem, the National Radiation Dose Registration Systems was proposed already by Atomic Energy Commission about 40 years ago. But only one radiation dose registration system is partly effective, which was applied for workers in nuclear plants. This paper reports political problems in the system of radiation protection laws of Japan, and proposes the new national radiation dose registration systems which will be able to have a function of supplementation of quality assurance of radiation protection laws. (author)

Applying formal method to design of nuclear power plant embedded protection system

International Nuclear Information System (INIS)

Kim, Jin Hyun; Kim, Il Gon; Sung, Chang Hoon; Choi, Jin Young; Lee, Na Young

2001-01-01

Nuclear power embedded protection systems is a typical safety-critical system, which detects its failure and shutdowns its operation of nuclear reactor. These systems are very dangerous so that it absolutely requires safety and reliability. Therefore nuclear power embedded protection system should fulfill verification and validation completely from the design stage. To develop embedded system, various V and V method have been provided and especially its design using Formal Method is studied in other advanced country. In this paper, we introduce design method of nuclear power embedded protection systems using various Formal-Method in various respect following nuclear power plant software development guideline

Hazard rate for a two-channel protective system subject to a high demand rate

International Nuclear Information System (INIS)

Oliveira, L.F.; Youngblood, R.; Melo, P.F.F.

1989-01-01

A basic figure of merit associated with a protective system for an industrial plant is the number of accidents expected to occur in the plant within a given period of time, with the system installed. By definition, in a plant equipped with a protective system, an accident can only happen if an initiating event (a demand) occurs while the protective system is unavailable, that is, while it is in one of its possible failed states. This means that the hazard rate or accident frequency depends on the demand rate and on the unavailability of the protective systems. It has long been recognized that the demand rate influences the unavailability of the protective system, and practical expressions incorporating that effect have been developed for single-channel (Lees, 1982) and multi-channel (Kumamoto and Henley 1978) protective systems. The effect has also been incorporated into a Markovian treatment of a plant protection system (Papazoglou and Cho, 1985). In a previous paper (Oliveira and Netto, 1987) a Markovian approach was used to derive analytical expressions for the evaluation of the plant hazard rate for a single-channel protective system, properly accounting for the effects of the demand and the repair rates. In this paper the authors present an extension of that model to the case of a plant equipped with a two-channel protective system

Dependable Design Flow for Protection Systems using Programmable Logic Devices

CERN Document Server

Kwiatkowski, M

2011-01-01

Programmable Logic Devices (PLD) such as Field Programmable Gate Arrays (FPGA) are becoming more prevalent in protection and safety-related electronic systems. When employing such programmable logic devices, extra care and attention needs to be taken. The final synthesis result, used to generate the bit-stream to program the device, must be shown to meet the design’s requirements. This paper describes how to maximize confidence using techniques such as Formal Methods, exhaustive Hardware Description Language (HDL) code simulation and hardware testing. An example is given for one of the critical functions of the Safe Machine Parameters (SMP) system, used in the protection of the Large Hadron Collider (LHC) at CERN. CERN is also working towards an adaptation of the IEC- 61508 lifecycle designed for Machine Protection Systems (MPS), and the High Energy Physics environment, implementation of a protection function in FPGA code is only one small step of this lifecycle. The ultimate aim of this project is to cre...

Motor drive chassis for the plutonium protection system

International Nuclear Information System (INIS)

Shaut, A.L.

1979-05-01

A motor drive chassis has been developed for use in the Plutonium Protection System. Rotation of the desired carrousel in a secure storage module is controlled by this chassis which supplies the power and drive pulses required by the carrousel motor. This work was sponsored by the Department of Energy/Office of Safeguards and Security (DOE/OSS) as part of the overall Sandia Fixed Physical Protection Program

Large Steel Tank Fails and Rockets to Height of 30 meters - Rupture Disc Installed Incorrectly.

Science.gov (United States)

Hedlund, Frank H; Selig, Robert S; Kragh, Eva K

2016-06-01

At a brewery, the base plate-to-shell weld seam of a 90-m(3) vertical cylindrical steel tank failed catastrophically. The 4 ton tank "took off" like a rocket leaving its contents behind, and landed on a van, crushing it. The top of the tank reached a height of 30 m. The internal overpressure responsible for the failure was an estimated 60 kPa. A rupture disc rated at < 50 kPa provided overpressure protection and thus prevented the tank from being covered by the European Pressure Equipment Directive. This safeguard failed and it was later discovered that the rupture disc had been installed upside down. The organizational root cause of this incident may be a fundamental lack of appreciation of the hazards of large volumes of low-pressure compressed air or gas. A contributing factor may be that the standard piping and instrumentation diagram (P&ID) symbol for a rupture disc may confuse and lead to incorrect installation. Compressed air systems are ubiquitous. The medium is not toxic or flammable. Such systems however, when operated at "slight overpressure" can store a great deal of energy and thus constitute a hazard that ought to be addressed by safety managers.

Hybrid Plasma Reactor/Filter for Transportable Collective Protection Systems

Energy Technology Data Exchange (ETDEWEB)

Josephson, Gary B.; Tonkyn, Russell G.; Frye, J. G.; Riley, Brian J.; Rappe, Kenneth G.

2011-04-06

Pacific Northwest National Laboratory (PNNL) has performed an assessment of a Hybrid Plasma/Filter system as an alternative to conventional methods for collective protection. The key premise of the hybrid system is to couple a nonthermal plasma (NTP) reactor with reactive adsorption to provide a broader envelope of protection than can be provided through a single-solution approach. The first step uses highly reactive species (e.g. oxygen radicals, hydroxyl radicals, etc.) created in a nonthermal plasma (NTP) reactor to destroy the majority (~75% - 90%) of an incoming threat. Following the NTP reactor an O3 reactor/filter uses the O3 created in the NTP reactor to further destroy the remaining organic materials. This report summarizes the laboratory development of the Hybrid Plasma Reactor/Filter to protect against a ‘worst-case’ simulant, methyl bromide (CH3Br), and presents a preliminary engineering assessment of the technology to Joint Expeditionary Collective Protection performance specifications for chemical vapor air purification technologies.

Adaptive Overcurrent Protection for Microgrids in Extensive Distribution Systems

DEFF Research Database (Denmark)

Lin, Hengwei; Guerrero, Josep M.; Jia, Chenxi

2016-01-01

Microgrid is regarded as a new form to integrate the increasing penetration of distributed generation units (DGs) in the extensive distribution systems. This paper proposes an adaptive overcurrent protection strategy for a microgrid network. The protection coordination of the overcurrent relays...... measurements in another neural network model. Reconfigurations can be performed to modify the settings of the on-field relays to enhance the reliable operation for the different operational situations. The test results show that the adaptive overcurrent protection scheme with the assistance of estimation model...... can modify the protective settings for the new operation state accurately and intelligently....

Development of a protection system for high power klystrons in EAST

International Nuclear Information System (INIS)

Feng Jianqiang; Shan Jiafang; Yang Yong; Wang Mao; Wang Dongxia

2010-01-01

The energy dissipated on the electrodes of a klystron can be estimated from maximal breakdown current, value of the arc discharge voltage and time of turning off the power supply. It mainly introduces the design of over-current protection of Klystrons for 2.45 G/2 MW LHCD System on EAST. Circuits triggering by an over-current and ignitrons are adopted to protect klystrons. Experiment results prove that the system can protect klystrons efficiently. (authors)

Random Vibration of Space Shuttle Weather Protection Systems

Directory of Open Access Journals (Sweden)

Isaac Elishakoff

1995-01-01

Full Text Available The article deals with random vibrations of the space shuttle weather protection systems. The excitation model represents a fit to the measured experimental data. The cross-spectral density is given as a convex combination of three exponential functions. It is shown that for the type of loading considered, the Bernoulli-Euler theory cannot be used as a simplified approach, and the structure will be more properly modeled as a Timoshenko beam. Use of the simple Bernoulli-Euler theory may result in an error of about 50% in determining the mean-square value of the bending moment in the weather protection system.

The evolution of the system of radiological protection: the programme of the Nea committee on radiation protection and public health

International Nuclear Information System (INIS)

Mundigl, S.

2004-01-01

The primary aim of radiological protection has always been to provide an appropriate standard of protection for the public and workers without unduly limiting the beneficial practices giving rise to radiation exposure. Over the past few decades, many studies concerning the effects of ionising radiation have been conducted, ranging from those that examine the effects of radiation on individual cells, to epidemiological studies that examine the effects on large populations exposed to different radiation sources. Using information gained from these studies to estimate the consequences of radiation exposure, together with the necessary social and economic judgements, the International Commission on Radiological Protection (ICRP) has put forward a series of recommendations to structure an appropriate system for radiological protection, and to ensure a high standard of protection for the public and for occupational exposed workers. The ICRP system of radiological protection that has evolved over the years now covers many diverse radiological protection issues. Emerging issues have been dealt with more or less on an individual basis resulting in an overall system, which while very comprehensive, is also complex. With such a complex system it is not surprising that some perceived inconsistencies or incoherence may lead to concerns that radiation protection issues are not being adequately addressed. Different stakeholders in decisions involving radiological protection aspects tend to focus on different elements of this perceived incoherence. To advance solutions to these issues, the OECD Nuclear Energy Agency (NEA) has been working for some time to contribute to the evolution of a new radiological protection system, through its Committee on Radiation Protection and Public Health (CRPPH). This group of senior regulators and expert practitioners has, throughout its existence, been interested in the development of recommendations by the ICRP. Recently, this interest has

Application of DIgSILENT POWERFACTORY software for modeling of industrial network relay protection system

OpenAIRE

Sučević Nikola; Milošević Dejan

2016-01-01

This paper presents modeling of industrial network relay protection system using DIgSILENT PowerFactory software. The basis for the model of protection system is a model of a single substation in an industrial network. The paper presents the procedure for modeling of protective devices of 6 kV asynchronous motors, 6/0,4 kV/kV transformers as well as protection in the bus coupler and busbar protection. Protective relay system response for the simulated disturbances is shown in the paper.

Implementation of Pilot Protection System for Large Scale Distribution System like The Future Renewable Electric Energy Distribution Management Project

Science.gov (United States)

Iigaya, Kiyohito

A robust, fast and accurate protection system based on pilot protection concept was developed previously and a few alterations in that algorithm were made to make it faster and more reliable and then was applied to smart distribution grids to verify the results for it. The new 10 sample window method was adapted into the pilot protection program and its performance for the test bed system operation was tabulated. Following that the system comparison between the hardware results for the same algorithm and the simulation results were compared. The development of the dual slope percentage differential method, its comparison with the 10 sample average window pilot protection system and the effects of CT saturation on the pilot protection system are also shown in this thesis. The implementation of the 10 sample average window pilot protection system is done to multiple distribution grids like Green Hub v4.3, IEEE 34, LSSS loop and modified LSSS loop. Case studies of these multi-terminal model are presented, and the results are also shown in this thesis. The result obtained shows that the new algorithm for the previously proposed protection system successfully identifies fault on the test bed and the results for both hardware and software simulations match and the response time is approximately less than quarter of a cycle which is fast as compared to the present commercial protection system and satisfies the FREEDM system requirement.

A Multiagent System-Based Protection and Control Scheme for Distribution System With Distributed-Generation Integration

DEFF Research Database (Denmark)

Liu, Z.; Su, Chi; Hoidalen, Hans

2017-01-01

In this paper, a multi agent system (MAS) based protection and control scheme is proposed to deal with diverse operation conditions in distribution system due to distributed generation (DG) integration. Based on cooperation between DG controller and relays, an adaptive protection and control...... algorithm is designed on converter based wind turbine DG to limit the influence of infeed fault current. With the consideration of DG control modes, an adaptive relay setting strategy is developed to help protective relays adapt suitable settings to different operation conditions caused by the variations...

A control system of radiation protection at HESYRL

International Nuclear Information System (INIS)

Li Yuxiong; Li Juexin; Ning Xinquan

1990-01-01

A control system for radiation protection at Hefei National Synchrotron Radiation Laboratory (HESYRL) consists of three parts. They are a personal radiation safety interlock system, an automatic environmental radiation monitoring system and a data logging and management system for area radiation monitoring. Two-year operating experiments have shown that this system is reasonably designed, reliable, high-sensitive and automatic. The design principle, construction and operating status of each part of the system are introduced

Lightning protection system analysis at Multipurpose Reactor G A. Siwabessy building

International Nuclear Information System (INIS)

Teguh-Sulistyo

2003-01-01

Analysis to the part of lightning protection system at Multi Purpose Reactor GA Siwabessy (RSG-GAS) have been done. Observation examined the damage of some part of the earthing system caused by human error of chemically system. The analysis performed some assumptions and simulations to the points of lightning stroke. From this analysis obtained that the reactor building do not have vertical finial which can protect effectively to the whole reactor building and auxiliary building. Installing some new finials at some places are needed to protect building therefore the reactor building and auxiliary building well safe from lighting stroke

78 FR 49479 - Updates to List of National System of Marine Protected Areas MPAs

Science.gov (United States)

2013-08-14

... System of Marine Protected Areas MPAs AGENCY: National Marine Protected Areas Center (MPA Center), Office... Marine Protected Areas (MPAs). SUMMARY: The National System of Marine Protected Areas (MPAs) provides a... Protected Areas Center (MPA Center). The managing agencies listed above were then asked to make a final...

Tennessee Valley Authority becomes first to install digital process protection system

International Nuclear Information System (INIS)

Miller, W.; Doyle, J.

1991-01-01

Westinghouse Pressurized Water Reactors were originally furnished with analog process protection equipment of various vintages. The older equipment is quickly reaching the point of obsolescence, becoming costly to maintain and operate, its qualification increasingly difficult to achieve. Newer digital-based systems offer improved performance, automatic calibration, and streamlined surveillance test features, as discussed here. For these reasons, the Tennessee Valley Authority installed the world's first digital process protection system, complete with automatic test and calibration features, in its Sequoyah units 1 and 2 last year. The US utility replaced its ageing analog system with Westinghouse Electric's Eagle 21 Process Protection System during a routine maintenance shutdown in a record 23 days. (author)

TECHNICAL BASIS DOCUMENT FOR VENTILATION SYSTEM FILTRATION FAILURE LEADING TO AN UNFILTERED RELEASE

Energy Technology Data Exchange (ETDEWEB)

KOZLOWSKI, S.D.

2005-01-06

This document analyzed three scenarios involving failures of HEPA filtration systems leading to releases from liquid waste tanks. The scenarios are failure due to high temperature (fire), overpressure (filter blowout), and unfiltered release due to filter failure, improper installation. etc.

Alternative High Performance Polymers for Ablative Thermal Protection Systems

Science.gov (United States)

Boghozian, Tane; Stackpoole, Mairead; Gonzales, Greg

2015-01-01

Ablative thermal protection systems are commonly used as protection from the intense heat during re-entry of a space vehicle and have been used successfully on many missions including Stardust and Mars Science Laboratory both of which used PICA - a phenolic based ablator. Historically, phenolic resin has served as the ablative polymer for many TPS systems. However, it has limitations in both processing and properties such as char yield, glass transition temperature and char stability. Therefore alternative high performance polymers are being considered including cyanate ester resin, polyimide, and polybenzoxazine. Thermal and mechanical properties of these resin systems were characterized and compared with phenolic resin.

Application of DIgSILENT POWERFACTORY software for modeling of industrial network relay protection system

Directory of Open Access Journals (Sweden)

Sučević Nikola

2016-01-01

Full Text Available This paper presents modeling of industrial network relay protection system using DIgSILENT PowerFactory software. The basis for the model of protection system is a model of a single substation in an industrial network. The paper presents the procedure for modeling of protective devices of 6 kV asynchronous motors, 6/0,4 kV/kV transformers as well as protection in the bus coupler and busbar protection. Protective relay system response for the simulated disturbances is shown in the paper.

Interfacing system isolation experience review. Final report, August 1991

International Nuclear Information System (INIS)

1991-08-01

A light water reactor power plant has auxiliary systems interconnected with the reactor coolant system that are not designed for reactor operating pressure. These principally include the shutdown heat removal systems and various emergency core cooling injection systems. There are multiple isolation valves that prevent rector vessel pressure from causing overpressurization in low pressure interfacing systems. Combinations of hardware failures or operational errors are necessary to expose these systems to overpressurization. This experience review provides insights regarding the risk that an auxiliary system might become over pressurized from the reactor system. While analyses show that for the pressures involved the probability of auxiliary system failure is low, the auxiliary system conceivably might fail outside of containment while the plant is at power. Such a potential event has come to be called an interfacing system loss of coolant accident (ISLOCA). This report provides a compilation of occurrences where valve leakage, valve failure, or valve mispositioning played a role in the ability to maintain interfacing system isolation. Seventeen U.S. BWR events, twenty three U.S. PWR events and one foreign event are discussed in the report. Eleven of the U.S. BWR events and ten U.S. PWR events are judged to relate directly to the so-called ISLOCA event in that they fulfilled one or more of the failures necessary to cause an ISLOCA. (author)

Understanding of radiation protection in medicine. Pt. 2. Occupational exposure and system of radiation protection

International Nuclear Information System (INIS)

Iida, Hiroji; Yamamoto, Tomoyuki; Shimada, Yasuhiro

1997-01-01

Using a questionnaire we investigated whether radiation protection is correctly understood by medical doctors (n=140) and nurses (n=496). Although medical exposure is usually understood by medical doctors and dentists, their knowledge was found to be insufficient. Sixty-eight percent of medical doctors and 50% of dentists did not know about the system of radiation protection. Dose monitoring was not correctly carried out by approximately 20% of medical staff members, and medical personnel generally complained of anxiety about occupational exposure rather than medical exposure. They did not receive sufficient education on radiation exposure and protection in school. In conclusion, the results of this questionnaire suggested that they do not have adequate knowledge about radiation exposure and protection. The lack of knowledge about protection results in anxiety about exposure. To protect oneself from occupational exposure, individual radiation doses must be monitored, and medical practice should be reconsidered based on the results of monitoring. To eliminate unnecessary medical and occupational exposure and to justify practices such as radiological examinations, radiation protection should be well understood and appropriately carried out by medical doctors and dentists. Therefore, the education of medical students on the subject of radiation protection is required as is postgraduate education for medical doctors, dentists and nurses. (author)

Overvoltage protection system for wireless power transfer systems

Science.gov (United States)

Chambon, Paul H.; Jones, Perry T.; Miller, John M.; Onar, Omer C.; Tang, Lixin; White, Clifford P.

2017-05-02

A wireless power transfer overvoltage protection system is provided. The system includes a resonant receiving circuit. The resonant receiving circuit includes an inductor, a resonant capacitor and a first switching device. The first switching device is connected the ends of the inductor. The first switching device has a first state in which the ends of the inductor are electrically coupled to each other through the first switching device, and a second state in which the inductor and resonant capacitor are capable of resonating. The system further includes a control module configured to control the first switching device to switching between the first state and the second state when the resonant receiving circuit is charging a load and a preset condition is satisfied and otherwise, the first switching device is maintained in the first state.

Protection issues on microgrid/distributed generation based systems

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Angelo R. [Centro Federal de Educacao Tecnologica de Minas Gerais (CEFET-MG), Belo Horizonte, MG (Brazil); Ribeiro, Paulo F. [Calvin College, Grand Rapids, MI (United States). Dept. of Electrical Engineering; Iung, Anderson M. [Geracao Paranapanema S.A., SP (Brazil). Duke Energy International. Market Analysis Dept.; Garcia, Paulo A.N. [Federal University of Juiz de Fora (UFJF), MG (Brazil). Dept. of Circuits

2009-07-01

This paper aims to discuss protection issues related to the presence of distributed generation (DG) in distribution systems. A case study is developed to show some impacts of transitions and operations with relay static settings to verify the reliability of systems in the presence of DG. (author)

Status of physical protection systems of nuclear facilities; survey report

International Nuclear Information System (INIS)

Hwang, In Koo; Kwack, Eun Ho; Ahn, Jin Soo; Lee, Hyun Chul; Kim, Jung Soo

2002-02-01

This report presents a survey on the physical protection equipment for a nuclear power plant. This survey was conducted by Korea Atomic Energy Research Institute as a part of the project, 'Development of Technologies for National Control of and Accountancy for Nuclear Material,' funded by the Ministry of Science and Technology of Korea. A physical protection system of a nuclear plant includes outer and inner fences, intrusion detection sensors, alarm generation system, illumination equipment, central monitoring and control station, entry control and management system, etc. The outermost fence indicates the boundary of the plant area and prevents a simple or unintentional intrusion. The inner fence area of each plant unit associated with intrusion detection sensors, illuminators, monitoring cameras, serves the key role for physical protection function for the nuclear plant

76 FR 36863 - Special Conditions: Gulfstream Model GVI Airplane; Electronic Systems Security Protection From...

Science.gov (United States)

2011-06-23

... Security Protection From Unauthorized External Access AGENCY: Federal Aviation Administration (FAA), DOT... for Gulfstream GVI airplanes. 1. The applicant must ensure electronic system security protection for... that effective electronic system security protection strategies are implemented to protect the airplane...

Study of Physical Protection System at PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Ligam, A.S.; Ina, I.; Zarina Masood

2016-01-01

Physical protection program at PUSPATI TRIGA Reactor (RTP) which is located at Nuklear Malaysia, Bangi Complex has been strengthened and upgraded from time to time to accommodate current situation needs. However, there is always room for improvement. Hence, study have been made to look deeper into physical protection components such as delay systems, external sensors, PPS intruder alarm sensors, use of video system, personnel security or insider threats, access control operation system operation rules and security culture that may need to take into consideration. (author)

Overpressure generation by load transfer following shale framework weakening due to smectite diagenesis

Science.gov (United States)

Lahann, R.W.; Swarbrick, R.E.

2011-01-01

Basin model studies which have addressed the importance of smectite conversion to illite as a source of overpressure in the Gulf of Mexico have principally relied on a single-shale compaction model and treated the smectite reaction as only a fluid-source term. Recent fluid pressure interpretation and shale petrology studies indicate that conversion of bound water to mobile water, dissolution of load-bearing grains, and increased preferred orientation change the compaction properties of the shale. This results in substantial changes in effective stress and fluid pressure. The resulting fluid pressure can be 1500-3000psi higher than pressures interpreted from models based on shallow compaction trends. Shale diagenesis changes the mineralogy, volume, and orientation of the load-bearing grains in the shale as well as the volume of bound water. This process creates a weaker (more compactable) grain framework. When these changes occur without fluid export from the shale, some of the stress is transferred from the grains onto the fluid. Observed relationships between shale density and calculated effective stress in Gulf of Mexico shelf wells confirm these changes in shale properties with depth. Further, the density-effective stress changes cannot be explained by fluid-expansion or fluid-source processes or by prediagenesis compaction, but are consistent with a dynamic diagenetic modification of the shale mineralogy, texture, and compaction properties during burial. These findings support the incorporation of diagenetic modification of compaction properties as part of the fluid pressure interpretation process. ?? 2011 Blackwell Publishing Ltd.

Additional reactor protection system of RBMK-1500

International Nuclear Information System (INIS)

1999-01-01

Analysis of anticipated transients without scram of RBMK-1500 reactor showed that additional reactor protection system is required. Data of accident analysis in the case of loose of external electric power and loose of vacuum in condensers of turbines are provided

Distributed Computations Environment Protection Using Artificial Immune Systems

Directory of Open Access Journals (Sweden)

A. V. Moiseev

2011-12-01

Full Text Available In this article the authors describe possibility of artificial immune systems applying for distributed computations environment protection from definite types of malicious impacts.

Optimizing survivability of multi-state systems with multi-level protection by multi-processor genetic algorithm

International Nuclear Information System (INIS)