Comparison of Ruska and Rosemont pressure gages (U)

International Nuclear Information System (INIS)

Harvel, C.D.

1991-01-01

This paper reports that a 150,000 gallon tank was calibrated during the months of May and July of 1990. Six calibration runs were completed. Ruska and Rosemont pressure gages were installed to make in-tank liquid level measurements during the calibration process. A flow meter was used to measure the incremental volumes of water added to or removed from the tank. The Ruska and Rosemont gages were compared to determine the gage best suited for tank operation. One comparison criteria was the tolerance limits of error (LOE) for the predicted standardized in-tank volumes. For accountability purposes, the effects of the two gages on the LOE for the predicted inventory of U-235 were evaluated. The most important comparison criteria was the gage's contribution to the U-235 inventory LOE. The choice of which gage to use depends on the other measurement methods used for material accountability. The contributions to the inventory LOE were evaluated for two in-tank liquid level measurement methods, two concentration measurement methods, and one isotopic measurement method. The results indicate the Ruska pressure gage is best suited for tank operation only if the best concentration measurement method is used

GAGES: A stream gage database for evaluating natural and alteredflow conditions in the conterminous United States

Science.gov (United States)

Falcone, James A.; Carlisle, Daren M.; Wolock, David M.; Meador, Michael R.

2010-01-01

Stream flow is a controlling element in the ecology of rivers and streams. Knowledge of the natural flow regime facilitates the assessment of whether specific hydrologic attributes have been altered by humans in a particular stream and the establishment of specific goals for stream-flow restoration. Because most streams are ungaged or have been altered by human influences, characterizing the natural flow regime is often only possible by estimating flow characteristics based on nearby stream gages of reference quality, i.e., gaged locations that are least disturbed by human influences. The ability to evaluate natural stream flow, that which is not altered by human activities, would be enhanced by the existence of a nationally consistent and up-to-date database of gages in relatively undisturbed watersheds.

Stage measurement at gaging stations

Science.gov (United States)

Sauer, Vernon B.; Turnipseed, D. Phil

2010-01-01

Stream and reservoir stage are critical parameters in the computation of stream discharge and reservoir volume, respectively. In addition, a record of stream stage is useful in the design of structures that may be affected by stream elevation, as well as for the planning for various uses of flood plains. This report describes equipment and methodology for the observation, sensing, and recording of stage in streams and reservoirs. Although the U.S. Geological Survey (USGS) still uses the traditional, basic stilling-well float system as a predominant gaging station, modern electronic stage sensors and water-level recorders are now commonly used. Bubble gages coupled with nonsubmersible pressure transducers eliminate the need for stilling wells. Submersible pressure transducers have become common in use for the measurement of stage in both rivers and lakes. Furthermore, noncontact methods, such as radar, acoustic, and laser methods of sensing water levels, are being developed and tested, and in the case of radar, are commonly used for the measurement of stage. This report describes commonly used gaging-station structures, as well as the design and operation of gaging stations. Almost all of the equipment and instruments described in this report will meet the accuracy standard set by the USGS Office of Surface Water (OSW) for the measurement of stage for most applications, which is ±0.01 foot (ft) or 0.2 percent of the effective stage. Several telemetry systems are used to transmit stage data from the gaging station to the office, although satellite telemetry has become the standard. These telemetry systems provide near real-time stage data, as well as other information that alerts the hydrographer to extreme or abnormal events, and instrument malfunctions.

Gage for measuring coastal erosion and sedimentation

Science.gov (United States)

Carpini, T. D.; Moughon, W. C.

1970-01-01

Underwater sand height gage, which measures heights up to 12 inches, is comprised of two standard flush-diaphragm pressure transducers. Gage is very sensitive to buried water heights and is useful as a research tool in study of wet earth and landslide phenomena.

Evaluation results of the 700 deg C Chinese strain gages

Science.gov (United States)

Hobart, H. F.

1984-01-01

There is a continuing interest and need for resistance strain gages capable of making static strain measurements on components located in the hot section of gas turbine engines. A paper by Tsen-tai Wu describes the development and evaluation of high temperature gauges fabricated from specially developed Fe-Cr-Al-V-Ti-Y alloy wire. Several of these gages and a quantity of P12-2 ceramic adhesive were purchased for evaluation. Nine members of the aircraft turbine engine community were invited to participate in an evaluation of these gages. Each participant was sent one strain gage, a small amount of ceramic adhesive, instructions for mounting the gage on a test beam, and a set of suggestions for the experiment. Data on gage factor variation with temperature, apparent strain, and drift are discussed.

A new strain gage method for measuring the contractile strain ratio of Zircaloy tubing

International Nuclear Information System (INIS)

Hwang, S.K.; Sabol, G.P.

1988-01-01

An improved strain gage method for determining the contractile strain ratio (CSR) of Zircaloy tubing was developed. The new method consists of a number of load-unload cyclings at approximately 0.2% plastic strain interval. With this method the CSR of Zircaloy-4 tubing could be determined accurately because it was possible to separate the plastic strains from the elastic strain involvement. The CSR values determined by use of the new method were in good agreement with those calculated from conventional post-test manual measurements. The CSR of the tubing was found to decrease with the amount of deformation during testing because of uneven plastic flow in the gage section. A new technique of inscribing gage marks by use of a YAG laser is discussed. (orig.)

Low pressure gage type VM-01

International Nuclear Information System (INIS)

Brandea, I.; Curuia, M.; Culcer, M.

2000-01-01

High vacuum systems became an important element of many applied technologies, from gas analysers to rocket engines. An intelligent apparatus for pressure measurement in the range of 10 -3 - 10 -8 mbar, with incorporated INTEL 80C51 microcontroller is presented. Based on a Bayard-Alpert hot cathode gage, equally developed in our institute, the pressure gage allows the displaying of different operation parameters and also of the error codes for different kinds of malfunctioning, as for instance missing of grid voltage, grid-collector breakdown, pressure increasing above 10 -3 mbar. Its operation is based on a microcontroller assembly language program especially worked out and introduced in the central units EPROM memory. The gage characteristics for different gases are also introduced in an EPROM memory, and the type of the gas is selected by the operator from the front panel. One can select also from the front panel the pressure unit (mbar, torr, Pa). If a remote control is necessary, this can be done by means of a PC, with a program written in the LabVIEW graphical programming language. The pressure gage was tested and calibrated in relation with an EDWARDS vacuum measuring system and provided a good accuracy (better than 25%). Its field of application is both laboratory and industrial measurements. Its main features are: - supply voltage, 220 V ac / 50 Hz; - power consumption, 30 W; - gage's grid supply voltage, 160 V; grid current, 2 mA / p = 10 -5 ...10 -8 mbar and 0.2 mA / p = 10 -3 ...10 -5 mbar; - cathode heating current, max. 3 A; - measuring range, 10 -3 ...10 -8 mbar; - error of measurement, ±35%; - remote control, according to the RS232 standard; - size, 320 x 200 x 100 mm; - weight, 3.5 Kg. (authors)

Vision system for dial gage torque wrench calibration

Science.gov (United States)

Aggarwal, Neelam; Doiron, Theodore D.; Sanghera, Paramjeet S.

1993-11-01

In this paper, we present the development of a fast and robust vision system which, in conjunction with the Dial Gage Calibration system developed by AKO Inc., will be used by the U.S. Army in calibrating dial gage torque wrenches. The vision system detects the change in the angular position of the dial pointer in a dial gage. The angular change is proportional to the applied torque. The input to the system is a sequence of images of the torque wrench dial gage taken at different dial pointer positions. The system then reports the angular difference between the different positions. The primary components of this vision system include modules for image acquisition, linear feature extraction and angle measurements. For each of these modules, several techniques were evaluated and the most applicable one was selected. This system has numerous other applications like vision systems to read and calibrate analog instruments.

Theory and Practice of Shear/Stress Strain Gage Hygrometry

Science.gov (United States)

Shams, Qamar A.; Fenner, Ralph L.

2006-01-01

Mechanical hygrometry has progressed during the last several decades from crude hygroscopes to state-of-the art strain-gage sensors. The strain-gage devices vary from different metallic beams to strain-gage sensors using cellulose crystallite elements, held in full shear restraint. This old technique is still in use but several companies are now actively pursuing development of MEMS miniaturized humidity sensors. These new sensors use polyimide thin film for water vapor adsorption and desorption. This paper will provide overview about modern humidity sensors.

Restriction of GAGE protein expression to subpopulations of cancer cells is independent of genotype and may limit the use of GAGE proteins as targets for cancer immunotherapy

DEFF Research Database (Denmark)

Gjerstorff, M F; Johansen, L E; Nielsen, O

2006-01-01

The GAGE cancer testis antigen gene family encodes products that can be recognized by autologous T cells, and GAGE proteins have been suggested as potential targets for cancer immunotherapy. Analysis of GAGE expression in tumours has primarily been performed at the level of gene transcription, wh...

Improving Streamflow Simulation in Gaged and Ungaged Areas Using a Multi-Model Synthesis Combined with Remotely-Sensed Data and Estimates of Uncertainty

Science.gov (United States)

Lafontaine, J.; Hay, L.

2015-12-01

The United States Geological Survey (USGS) has developed a National Hydrologic Model (NHM) to support coordinated, comprehensive and consistent hydrologic model development, and facilitate the application of hydrologic simulations within the conterminous United States (CONUS). More than 1,700 gaged watersheds across the CONUS were modeled to test the feasibility of improving streamflow simulations in gaged and ungaged watersheds by linking statistically- and physically-based hydrologic models with remotely-sensed data products (i.e. - snow water equivalent) and estimates of uncertainty. Initially, the physically-based models were calibrated to measured streamflow data to provide a baseline for comparison. As many stream reaches in the CONUS are either not gaged, or are substantially impacted by water use or flow regulation, ancillary information must be used to determine reasonable parameter estimations for streamflow simulations. In addition, not all ancillary datasets are appropriate for application to all parts of the CONUS (e.g. - snow water equivalent in the southeastern U.S., where snow is a rarity). As it is not expected that any one data product or model simulation will be sufficient for representing hydrologic behavior across the entire CONUS, a systematic evaluation of which data products improve simulations of streamflow for various regions across the CONUS was performed. The resulting portfolio of calibration strategies can be used to guide selection of an appropriate combination of simulated and measured information for model development and calibration at a given location of interest. In addition, these calibration strategies have been developed to be flexible so that new data products or simulated information can be assimilated. This analysis provides a foundation to understand how well models work when streamflow data is either not available or is limited and could be used to further inform hydrologic model parameter development for ungaged areas.

SAF line pellet gaging

International Nuclear Information System (INIS)

Jedlovec, D.R.; Bowen, W.W.; Brown, R.L.

1983-10-01

Automated and remotely controlled pellet inspection operations will be utilized in the Secure Automated Fabrication (SAF) line. A prototypic pellet gage was designed and tested to verify conformance to the functions and requirements for measurement of diameter, surface flaws and weight-per-unit length

The role of GAGE cancer/testis antigen in metastasis

DEFF Research Database (Denmark)

Gjerstorff, Morten Frier; Terp, Mikkel Green; Hansen, Malene Bredahl

2016-01-01

with migratory and invasive properties and were found to be upregulated in cancer cells with metastasizing potential in a gastric cancer model. METHODS: We have addressed the direct role of GAGE proteins in supporting metastasis using an isogenic metastasis model of human cancer, consisting of 4 isogenic cell......) and moderately metastatic clones (LM3), stable downregulation of GAGE expression did not affect the ability of CL16 cells to establish primary tumors and form metastasis in the lungs of immunodeficient mice. CONCLUSIONS: These results suggest that GAGE proteins per se do not support metastasis and that further...

Development of Displacement Gages Exposed to Solid Rocket Motor Internal Environments

Science.gov (United States)

Bolton, D. E.; Cook, D. J.

2003-01-01

The Space Shuttle Reusable Solid Rocket Motor (RSRM) has three non-vented segment-to-segment case field joints. These joints use an interference fit J-joint that is bonded at assembly with a Pressure Sensitive Adhesive (PSA) inboard of redundant O-ring seals. Full-scale motor and sub-scale test article experience has shown that the ability to preclude gas leakage past the J-joint is a function of PSA type, joint moisture from pre-assembly humidity exposure, and the magnitude of joint displacement during motor operation. To more accurately determine the axial displacements at the J-joints, two thermally durable displacement gages (one mechanical and one electrical) were designed and developed. The mechanical displacement gage concept was generated first as a non-electrical, self-contained gage to capture the maximum magnitude of the J-joint motion. When it became feasible, the electrical displacement gage concept was generated second as a real-time linear displacement gage. Both of these gages were refined in development testing that included hot internal solid rocket motor environments and simulated vibration environments. As a result of this gage development effort, joint motions have been measured in static fired RSRM J-joints where intentional venting was produced (Flight Support Motor #8, FSM-8) and nominal non-vented behavior occurred (FSM-9 and FSM-10). This data gives new insight into the nominal characteristics of the three case J-joint positions (forward, center and aft) and characteristics of some case J-joints that became vented during motor operation. The data supports previous structural model predictions. These gages will also be useful in evaluating J-joint motion differences in a five-segment Space Shuttle solid rocket motor.

Behavior of porous beryllium under thermomechanical loading. Part 7. Calibration studies on the carbon piezoresistive gage

International Nuclear Information System (INIS)

Horning, R.R.; Isbell, W.M.

1975-01-01

The calibrations, time responses, and Hugoniot for carbon piezoresistive gages from two manufacturers are presented. These gages exhibit a high sensitivity of about --20 percent resistance change per GPa at 0.5 GPa. Their equilibrium times, when tested in fused silica, exceed 0.6 μs below 0.5 GPa but improve at higher stresses and under better impedance matching conditions. They can be made of low atomic number materials, making them interesting candidates for studying the mechanical responses of materials to electron and x-ray deposition. (U.S.)

Standard Test Method for Measuring Heat Flux Using Flush-Mounted Insert Temperature-Gradient Gages

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This test method describes the measurement of the net heat flux normal to a surface using gages inserted flush with the surface. The geometry is the same as heat-flux gages covered by Test Method E 511, but the measurement principle is different. The gages covered by this standard all use a measurement of the temperature gradient normal to the surface to determine the heat that is exchanged to or from the surface. Although in a majority of cases the net heat flux is to the surface, the gages operate by the same principles for heat transfer in either direction. 1.2 This general test method is quite broad in its field of application, size and construction. Two different gage types that are commercially available are described in detail in later sections as examples. A summary of common heat-flux gages is given by Diller (1). Applications include both radiation and convection heat transfer. The gages used for aerospace applications are generally small (0.155 to 1.27 cm diameter), have a fast time response ...

Comparison of NEXRAD multisensor precipitation estimates to rain gage observations in and near DuPage County, Illinois, 2002–12

Science.gov (United States)

Spies, Ryan R.; Over, Thomas M.; Ortel, Terry W.

2018-05-21

In this report, precipitation data from 2002 to 2012 from the hourly gridded Next-Generation Radar (NEXRAD)-based Multisensor Precipitation Estimate (MPE) precipitation product are compared to precipitation data from two rain gage networks—an automated tipping bucket network of 25 rain gages operated by the U.S. Geological Survey (USGS) and 51 rain gages from the volunteer-operated Community Collaborative Rain, Hail, and Snow (CoCoRaHS) network—in and near DuPage County, Illinois, at a daily time step to test for long-term differences in space, time, and distribution. The NEXRAD–MPE data that are used are from the fifty 2.5-mile grid cells overlying the rain gages from the other networks. Because of the challenges of measuring of frozen precipitation, the analysis period is separated between days with or without the chance of freezing conditions. The NEXRAD–MPE and tipping-bucket rain gage precipitation data are adjusted to account for undercatch by multiplying by a previously determined factor of 1.14. Under nonfreezing conditions, the three precipitation datasets are broadly similar in cumulative depth and distribution of daily values when the data are combined spatially across the networks. However, the NEXRAD–MPE data indicate a significant trend relative to both rain gage networks as a function of distance from the NEXRAD radar just south of the study area. During freezing conditions, of the USGS network rain gages only the heated gages were considered, and these gages indicate substantial mean undercatch of 50 and 61 percent compared to the NEXRAD–MPE and the CoCoRaHS gages, respectively. The heated USGS rain gages also indicate substantially lower quantile values during freezing conditions, except during the most extreme (highest) events. Because NEXRAD precipitation products are continually evolving, the report concludes with a discussion of recent changes in those products and their potential for improved precipitation estimation. An appendix

Utilizing Photogrammetry and Strain Gage Measurement to Characterize Pressurization of an Inflatable Module

Science.gov (United States)

Valle, Gerard D.; Selig, Molly; Litteken, Doug; Oliveras, Ovidio

2012-01-01

This paper documents the integration of a large hatch penetration into an inflatable module. This paper also documents the comparison of analytical load predictions with measured results utilizing strain measurement. Strain was measured by utilizing photogrammetric measurement and through measurement obtained from strain gages mounted to selected clevises that interface with the structural webbings. Bench testing showed good correlation between strain measurement obtained from an extensometer and photogrammetric measurement especially after the fabric has transitioned through the low load/high strain region of the curve. Test results for the full-scale torus showed mixed results in the lower load and thus lower strain regions. Overall strain, and thus load, measured by strain gages and photogrammetry tracked fairly well with analytical predictions. Methods and areas of improvements are discussed.

Water level monitoring device in nuclear reactor

International Nuclear Information System (INIS)

Miura, Kiyohide; Otake, Tomohiro.

1988-01-01

Purpose: To monitor the water level in a pressure vessel of BWR type nuclear reactors at high accuracy by improving the compensation functions. Constitution: In the conventional water level monitor in a nuclear reactor, if the pressure vessel is displaced by the change of the pressure in the reactor or the temperature of the reactor water, the relative level of the reference water head in a condensation vessel is changed to cause deviation between the actual water level and the indicated water level to reduce the monitoring accuracy. According to the invention, means for detecting the position of the reference water head and means for detection the position in the condensation vessel are disposed to the pressure vessel. Then, relative positional change between the condensation vessel and the reference water head is calculated based on detection sinals from both of the means. The water level is compensated and calculated by water level calculation means based on the relative positional change, water level signals from the level gage and the pressure signals from the pressure gage. As a result, if the pressure vessel is displaced due to the change of the temperature or pressure, it is possible to measure the reactor water level accurately thereby remakably improve the reliability for the water level control in the nuclear reactor. (Horiuchi, T.)

Evaluation test on stability of high temperature strain gage

Energy Technology Data Exchange (ETDEWEB)

Sato, Toshimi (Kyowa Electronic Instruments Co. Ltd., Tokyo (Japan)); Ito, Haruhiko; Tanaka, Isao; Komori, Yoshihiro

1983-08-01

This report deals with the results on a stability test of high temperature strain gage which is utilized for development of the Stethoscope for OGL - 1 Components in Elevated Temperature Services (ab. SOCETS). The test has proved that the weldable strain gage (KHC - 20 - G5) exhibits excellent stability at 500/sup 0/C during 3000 to 4000 hours service and can be applied sufficiently to evaluate integrity of OGL - 1 high temperature pipings and others.

Evaluation test on stability of high temperature strain gage

International Nuclear Information System (INIS)

Sato, Toshimi; Ito, Haruhiko; Tanaka, Isao; Komori, Yoshihiro.

1983-01-01

This report deals with the results on a stability test of high temperature strain gage which is utilized for development of the Stethoscope for OGL - 1 Components in Elevated Temperature Services (ab. SOCETS). The test has proved that the weldable strain gage (KHC - 20 - G5) exhibits excellent stability at 500 0 C during 3000 to 4000 hours service and can be applied sufficiently to evaluate integrity of OGL - 1 high temperature pipings and others. (author)

Suitability of Strain Gage Sensors for Integration into Smart Sport Equipment: A Golf Club Example.

Science.gov (United States)

Umek, Anton; Zhang, Yuan; Tomažič, Sašo; Kos, Anton

2017-04-21

Wearable devices and smart sport equipment are being increasingly used in amateur and professional sports. Smart sport equipment employs various sensors for detecting its state and actions. The correct choice of the most appropriate sensor(s) is of paramount importance for efficient and successful operation of sport equipment. When integrated into the sport equipment, ideal sensors are unobstructive, and do not change the functionality of the equipment. The article focuses on experiments for identification and selection of sensors that are suitable for the integration into a golf club with the final goal of their use in real time biofeedback applications. We tested two orthogonally affixed strain gage (SG) sensors, a 3-axis accelerometer, and a 3-axis gyroscope. The strain gage sensors are calibrated and validated in the laboratory environment by a highly accurate Qualisys Track Manager (QTM) optical tracking system. Field test results show that different types of golf swing and improper movement in early phases of golf swing can be detected with strain gage sensors attached to the shaft of the golf club. Thus they are suitable for biofeedback applications to help golfers to learn repetitive golf swings. It is suggested that the use of strain gage sensors can improve the golf swing technical error detection accuracy and that strain gage sensors alone are enough for basic golf swing analysis. Our final goal is to be able to acquire and analyze as many parameters of a smart golf club in real time during the entire duration of the swing. This would give us the ability to design mobile and cloud biofeedback applications with terminal or concurrent feedback that will enable us to speed-up motor skill learning in golf.

Measurement of aerosol concentration with a beta-ray gage

International Nuclear Information System (INIS)

Auzac, G. d'; Dubillot, J.

1978-01-01

Because dusts in suspension are a dangerous polluting agent, several methods have been used to monitor their concentration. Among these, the beta-ray gage enjoys a privileged position. The authors describe such a gage and discuss the conditions to be observed for it to be capable of giving results comparable to those obtained with manual gravimetric methods. The satisfactory results obtained led to standardization of the method and a whole range of instruments based on this principle are employed in pollution supervising networks and for continuously monitoring industrial emissions [fr

Latin square three dimensional gage master

Science.gov (United States)

Jones, Lynn L.

1982-01-01

A gage master for coordinate measuring machines has an nxn array of objects distributed in the Z coordinate utilizing the concept of a Latin square experimental design. Using analysis of variance techniques, the invention may be used to identify sources of error in machine geometry and quantify machine accuracy.

Latin-square three-dimensional gage master

Science.gov (United States)

Jones, L.

1981-05-12

A gage master for coordinate measuring machines has an nxn array of objects distributed in the Z coordinate utilizing the concept of a Latin square experimental design. Using analysis of variance techniques, the invention may be used to identify sources of error in machine geometry and quantify machine accuracy.

Dynamic testing of POSI-SEAL motor-operated butterfly valves using strain gages

International Nuclear Information System (INIS)

Richard, M.C.; Chiou, D.

1994-01-01

Utilities operating nuclear power plants recognize that the correct functioning of all motor-operated valves, and particularly those in safety-related systems, is of paramount importance. The U.S. Nuclear Regulatory Commission has issued Generic Letter 89-10 relative to this concern. Operability must be demonstrated under design-basis conditions. In order to demonstrate operability of motor-operated butterfly valves, the valve stem torque must be determined. The valve stem torque is a function of seat material, stem packing, stem bearing friction, and hydrodynamic lift and drag. The total valve operating hydrodynamic torque can be predicted using the valve manufacturer's data and the differential pressure. In order to validate the valve manufacturer's data, the actual total valve hydrodynamic torque is measured using strain gages mounted directly on the valve stem. This paper presents the results of comparing the predicted total valve operating hydrodynamic torque with the actual total valve operating hydrodynamic torque for six POSI-SEAL Class 150 high performance butterfly valves

Investigation of factors affecting the calibration of strain gage based transducers (''Goodzeit gages'') for SSC magnets

International Nuclear Information System (INIS)

Davidson, M.; Gilbertson, A.; Dougherty, M.

1991-03-01

These transducers are designed to measure stresses on SSC collared coils. They are individually calibrated with a bonded ten-stack of SSC inner coil cable by applying a known load and reading corresponding output from the gages. The transducer is supported by a notched ''backing plate'' that allows for bending of the gage beam during calibration or in use with an actual coil. Several factors affecting the calibration and use of the transducers are: the number of times a ''backing plate'' is used, the similarities or difficulties between bonded ten-stacks, and the differences between the ten-stacks and the coil they represent. The latter is probably the most important because a calibration curve is a model of how a transducer should react within a coil. If the model is wrong, the calibration curve is wrong. Information will be presented regarding differences in calibrations between Brookhaven National Labs (also calibrating these transducers) and Fermilab -- what caused these differences, the investigation into the differences between coils and ten-stacks and how they relate to transducer calibration, and some suggestions for future calibrations

Testing for moisture content in foods by neutron gaging

International Nuclear Information System (INIS)

Helf, S.

1976-01-01

Neutron gaging was applied to the testing for moisture content in bulk powdered foods and in canned Army field rations. The technique is based on the moderation or thermalization of fast neutrons by hydrogenous matter and the measurement of thermal neutron intensity as a function of moisture content. A small californium-252 capsule, of approximate output 10 7 neutrons per second, was used as the source of fast neutrons. It is concluded that a fast neutron moderation technique is feasible for the nondestructive measurement or control of moisture or both in near-dry bulk powdered foods. Samples must be measured under identical geometric conditions, that is, uniform bulk density and volume using a standard metal container or cell. For canned or otherwise prepacked rations, measurement of moisture is interfered with by variations in fill weight among cans or packages of the same product. A gamma-ray attenuation gaging method proved to be of insufficient sensitivity to correct for fill weight variation and was further complicated by nonuniformity in can wall dimensions. Neutron gaging, however, appears to be quite useful for monitoring a standard packaged item for fill weight since the neutron signal is virtually unaffected by variations in container dimensions. The radiation dose imparted to a sample or package of food subjected to such a test is judged to pose no threat to humans from subsequent consumption of the food. An estimate is given for the cost range of a commercial neutron gage and of encapsulated radioisotopic neutron sources

Skin-friction measurements with hot-wire gages

Science.gov (United States)

Houdeville, R.; Juillen, J. C.; Cousteix, J.

1983-11-01

The development of two hot-wire gauges for implantation in wind-tunnel models and their application to the measurement of skin-friction phenomena are reported. The measurement principle is explained; the design and calibration of a single-wire gage containing a thermocouple for temperature determination (Cousteix and Juillen, 1982-1983) are summarized; and sample results for 2D and 3D flows with positive pressure gradients are shown. An advanced design employing a thin hot film deposited on an 80-micron-diameter quartz fiber extending into a 1-mm-sq 0.8-mm-deep cavity is characterized and demonstrated on a pulsed flow on a flat plate, Tollmien-Schlichting waves, and a turbulent boundary layer. Two cold-wire temperature sensors are added to this gage to permit detection of the skin of the skin friction in the separated flow over a cylinder.

Nickel--chromium strain gages for cryogenic stress analysis of superconducting structures in high magnetic fields

International Nuclear Information System (INIS)

Freynik, H.S. Jr.; Roach, D.R.; Deis, D.W.; Hirzel, D.G.

1977-01-01

Evaluation and calibration measurements were performed on commercial nickel-chromium metal-foil strain gages in a high-magnetic-field (12 T), liquid-helium (4.2 K) environment. The purpose was to fully characterize strain gages for use at cryogenic temperatures in high magnetic fields. In this study, the magnetoresistance of a number of strain gages was measured in three orthogonal directions at mechanical strain levels to 8900 μm/m. As a result, a unique calibration curve was defined for magnetoresistance strain errors that is independent of strain level and field direction to 12 T at 4.2 K. A current strain-gage application is the measurement of superconductor mechanical properties. These gages will soon be used in the stress analysis of superconducting fusion magnets during cooldown from ambient temperatures and during operation at 4.2 K with magnetic fields to 12 T

Cost effective stream-gaging strategies for the Lower Colorado River basin; the Blythe field office operations

Science.gov (United States)

Moss, Marshall E.; Gilroy, Edward J.

1980-01-01

This report describes the theoretical developments and illustrates the applications of techniques that recently have been assembled to analyze the cost-effectiveness of federally funded stream-gaging activities in support of the Colorado River compact and subsequent adjudications. The cost effectiveness of 19 stream gages in terms of minimizing the sum of the variances of the errors of estimation of annual mean discharge is explored by means of a sequential-search optimization scheme. The search is conducted over a set of decision variables that describes the number of times that each gaging route is traveled in a year. A gage route is defined as the most expeditious circuit that is made from a field office to visit one or more stream gages and return to the office. The error variance is defined as a function of the frequency of visits to a gage by using optimal estimation theory. Currently a minimum of 12 visits per year is made to any gage. By changing to a six-visit minimum, the same total error variance can be attained for the 19 stations with a budget of 10% less than the current one. Other strategies are also explored. (USGS)

Neutron moisture gaging of agricultural soil

International Nuclear Information System (INIS)

Pospisil, S.; Janout, Z.; Kovacik, M.

1987-01-01

The design is described of a neutron moisture gage which consists of a measuring probe, neutron detector, small electronic recording device and a 241 Am-Be radionuclide source. The neutron detector consists of a surface barrier semiconductor silicon detector and a conversion layer of lithium fluoride. The detection of triton which is the reaction product of lithium with neutrons by the silicon detector is manifested as a voltage pulse. The detector has low sensitivity for fast neutrons and for gamma radiation and is suitable for determining moisture values in large volume samples. Verification and calibration measurements were carried out of chernozem, brown soil and podzolic soils in four series. The results are tabulated. Errors of measurement range between 0.8 to 1.0%. The precision of measurement could be improved by the calibration of the device for any type of soil. (E.S.). 4 tabs., 6 refs., 5 figs

Expression, purification and characterization of the cancer-germline antigen GAGE12I: a candidate for cancer immunotherapy

DEFF Research Database (Denmark)

Gjerstorff, Morten F; Besir, Hüseyin; Larsen, Martin R

2010-01-01

GAGE cancer-germline antigens are frequently expressed in a broad range of different cancers, while their expression in normal tissues is limited to the germ cells of the immune privileged organs, testis and ovary. GAGE proteins are immunogenic in humans, which make them promising targets...... for immunotherapy and candidates for cancer vaccines. Recombinant proteins may be superior to peptides as immunogens, since they have the potential to prime both CD4(+) and CD8(+) T cells and are not dependent on patient HLA-type. We have developed a method for production of highly pure recombinant GAGE12I...... filtration and formaldehyde cross-linking indicated that GAGE12I forms tetramers. The purified recombinant GAGE12I represents a candidate molecule for vaccination of cancer patients and will form the basis for further structural analysis of GAGE proteins....

Design, analysis, and initial testing of a fiber-optic shear gage for three-dimensional, high-temperature flows

Science.gov (United States)

Orr, Matthew W.

This investigation concerns the design, analysis, and initial testing of a new, two-component wall shear gage for 3D, high-temperature flows. This gage is a direct-measuring, non-nulling design with a round head surrounded by a small gap. Two flexure wheels are used to allow small motions of the floating head. Fiber-optic displacement sensors measure how far the polished faces of counterweights on the wheels move in relation to a fixed housing as the primary measurement system. No viscous damping was required. The gage has both fiber-optic instrumentation and strain gages mounted on the flexures for validation of the newer fiber optics. The sensor is constructed of Haynes RTM 230RTM, a high-temperature nickel alloy. The gage housing is made of 316 stainless steel. All components of the gage in pure fiber-optic form can survive to a temperature of 1073 K. The bonding methods of the backup strain gages limit their maximum temperature to 473 K. The dynamic range of the gage is from 0--500 Pa (0--10g) and higher shears can be measured by changing the floating head size. Extensive use of finite element modeling was critical to the design and analysis of the gage. Static structural, modal, and thermal analyses were performed on the flexures using the ANSYS finite element package. Static finite element analysis predicted the response of the flexures to a given load, and static calibrations using a direct force method confirmed these results. Finite element modal analysis results were within 16.4% for the first mode and within 30% for the second mode when compared with the experimentally determined modes. Vibration characteristics of the gage were determined from experimental free vibration data after the gage was subjected to an impulse. Uncertainties in the finished geometry make this level of error acceptable. A transient thermal analysis examined the effects of a very high heat flux on the exposed head of the gage. The 100,000 W/m2 heat flux used in this analysis is

Fast recovery strain measurements in a nuclear test environment

International Nuclear Information System (INIS)

Kitchen, W.R.; Nauman, W.J.; Vollmer, D.W.

1979-01-01

The recovery of early-time (50 μs or less) strain gage data on structural response experiments in underground nuclear tests has been a continuing problem for experimenters at the Nevada Test Site. Strain measurement is one of the primary techniques used to obtain experimental data for model verification and correlation with predicted effects. Peak strains generally occur within 50 to 100 μs of the radiation exposure. Associated with the exposure is an intense electromagnetic impulse that produces potentials of kilovolts and currents of kiloamperes on the experimental structures. For successful operation, the transducer and associated recording system must recover from the initial noise overload and accurately track the strain response within about 50 μs of the nuclear detonation. A gaging and fielding technique and a recording system design that together accomplish these objectives are described. Areas discussed include: (1) noise source model; (2) experimental cassette design, gage application, grounding, and shielding; (3) cable design and shielding between gage and recorder; (4) recorder design including signal conditioner/amplifier, digital encoder, buffer memory, and uphole data transmission; and (5) samples of experimental data

Cost-effectiveness of the stream-gaging program in Maine; a prototype for nationwide implementation

Science.gov (United States)

Fontaine, Richard A.; Moss, M.E.; Smath, J.A.; Thomas, W.O.

1984-01-01

This report documents the results of a cost-effectiveness study of the stream-gaging program in Maine. Data uses and funding sources were identified for the 51 continuous stream gages currently being operated in Maine with a budget of $211,000. Three stream gages were identified as producing data no longer sufficiently needed to warrant continuing their operation. Operation of these stations should be discontinued. Data collected at three other stations were identified as having uses specific only to short-term studies; it is recommended that these stations be discontinued at the end of the data-collection phases of the studies. The remaining 45 stations should be maintained in the program for the foreseeable future. The current policy for operation of the 45-station program would require a budget of $180,300 per year. The average standard error of estimation of streamflow records is 17.7 percent. It was shown that this overall level of accuracy at the 45 sites could be maintained with a budget of approximately $170,000 if resources were redistributed among the gages. A minimum budget of $155,000 is required to operate the 45-gage program; a smaller budget would not permit proper service and maintenance of the gages and recorders. At the minimum budget, the average standard error is 25.1 percent. The maximum budget analyzed was $350,000, which resulted in an average standard error of 8.7 percent. Large parts of Maine's interior were identified as having sparse streamflow data. It was determined that this sparsity be remedied as funds become available.

Wind Tunnel Strain-Gage Balance Calibration Data Analysis Using a Weighted Least Squares Approach

Science.gov (United States)

Ulbrich, N.; Volden, T.

2017-01-01

A new approach is presented that uses a weighted least squares fit to analyze wind tunnel strain-gage balance calibration data. The weighted least squares fit is specifically designed to increase the influence of single-component loadings during the regression analysis. The weighted least squares fit also reduces the impact of calibration load schedule asymmetries on the predicted primary sensitivities of the balance gages. A weighting factor between zero and one is assigned to each calibration data point that depends on a simple count of its intentionally loaded load components or gages. The greater the number of a data point's intentionally loaded load components or gages is, the smaller its weighting factor becomes. The proposed approach is applicable to both the Iterative and Non-Iterative Methods that are used for the analysis of strain-gage balance calibration data in the aerospace testing community. The Iterative Method uses a reasonable estimate of the tare corrected load set as input for the determination of the weighting factors. The Non-Iterative Method, on the other hand, uses gage output differences relative to the natural zeros as input for the determination of the weighting factors. Machine calibration data of a six-component force balance is used to illustrate benefits of the proposed weighted least squares fit. In addition, a detailed derivation of the PRESS residuals associated with a weighted least squares fit is given in the appendices of the paper as this information could not be found in the literature. These PRESS residuals may be needed to evaluate the predictive capabilities of the final regression models that result from a weighted least squares fit of the balance calibration data.

Improving versus maintaining nuclear safety

International Nuclear Information System (INIS)

2002-01-01

The concept of improving nuclear safety versus maintaining it has been discussed at a number of nuclear regulators meetings in recent years. National reports have indicated that there are philosophical differences between NEA member countries about whether their regulatory approaches require licensees to continuously improve nuclear safety or to continuously maintain it. It has been concluded that, while the actual level of safety achieved in all member countries is probably much the same, this is difficult to prove in a quantitative way. In practice, all regulatory approaches require improvements to be made to correct deficiencies and when otherwise warranted. Based on contributions from members of the NEA Committee on Nuclear Regulatory Activities (CNRA), this publication provides an overview of current nuclear regulatory philosophies and approaches, as well as insights into a selection of public perception issues. This publication's intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested. (author)

Iterative Strain-Gage Balance Calibration Data Analysis for Extended Independent Variable Sets

Science.gov (United States)

Ulbrich, Norbert Manfred

2011-01-01

A new method was developed that makes it possible to use an extended set of independent calibration variables for an iterative analysis of wind tunnel strain gage balance calibration data. The new method permits the application of the iterative analysis method whenever the total number of balance loads and other independent calibration variables is greater than the total number of measured strain gage outputs. Iteration equations used by the iterative analysis method have the limitation that the number of independent and dependent variables must match. The new method circumvents this limitation. It simply adds a missing dependent variable to the original data set by using an additional independent variable also as an additional dependent variable. Then, the desired solution of the regression analysis problem can be obtained that fits each gage output as a function of both the original and additional independent calibration variables. The final regression coefficients can be converted to data reduction matrix coefficients because the missing dependent variables were added to the data set without changing the regression analysis result for each gage output. Therefore, the new method still supports the application of the two load iteration equation choices that the iterative method traditionally uses for the prediction of balance loads during a wind tunnel test. An example is discussed in the paper that illustrates the application of the new method to a realistic simulation of temperature dependent calibration data set of a six component balance.

Slovak Electric, plc, Bohunice Nuclear Power Plant

International Nuclear Information System (INIS)

1999-01-01

A brief account of activities carried out by the Bohunice Nuclear Power Plant in 1998 is presented. These activities are reported under the headings: (1) Operation and electric power generation; (2) Nuclear and radiation safety; (3) Maintenance and scheduled refuelling out-gages; (4) Investment and WWER units upgrading; (5) Power Plants Personnel; (6) Public relations

Nuclear safety. Improvement programme

International Nuclear Information System (INIS)

2000-01-01

In this brochure the improvement programme of nuclear safety of the Mochovce NPP is presented in detail. In 1996, a 'Mochovce NPP Nuclear Safety Improvement Programme' was developed in the frame of unit 1 and 2 completion project. The programme has been compiled as a continuous one, with the aim to reach the highest possible safety level at the time of commissioning and to establish good preconditions for permanent safety improvement in future. Such an approach is in compliance with the world's trends of safety improvement, life-time extension, modernisation and nuclear station power increase. The basic document for development of the 'Programme' is the one titled 'Safety Issues and their Ranking for WWER 440/213 NPP' developed by a group of IAEA experts. The following organisations were selected for solution of the safety measures: EUCOM (Consortium of FRAMATOME, France, and SIEMENS, Germany); SKODA Prague, a.s.; ENERGOPROJEKT Prague, a.s. (EGP); Russian organisations associated in ATOMENERGOEXPORT; VUJE Trnava, a.s

49 CFR 213.110 - Gage restraint measurement systems.

Science.gov (United States)

2010-10-01

... requirements specified in §§ 213.109 and 213.127. (5) If the PTLF becomes non-functional or is missing, the... and fastener requirements specified in §§ 213.109 and 213.127 provided that— (1) The track owner... the minimum design requirements of a GRMS vehicle which specify that— (1) Gage restraint shall be...

Nickel--chromium strain gages for cryogenic stress analysis of superconducting structures in high magnetic fields

International Nuclear Information System (INIS)

Anon.

1977-01-01

Magnetoresistance measurements of strain gages were made. The magnitude and variation of the magnetoresistance of a large number of strain gages were measured for the following conditions: (1) dc magnetic fields up to 12 T, (2) three orthogonal field directions, (3) increasing and decreasing fields, (4) a wide range of strain levels, and (5) liquid helium temperature

HydroCloud: A Web Application for Exploring Stream Gage Data

Directory of Open Access Journals (Sweden)

Martin C. Roberge

2017-08-01

Full Text Available HydroCloud (hydrocloud.org is a mobile-friendly web application for visually browsing hydrology data from multiple sources. Data providers such as the US Geological Survey (USGS and the German 'Wasserstraßen- und Schifffahrtsverwaltung des Bundes' (WSV currently serve stream discharge data from more than 10,000 stream gages around the world. HydroCloud allows users to plot these data while out in the field, while also providing contextual information such as the current NEXRAD weather imagery or descriptive information about the stream gage and its watershed. Additional features include a chat mechanism for contacting developers, and the use of local storage for saving data.   Funding Statement: This project was supported in part by a grant from the Towson University School of Emerging Technology.

An introduction to NH-A neutron earth base moisture gage

International Nuclear Information System (INIS)

Zhu Huaian; Jiang Yulan; Yin Xilin; Yu Peiying; Luo Pinjie

1988-01-01

NH-A neutron earth base moisture gage is an accurate instrument which can measure earth moisture rapidly and non-destructively and display moisture results immediately. The deviation is estimated at ±0.012g/cm

Data acquisition from vacuum gage controlled by RS-232 standard using LabVIEW

International Nuclear Information System (INIS)

Brandea, Iulian; Culcer, Mihai; Steflea, Dumitru

1999-01-01

This paper deals with the problem of connecting a microcontroller-based vacuum gage to a personal computer, using the RS-232 hardware standard and the software LabVIEW and his collection of virtual instruments from National Instruments. To solve the problem an instrument driver was created. This provided the customer with a perfect solution for the remote control and data acquisition from an Intel 80CXX microcontroller-based vacuum gage. The remote control making use of an IBM-PC was design and manufactured in our institute. In order to make it intelligent the device was provided with a microprocessor or a microcontroller. To fulfill the requirements a vacuum gage with an 80C31 microcontroller and two Bayard-Alpert ion gauges, for very low pressures (10 -3 to 10 -7 mbar) and low pressure (10 mbar to 10 -3 mbar) was built. Because this microcontroller has a built-in circuitry for a serial communication, we established a serial communication between the PC (Pentium -166 MHz) and the vacuum gage, according to the RS-232 hardware standard. Optimum selection of software development tools however, was not as straightforward. Most producers use the C/C ++ - language programming tool for developing instrument drivers for their intelligent devices. One of the advantages of C/C ++ is its speed, but the compilation and the high-level skill required for optimum programming do not fit well with some requirements, particularly those of versatility, upgradability and user friendliness. After careful evaluation of several options, a final decision was to develop a hybrid software package using two different software development tools: LabVIEW, and assembly language. We chose LabVIEW because it is dedicated to data acquisition and communications, containing libraries for data collection, analysis, presentation and storage. The assembly language for Intel 8051's microcontrollers family is used to write the firmware for the vacuum gage and arithmetic routines. (authors)

Quantum dots as mineral- and matrix-specific strain gages for bone biomechanical studies

Science.gov (United States)

Zhu, Peizhi; Xu, Jiadi; Morris, Michael; Ramamoorthy, Ayyalusamy; Sahar, Nadder; Kohn, David

2009-02-01

We report the use of quantum dots (Qdots) as strain gages in the study of bone biomechanics using solid state nuclear magnetic resonance (NMR) spectroscopy. We have developed solid state NMR sample cells for investigation of deformations of bone tissue components at loads up to several Mega Pascal. The size constraints of the NMR instrumentation limit the bone specimen diameter and length to be no greater than 2-3 mm and 30 mm respectively. Further, magic angle spinning (MAS) solid state NMR experiments require the use of non-metallic apparatus that can be rotated at kilohertz rates. These experimental constraints preclude the use of standard biomechanical measurement systems. In this paper we explore the use of quantum dot center of gravity measurement as a strain gage technology consistent with the constraints of solid state NMR. We use Qdots that bind calcium (625 nm emission) and collagen (705 nm emission) for measurement of strain in these components. Compressive loads are applied to a specimen in a cell through a fine pitch screw turned with a mini-torque wrench. Displacement is measured as changes in the positions of arrays of quantum dots on the surface of a specimen. Arrays are created by spotting the specimen with dilute suspensions of Qdots. Mineral labeling is achieved with 705 nm carboxylated dots and matrix labeling with 565 nm quantum dots conjugated to collagen I antibodies. After each load increment the new positions of the quantum dots are measured by fluorescence microscopy. Changes in Qdot center of gravity as a function of applied load can be measured with submicron accuracy.

Development and application of the variable focus laser leveling gage

International Nuclear Information System (INIS)

Gong Kun; Ma Jinglong

2005-01-01

The variable focus laser leveling gage was developed. The performance and structure were introduced. The several alignments and tests in KrF laser angle multi-path optical system were accomplished with them. Its application in other optical equipment was discussed too. (author)

Improving nuclear regulatory effectiveness

International Nuclear Information System (INIS)

2001-01-01

Ensuring that nuclear installations are operated and maintained in such a way that their impact on public health and safety is as low as reasonably practicable has been and will continue to be the cornerstone of nuclear regulation. In the past, nuclear incidents provided the main impetus for regulatory change. Today, economic factors, deregulation, technological advancements, government oversight and the general requirements for openness and accountability are leading regulatory bodies to review their effectiveness. In addition, seeking to enhance the present level of nuclear safety by continuously improving the effectiveness of regulatory bodies is seen as one of the ways to strengthen public confidence in the regulatory systems. This report covers the basic concepts underlying nuclear regulatory effectiveness, advances being made and future requirements. The intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested. (author)

New approach for calibration and interpretation of IRAD GAGE vibrating-wire stressmeters

International Nuclear Information System (INIS)

Mao, N.

1986-05-01

IRAD GAGE vibrating-wire stressmeters were installed in the Spent Fuel Facility at the Nevada Test Site to measure the change in in-situ stress during the Spent Fuel Test-Climax (SFT-C). This paper discusses the results of removing a cylindrical section of rock and gages as a unit through overcoring, and the subsequent post-test calibration of the stressmeters in the laboratory. The estimated in-situ stresses based on post test calibration data are quite consistent with those directly measured in nearby holes. The magnitude of stress change calculated from pre-test calibration data is generally much smaller than that estimated from post test calibration data. 11 refs., 5 figs., 2 tabs

Thermal expansion measurement of turbine and main steam piping by using strain gages in power plants

International Nuclear Information System (INIS)

Na, Sang Soo; Chung, Jae Won; Bong, Suk Kun; Jun, Dong Ki; Kim, Yun Suk

2000-01-01

One of the domestic co-generation plants have undergone excessive vibration problems of turbine attributed to external force for years. The root cause of turbine vibration may be shaft alignment problem which sometimes is changed by thermal expansion and external force, even if turbine technicians perfectly performed it. To evaluate the alignment condition from plant start-up to full load, a strain measurement of turbine and main steam piping subjected to thermal loading is monitored by using strain gages. The strain gages are bonded on both bearing housing adjusting bolts and pipe stoppers which installed in the x-direction of left-side main steam piping near the turbine inlet in order to monitor closely the effect of turbine under thermal deformation of turbine casing and main steam piping during plant full load. Also in situ load of constant support hangers in main steam piping system is measured by strain gages and its results are used to rebalance the hanger rod load. Consequently, the experimental stress analysis by using strain gages turns out to be very useful tool to diagnose the trouble and failures of not only to stationary components but to rotating machinery in power plants

Analysis of GAGE, NY-ESO-1 and SP17 cancer/testis antigen expression in early stage non-small cell lung carcinoma

International Nuclear Information System (INIS)

Gjerstorff, Morten F; Pøhl, Mette; Olsen, Karen E; Ditzel, Henrik J

2013-01-01

The unique expression pattern and immunogenic properties of cancer/testis antigens make them ideal targets for immunotherapy of cancer. The MAGE-A3 cancer/testis antigen is frequently expressed in non-small cell lung cancer (NSCLC) and vaccination with MAGE-A3 in patients with MAGE-A3-positive NSCLC has shown promising results. However, little is known about the expression of other cancer/testis antigens in NSCLC. In the present study the expression of cancer/testis antigens GAGE, NY-ESO-1 and SP17 was investigated in patients with completely resected, early stage, primary NSCLC. Tumor biopsies from normal lung tissue and from a large cohort (n = 169) of NSCLC patients were examined for GAGE, NY-ESO-1 and SP17 protein expression by immunohistochemical analysis. The expression of these antigens was further matched to clinical and pathological features using univariate cox regression analysis. GAGE and NY-ESO-1 cancer/testis antigens were not expressed in normal lung tissue, while SP17 was expressed in ciliated lung epithelia. The frequency of GAGE, NY-ESO-1 and SP17 expression in NSCLC tumors were 26.0% (44/169), 11.8% (20/169) and 4.7% (8/169), respectively, and 33.1% (56/169) of the tumors expressed at least one of these antigens. In general, the expression of GAGE, NY-ESO-1 and SP17 was not significantly associated with a specific histotype (adenocarcinoma vs. squamous cell carcinoma), but high-level GAGE expression (>50%) was more frequent in squamous cell carcinoma (p = 0.02). Furthermore, the frequency of GAGE expression was demonstrated to be significantly higher in stage II-IIIa than stage I NSCLC (17.0% vs. 35.8%; p = 0.02). Analysis of the relation between tumor expression of GAGE and NY-ESO-1 and survival endpoints revealed no significant associations. Our study demonstrates that GAGE, NY-ESO-1 and SP17 cancer/testis antigens are candidate targets for immunotherapy of NSCLC and further suggest that multi-antigen vaccines may be beneficial

Utilizing Photogrammetry and Strain Gage Measurement to Characterize Pressurization of Inflatable Modules

Science.gov (United States)

Mohammed, Anil

2011-01-01

This paper focuses on integrating a large hatch penetration into inflatable modules of various constructions. This paper also compares load predictions with test measurements. The strain was measured by utilizing photogrammetric methods and strain gages mounted to select clevises that interface with the structural webbings. Bench testing showed good correlation between strain data collected from an extensometer and photogrammetric measurements, even when the material transitioned from the low load to high load strain region of the curve. The full-scale torus design module showed mixed results as well in the lower load and high strain regions. After thorough analysis of photogrammetric measurements, strain gage measurements, and predicted load, the photogrammetric measurements seem to be off by a factor of two.

Portable neutron moisture gage for the moisture determination of structure parts

International Nuclear Information System (INIS)

Harnisch, M.

1985-01-01

For determining the moisture of structure parts during building or before repairing a portable neutron moisture gage consisting of a neutron probe and pulse analyzer has been developed. The measuring process, calibration, and prerequisites of application are briefly discussed

Evaluation test of high temperature strain gages used in a stethoscope for OGL-1 components in an elevated temperature service

Energy Technology Data Exchange (ETDEWEB)

Sato, Toshimi (Kyowa Electronic Inst. Co. Ltd. (Japan)); Tanaka, Isao; Komori, Yoshihiro; Suzuki; Toshiaki

1982-08-01

The stethoscope for OGL-1 components in a elevated temperature service (SOCETS) is a measuring system of evaluation integrity of structures for high temperature pipings during operations of Japan Material Testing Reactor. This paper is described about the results on fundamental performance on high temperature strain gages. From their test results that have been based on correlation of temperature-timestrain factors, it became clear that two weldable strain gages and a capacitance strain gage were available for strain measurements of OGL-1 components.

Methodology to measure strains at high temperatures using electrical strain gages with free filaments

International Nuclear Information System (INIS)

Atanazio Filho, Nelson N.; Gomes, Paulo T. Vida; Scaldaferri, Denis H.B.; Silva, Luiz L. da; Rabello, Emerson G.; Mansur, Tanius R.

2013-01-01

An experimental methodology used for strains measuring at high temperatures is show in this work. In order to do the measurements, it was used electric strain gages with loose filaments attached to a stainless steel 304 beam with specific cements. The beam has triangular shape and a constant thickness, so the strain is the same along its length. Unless the beam surface be carefully prepared, the strain gage attachment is not efficient. The showed results are for temperatures ranging from 20 deg C to 300 deg C, but the experimental methodology could be used to measure strains at a temperature up to 900 deg C. Analytical calculations based on solid mechanics were used to verify the strain gage electrical installation and the measured strains. At a first moment, beam deformations as a temperature function were plotted. After that, beam deformations with different weighs were plotted as a temperature function. The results shown allowed concluding that the experimental methodology is trustable to measure strains at temperatures up to 300 deg C. (author)

Low Cost Stream Gaging through Analysis of Stage Height Using Digital Photography

Science.gov (United States)

Mui, C. K.; Royem, A. A.; Walter, M. T.

2010-12-01

Through the middle of the twentieth century, the US was relatively rich in active streamflow gages. Over the past four decades, the number of gages has decreased by approximately 10% (approx. 20 gages a year) and it is likely this trend will continue for the foreseeable future. Not only are streaflow data valuable for water resources planning and management, but they are invaluable for assessing how land use and climate changes are impacting the environment. Affordable, easy-to-use systems need to be developed to enable a wider community to establish and maintain streamflow observation sites. Currently USGS-like gauges cost 30,000 to 50,000 to build and $6,000/year to maintain. We are developing a system that uses digital images in conjunction with MATLAB for image post processing that has the potential to both accurately and cost effectively monitor stream gauge. We explored several different staff gauge designs in conjunction with associated image processing code. The most robust design so far consists of a brightly colored metal staff gauge and and code that allows a point-and-click method for training the image processing code to correctly identify the staff. We ultimately envision a system in which users can upload their images via the Internet and post-processing is done on a remote server, which also collates data and metadata for open-access downloading.

Evaluation test of high temperature strain gages used in a stethoscope for OGL-1 components in an elevated temperature service

International Nuclear Information System (INIS)

Sato, Toshimi; Tanaka, Isao; Komori, Yoshihiro; Suzuki; Toshiaki.

1982-01-01

The stethoscope for OGL-1 components in a elevated temperature service (SOCETS) is a measuring system of evaluation integrity of structures for high temperature pipings during operations of Japan Material Testing Reactor. This paper is described about the results on fundamental performance on high temperature strain gages. From their test results that have been based on correlation of temperature-timestrain factors, it became clear that two weldable strain gages and a capacitance strain gage were available for strain measurements of OGL-1 components. (author)

Design of Gages for Direct Skin Friction Measurements in Complex Turbulent Flows with Shock Impingement Compensation

Science.gov (United States)

2007-06-07

100 kW/m2 for 0.1 s. Along with the material change, an oil leak problem required a geometric change. Initially, we considered TIG welding or...shear and moment, is addressed through the design, development, and testing of the CF1 and CF2 gages. Chapter 3 presents the evolutionary process ...a shock. Chapter 4 examines the performance of each gage to the nominal load conditions. Through this process , objective 2 is met. The best

Strain-gage signal-conditioning system for use in the LCP

International Nuclear Information System (INIS)

Ellis, J.F.; Walstrom, P.L.

1979-01-01

A strain-gage signal-conditioning system, providing wide-band noise rejection and isolation from high voltages that occur during emergency coil discharges, has been developed and tested. The multichannel system combines double-shielded transformers, neutralizing networks, and bandpass filters (with commercial 3-kHz carrier amplifier modules to isolate the strain gages to 5000 V) eliminate thermoelectric effects, and provide a signal bandwidth of 200 Hz. Common-mode interference occurs primarily as a result of beat-note effects between the carrier and the superimposed noise at frequencies near the odd harmonics of the carrier. The common-mode rejection of the test circuit was measured to be 120 dB for noise at 2750 and 3250 Hz, 135 dB at 3 kHz, and 135 dB and better at the odd harmonics of 9 kHz and above. The system has been successfully used in strain measurements on the toroidal field coils of the ISX-B tokamak and will be used in the Large Coil Test Facility to monitor strains in the energized coil conductors

A Dual-Range Strain Gage Weighing Transducer Employing Automatic Switching

Science.gov (United States)

Rodger A. Arola

1968-01-01

Describes a dual-range strain gage transducer which has proven to be an excellent weight-sensing device for weighing trees and tree-length logs; discusses basic principals of the design and operation; and shows that a single transducer having two sensitivity ranges with automatic internal switching can sense weight with good repeatability and that one calibration curve...

The effects of incomplete annealing on the temperature dependence of sheet resistance and gage factor in aluminum and phosphorus implanted silicon on sapphire

Science.gov (United States)

Pisciotta, B. P.; Gross, C.

1976-01-01

Partial annealing of damage to the crystal lattice during ion implantation reduces the temperature coefficient of resistivity of ion-implanted silicon, while facilitating controlled doping. Reliance on this method for temperature compensation of the resistivity and strain-gage factor is discussed. Implantation conditions and annealing conditions are detailed. The gage factor and its temperature variation are not drastically affected by crystal damage for some crystal orientations. A model is proposed to account for the effects of electron damage on the temperature dependence of resistivity and on silicon piezoresistance. The results are applicable to the design of silicon-on-sapphire strain gages with high gage factors.

Improved nuclear boiler

International Nuclear Information System (INIS)

Pierart, Robert.

1980-01-01

The improved nuclear boiler concerned in this invention is of the kind comprising, inter alia, a nuclear reactor supported by a metallic structure and of which the vessel is at least enclosed in part by a casing acting as a protective containment integrated in this structure. It is essentially characterized in that this casing is fitted into and maintained in position in the metallic structure by removable locking devices which enable the casing to be withdrawn from the remainder of the structure. Hence, after the casing has been withdrawn or removed from the metallic structure, access to the reactor vessel is readily obtained for inspection and/or testing from without [fr

Strain measurement on a compact nuclear reactor steam generator

International Nuclear Information System (INIS)

Scaldaferri, Denis Henrique Bianchi; Gomes, Paulo de Tarso Vida; Mansur, Tanius Rodrigues; Pozzo, Renato del; Mola, Jairo

2011-01-01

This work presents the strain measurement procedures applied to a compact nuclear reactor steam generator, during a hydrostatic test, using strain gage technology. The test was divided in two steps: primary side test and secondary side test. In the primary side test twelve points for strain measurement using rectangular rosettes, three points (two external and one internal) for temperature measurement using special strain gages and one point for pressure measurement using a pressure transducer were monitored. In the secondary side test 18 points for strain measurement using rectangular rosettes, four points (two external and two internal) for temperature measurement using special strain gages and one point for pressure measurement using a pressure transducer were monitored. The measurement points on both internal and external pressurizer walls were established from pre-calculated stress distribution by means of numerical approach (finite elements modeling). Strain values using a quarter Wheatstone bridge circuit were obtained. Stress values, from experimental strain were determined, and to numerical calculation results were compared. (author)

Nuclear Station Facilities Improvement Planning

International Nuclear Information System (INIS)

Hooks, R. W.; Lunardini, A. L.; Zaben, O.

1991-01-01

An effective facilities improvement program will include a plan for the temporary relocation of personnel during the construction of an adjoining service building addition. Since the smooth continuation of plant operation is of paramount importance, the phasing plan is established to minimize the disruptions in day-to-day station operation and administration. This plan should consider the final occupancy arrangements and the transition to the new structure; for example, computer hookup and phase-in should be considered. The nuclear industry is placing more emphasis on safety and reliability of nuclear power plants. In order to do this, more emphasis is placed on operations and maintenance. This results in increased size of managerial, technical and maintenance staffs. This in turn requires improved office and service facilities. The facilities that require improvement may include training areas, rad waste processing and storage facilities, and maintenance facilities. This paper discusses an approach for developing an effective program to plan and implement these projects. These improvement projects can range in magnitude from modifying a simple system to building a new structure to allocating space for a future project. This paper addresses the planning required for the new structures with emphasis on site location, space allocation, and internal layout. Since facility planning has recently been completed by Sargent and Leyden at six U. S. nuclear stations, specific examples from some of those plants are presented. Site planning and the establishment of long-range goals are of the utmost importance when undertaking a facilities improvement program for a nuclear station. A plan that considers the total site usage will enhance the value of both the new and existing facilities. Proper planning at the beginning of the program can minimize costs and maximize the benefits of the program

United States Geological Survey discharge data from five example gages on intermittent streams

Data.gov (United States)

U.S. Environmental Protection Agency — The data are mean daily discharge data at United States Geological Survey gages. Once column provides the date (mm/dd/yyyy) and the other column provides the mean...

Evaluation of metal-foil strain gages for cryogenic application in magnetic fields

International Nuclear Information System (INIS)

Freynik, H.S. Jr.; Roach, D.R.; Deis, D.W.; Hirzel, D.G.

1977-01-01

The requirement for the design and construction of large superconducting magnet systems for fusion research has raised a number of new questions regarding the properties of composite superconducting conductors. One of these, the effect of mechanical stress on the current-carrying capacity of Nb 3 Sn, is of major importance in determining the feasibility of constructing large magnets with this material. A typical experiment for determining such data involves the measurement of critical current versus magnetic field while the conductor is being mechanically strained to various degrees. Techniques are well developed for the current and field measurements, but much less so for the accurate measurement of strain at liquid-helium temperature in a high magnetic field. A study was made of commercial, metal-foil strain gages for use under these conditions. The information developed can also be applied to the use of strain gages as diagnostic tools in superconducting magnets

Continuous improvement methods in the nuclear industry

International Nuclear Information System (INIS)

Heising, Carolyn D.

1995-01-01

The purpose of this paper is to investigate management methods for improved safety in the nuclear power industry. Process improvement management, methods of business process reengineering, total quality management, and continued process improvement (KAIZEN) are explored. The anticipated advantages of extensive use of improved process oriented management methods in the nuclear industry are increased effectiveness and efficiency in virtually all tasks of plant operation and maintenance. Important spin off include increased plant safety and economy. (author). 6 refs., 1 fig

Accuracy Improvement of Neutron Nuclear Data on Minor Actinides

Science.gov (United States)

Harada, Hideo; Iwamoto, Osamu; Iwamoto, Nobuyuki; Kimura, Atsushi; Terada, Kazushi; Nakao, Taro; Nakamura, Shoji; Mizuyama, Kazuhito; Igashira, Masayuki; Katabuchi, Tatsuya; Sano, Tadafumi; Takahashi, Yoshiyuki; Takamiya, Koichi; Pyeon, Cheol Ho; Fukutani, Satoshi; Fujii, Toshiyuki; Hori, Jun-ichi; Yagi, Takahiro; Yashima, Hiroshi

2015-05-01

Improvement of accuracy of neutron nuclear data for minor actinides (MAs) and long-lived fission products (LLFPs) is required for developing innovative nuclear system transmuting these nuclei. In order to meet the requirement, the project entitled as "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)" has been started as one of the "Innovative Nuclear Research and Development Program" in Japan at October 2013. The AIMAC project team is composed of researchers in four different fields: differential nuclear data measurement, integral nuclear data measurement, nuclear chemistry, and nuclear data evaluation. By integrating all of the forefront knowledge and techniques in these fields, the team aims at improving the accuracy of the data. The background and research plan of the AIMAC project are presented.

Thermal efficiency improvements - an imperative for nuclear generating stations

International Nuclear Information System (INIS)

Hassanien, S.; Rouse, S.

1997-01-01

A one and a half percent thermal performance improvement of Ontario Hydro's operating nuclear units (Bruce B, Pickering B, and Darlington) means almost 980 GWh are available to the transmission system (assuming an 80% capacity factor). This is equivalent to the energy consumption of 34,000 electrically-heated homes in Ontario, and worth more than $39 million in revenue to Ontario Hydro Nuclear Generation. Improving nuclear plant thermal efficiency improves profitability (more GWh per unit of fuel) and competitiveness (cost of unit energy), and reduces environmental impact (less spent fuel and nuclear waste). Thermal performance will naturally decrease due to the age of the units unless corrective action is taken. Most Ontario Hydro nuclear units are ten to twenty years old. Some common causes for loss of thermal efficiency are: fouling and tube plugging of steam generators, condensers, and heat exchangers; steam leaks in the condenser due to valve wear, steam trap and drain leaks; deposition, pitting, cracking, corrosion, etc., of turbine blades; inadequate feedwater metering resulting from corrosion and deposition. This paper stresses the importance of improving the nuclear units' thermal efficiency. Ontario Hydro Nuclear has demonstrated energy savings results are achievable and affordable. Between 1994 and 1996, Nuclear reduced its energy use and improved thermal efficiency by over 430,000 MWh. Efficiency improvement is not automatic - strategies are needed to be effective. This paper suggests practical strategies to systematically improve thermal efficiency. (author)

The basic discussion on nuclear power safety improvement based on nuclear equipment design

International Nuclear Information System (INIS)

Zhao Feiyun; Yao Yangui; Yu Hao; He Yinbiao; Gao Lei; Yao Weida

2013-01-01

The safety of strengthening nuclear power design was described based on nuclear equipment design after Fukushima nuclear accident. From these aspects, such as advanced standard system, advanced design method, suitable test means, consideration of beyond design basis event, and nuclear safety culture construction, the importance of nuclear safety improvement was emphatically presented. The enlightenment was given to nuclear power designer. (authors)

An overview of the GAGE cancer/testis antigen family with the inclusion of newly identified members

DEFF Research Database (Denmark)

Gjerstorff, M F; Ditzel, H J

2008-01-01

. This review describes the structure and phylogeny of the GAGE family members and presents a revised nomenclature, which will enable a more clear distinction of genes and gene products. The GAGE gene locus at chromosome X p11.23 consists of at least 16 genes, each of which is located in one of an equal number...... of highly conserved tandem repeats, and more genes remain to be identified. These genes are likely the creation of unequal replication under positive selection after the divergence of primates from other mammals. The encoded products are predicted to be highly similar small acidic proteins involved in germ...

Stress Measurement around a Circular Role in a Cantilever Beam under Bending Moment Using Strain Gage and Reflective Photoelasticity

Energy Technology Data Exchange (ETDEWEB)

Baek, Tae Hyun; Park, Tae Geun; Yang, Min Bok [Kunsan National University, Gunsan (Korea, Republic of)

2006-10-15

It is necessary to study on the stress concentration experimentally, which is the main reason to avoid mechanical dilapidation and failure, when designing a mechanical structure. Stress concentration factor of a specimen of cantilever beam with a circular hole in the center was measured using both strain gage and photoelastic methods in this paper. In strain-gage measurement, three strain gages along the line near a hole of the specimen were installed and maximum strain was extrapolated from three measurements. In photoelastic measurement, two methods were employed. First, the Babinet-Soleil compensation method was used to measure the maximum strain. Secondly, photoelastic 4-step phase shilling method was applied to observe the strain distribution around the hole. Measurements obtained by different experiments were comparable within the range of experimental error

Stress Measurement around a Circular Role in a Cantilever Beam under Bending Moment Using Strain Gage and Reflective Photoelasticity

International Nuclear Information System (INIS)

Baek, Tae Hyun; Park, Tae Geun; Yang, Min Bok

2006-01-01

It is necessary to study on the stress concentration experimentally, which is the main reason to avoid mechanical dilapidation and failure, when designing a mechanical structure. Stress concentration factor of a specimen of cantilever beam with a circular hole in the center was measured using both strain gage and photoelastic methods in this paper. In strain-gage measurement, three strain gages along the line near a hole of the specimen were installed and maximum strain was extrapolated from three measurements. In photoelastic measurement, two methods were employed. First, the Babinet-Soleil compensation method was used to measure the maximum strain. Secondly, photoelastic 4-step phase shilling method was applied to observe the strain distribution around the hole. Measurements obtained by different experiments were comparable within the range of experimental error

Current status and improvement of the nuclear physics experiment course for speciality of nuclear physics and nuclear technology

International Nuclear Information System (INIS)

Qu Guopu; Guo Lanying

1999-01-01

The author reviews the current status of the nuclear physics experiment course for speciality of nuclear physics and nuclear technology in higher education and expresses author's views on the future improvement of the nuclear physics experiment course

Problems in use and security of measurement of high temperature strain gages at various temperature limits up to 10000C

International Nuclear Information System (INIS)

Ziegler, K.

1982-01-01

The examples given show the quality and use of manufacturers' data for a series of behaviour criteria for strain gages in the high temperature region. These results should not only be regarded critically. The manufacturer must appreciate that the very costly programme of investigations on the users' side represents a product development for large parts for the manufacturer of the strain gauges. It would therefore be desirable if these considerations were to initiate investigations on the manufacturer's part, in order to clear up the problematic are of the use of strain gages in the high temperature field, in order to provide the customer with more reliable and better strain gage characteristics for very expensive high temperature strain measurements. (orig.) [de

Construct ability Improvement for Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Dae Soo; Lee, Jong Rim; Kim, Jong Ku [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

1997-12-31

The purpose of this study was to identify methods for improving the construct ability of nuclear power plants. This study reviewed several references of current construction practices of domestic and overseas nuclear plants in order to identify potential methods for improving construct ability. The identified methods for improving construct ability were then evaluated based on the applicability to domestic nuclear plant construction. The selected methods are expected to reduce the construction period, improve the quality of construction, cost, safety, and productivity. Selection of which methods should be implemented will require further evaluation of construction modifications, design changes, contract revisions. Among construction methods studied, platform construction methods can be applied through construction sequence modification without significant design changes, and Over the Top construction method of the NSSS, automatic welding of RCL pipes, CLP modularization, etc., are considered to be applied after design modification and adjustment of material lead time. (author). 49 refs., figs., tabs.

Improving animal productivity by nuclear techniques

International Nuclear Information System (INIS)

Garcia, M.; Jayasuriya, M.C.N.; Perera, B.M.A.O.

1995-01-01

The IAEA and FAO have run a joint programme for 30 years to assist national agricultural research systems in member states to develop, test and apply nuclear and related techniques for improving the productivity of livestock. Applications of nuclear technologies for improving livestock productivity include: use of radioimmunoassay in animal nutrition researches, animal production, and evaluating feeding and management systems through reproductive performance in a field. Geographic coverage and the type of livestock studies are: grazing animals (cattle, goats and sheep) in Africa, Latin America and Asia, as well as buffalo production in Asia. 6 refs, 8 figs, 6 tabs

Application of nuclear techniques in Poland; Perspektywy wykorzystania atomistyki w Polsce

Energy Technology Data Exchange (ETDEWEB)

Chmielewski, A.G.; Owczarczyk, A.; Urbanski, P. [Instytut Chemii i Techniki Jadrowej, Warsaw (Poland); Romanowski, M. [Biuro Studiow i Projektow Techniki Jadrowej `Proatom`, Warsaw (Poland); Stegowski, Z. [Akademia Gorniczo-Hutnicza, Cracow (Poland); Nowak, K. [Osrodek Badawczo-Rozwojowy Izotopow, Swierk-Otwock (Poland); Pachan, A. [Instytut Problemow Jadrowych, Swierk-Otwock (Poland); Tanczyk, R. [Centralne Laboratorium Ochrony Radiologicznej, Warsaw (Poland); Jablonski, R. [Zaklad Techniki Izotopowej `Polon-Izot`, Warsaw (Poland)

1997-12-31

The commercial applications of nuclear techniques in Poland have been presented. The special attention have been paid at: radiation technologies, application of radiometric gages in different branches of industry, tracer techniques, production and application of radiation sources in medicine, industry and material testing. 10 refs, 6 figs, 6 tabs.

Arrangement for correcting values measured by mass per unit area or thickness gages

International Nuclear Information System (INIS)

Volger, G.; Sandke, E.; Heinz, P.

1985-01-01

The described arrangement can be applied to gaged making use of beta radiation and of a protective screen for shielding the radiation source and the ionization chamber of the measuring instrument. It has been aimed at counterbalancing measuring inaccuracies caused by temperature fluctuations in the measuring slot

Managing Human Performance to Improve Nuclear Facility Operation

International Nuclear Information System (INIS)

2013-01-01

One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property'. The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. IAEA Nuclear Energy Series No. NG-G-2.1, Managing Human Resources in the Field of Nuclear Energy, was published in 2009. In that publication, four interrelated objectives of the management of human resources were identified and discussed: ensuring that nuclear industry personnel have the necessary competence for their jobs; effectively organizing work activities; anticipating human resource needs; and monitoring and continually improving performance. This publication addresses the fourth objective and, in particular, summarizes good practices in the area of managing human performance

Improved moulding material for addition to nuclear fuel particles to produce nuclear fuel elements

International Nuclear Information System (INIS)

Miertschin, G.N.; Leary, D.F.

1976-01-01

A suggestion is made to improve the moulding materials used to produce carbon-contained nuclear fuel particles by a coke-reducing added substance. The nuclear fuel particles are meant for the formation of fuel elements for gas-cooled high-temperature nuclear reactors. The moulding materials are above all for the formation of coated particles which are burnt in situ in nuclear fuel element chambers out of 'green' nuclear fuel bodies. The added substance improves the shape stability of the particles forming and prevents a stiding or bridge formation between the particles or with the surrounding walls. The following are named as added substances: 1) Polystyrene and styrene-butadiene-Co polymers (mol. wt. between 5oo and 1,000,000), 2) aromatic compounds (mol. wt. 75 to 300), 3) saturated hydrocarbon polymers (mol. wt. 5,000 to 1,000,000). Additional release agents further improve the properties in the same direction (e.g. alcohols, fatty acids, amines). (orig.) [de

Improved design on Qinshan 300 MWe nuclear power plant

International Nuclear Information System (INIS)

Shi Peihua; Cheng Wanli; Lu Rongliang

1993-01-01

The main aim, guiding ideology, general performance and parameters of improved design on Qinshan 300 MWe nuclear power plant are presented. Improved items are also introduced including the characteristic of layout in nuclear island building, decreasing unnecessary devices increasing necessary safety facilities and unifying code and standard. The progress of improved design is presented

Improved design on Qinshan 300 MWe nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Peihua, Shi; Wanli, Cheng; Rongliang, Lu [Shanghai Nuclear Engineering Research and Design Inst. (China)

1993-06-01

The main aim, guiding ideology, general performance and parameters of improved design on Qinshan 300 MWe nuclear power plant are presented. Improved items are also introduced including the characteristic of layout in nuclear island building, decreasing unnecessary devices increasing necessary safety facilities and unifying code and standard. The progress of improved design is presented.

Improving nutrition through nuclear science

International Nuclear Information System (INIS)

2003-06-01

Good nutrition is essential to health and quality of life. As a United Nations agency dedicated to helping Member States achieve their social and economic goals, the International Atomic Energy Agency (IAEA) recognizes the importance of good nutrition and is working to address the problems underlying poor nutrition. In fact, many Agency activities serve basic human needs, by applying nuclear science to increase food production, improve health care, improve management of water resources, and assess sources of environmental pollution. Global progress in reducing malnutrition throughout the human life cycle has been slow and patchy. In its 2000 Report on the World Nutrition Situation, the United Nations Sub Committee on Nutrition estimated that in developing countries 182 million children under five years of age are chronically undernourished and 150 million are underweight. An estimated 30 million infants are born each year with impaired growth due to poor nutrition during pregnancy. Worldwide, renewed international commitments have been made to address this situation, and the IAEA is a vital partner in these efforts. Nuclear science provides valuable tools for monitoring factors that influence nutrition, such as micronutrients, body composition, and breast milk uptake. Through its sub-programme on nutrition, the Agency is helping countries to use isotope applications and other nuclear techniques to their nutritional problems and is supporting leading-edge research on the interaction between nutrition and environmental pollution and infection with the ultimate goal of improving human nutrition

The Effect of Modeling Qualities, Tones and Gages in Ceramic Supply Chains' Master Planning

Directory of Open Access Journals (Sweden)

Isabel MUNDI

2012-01-01

Full Text Available Ceramic production processes are characterized by providing quantities of the same finished goods that differ in qualities, tones and gages. This aspect becomes a problem for ceramic supply chains (SCs that should promise and serve customer orders with homogeneous quantities of the same finished good. In this paper a mathematical programming model for the cen-tralized master planning of ceramic SC is proposed. Inputs to the master plan include demand forecasts in terms of customer order classes based on their order size and splitting percentages of a lot into homogeneous sub-lots. Then, the master plan defines the size and loading of lots to production lines and their distribution with the aim of maximizing the number of customer orders fulfilled with homogeneous quantities in the most efficient manner for the SC. Finally, the effect of modeling qualities, tones and gages in master planning is assessed.

Optimization of protection and calibration of the moisture-density gages troxler

International Nuclear Information System (INIS)

RAKOTONDRAVANONA, J.E.

2011-01-01

The purpose of this work is the implementation of the principle of optimization of the protection and calibration of moisture-density gages TROXLER. The main objectives are the application of radiation protection and the feasibility of a calibration laboratory design. The calibration of density and moisture may confirm the calibration of moisture-density gages TROXLER. The calibration of density consists of the assembly of measurements on three calibration blocks (magnesium, aluminium and magnesium/aluminium) built in the TRACKER. The value of density uncertainty is ±32 Kg.m -3 . The calibration of moisture is carried out on two calibration blocks (magnesium and magnesium/polyethylene)The value of moisture uncertainty is ±16 Kg.m -3 . The design of the laboratory returns to the dose limitation. The laboratory is designed mainly wall out of ordinary concrete, a good attenuator of the gamma radiations and neutron. For the design, the value of term source gamma is 25.77±0.20μSv.h -1 and the value of term source neutron is 7.88±0.35μSv.h -1 are used for the thickness of the walls. The importance of the design makes it possible to attenuate to the maximum doses and rates dose until the total absorption of the radiations. [fr

Nuclear and radiation techniques - state of art and development trends

International Nuclear Information System (INIS)

Chmielewski, A.G.

1995-01-01

The state of art and development trends of nuclear and radiation techniques in Poland and worldwide have been presented. Among them the radiometric gages, radiation technologies, radiotracer methods and measuring systems for pipeline and vessels, brightness control have been described and their applications in industry, agriculture, health and environment protection have been shown and discussed. 35 refs, 1 fig

Discharge measurements at gaging stations

Science.gov (United States)

Turnipseed, D. Phil; Sauer, Vernon B.

2010-01-01

The techniques and standards for making discharge measurements at streamflow gaging stations are described in this publication. The vertical axis rotating-element current meter, principally the Price current meter, has been traditionally used for most measurements of discharge; however, advancements in acoustic technology have led to important developments in the use of acoustic Doppler current profilers, acoustic Doppler velocimeters, and other emerging technologies for the measurement of discharge. These new instruments, based on acoustic Doppler theory, have the advantage of no moving parts, and in the case of the acoustic Doppler current profiler, quickly and easily provide three-dimensional stream-velocity profile data through much of the vertical water column. For much of the discussion of acoustic Doppler current profiler moving-boat methodology, the reader is referred to U.S. Geological Survey Techniques and Methods 3-A22 (Mueller and Wagner, 2009). Personal digital assistants (PDAs), electronic field notebooks, and other personal computers provide fast and efficient data-collection methods that are more error-free than traditional hand methods. The use of portable weirs and flumes, floats, volumetric tanks, indirect methods, and tracers in measuring discharge are briefly described.

Application of AFINCH as a tool for evaluating the effects of streamflow-gaging-network size and composition on the accuracy and precision of streamflow estimates at ungaged locations in the southeast Lake Michigan hydrologic subregion

Science.gov (United States)

Koltun, G.F.; Holtschlag, David J.

2010-01-01

size and composition of the streamflow-gaging network affected the average apparent errors and variability of the estimated flows and (b) whether results for certain months were more variable than for others. The six flow lines were categorized into one of three types depending upon their network topology and position relative to operating streamflow-gaging stations.    Statistical analysis of the model results indicates that (1) less precise (that is, more variable) estimates resulted from smaller streamflow-gaging networks as compared to larger streamflow-gaging networks, (2) precision of AFINCH flow estimates at an ungaged flow line is improved by operation of one or more streamflow gages upstream and (or) downstream in the enclosing basin, (3) no consistent seasonal trend in estimate variability was evident, and (4) flow lines from ungaged basins appeared to exhibit the smallest absolute apparent percent errors (APEs) and smallest changes in average APE as a function of increasing censoring level. The counterintuitive results described in item (4) above likely reflect both the nature of the base-streamflow estimate from which the errors were computed and insensitivity in the average model-derived estimates to changes in the streamflow-gaging-network size and composition. Another analysis demonstrated that errors for flow lines in ungaged basins have the potential to be much larger than indicated by their APEs if measured relative to their true (but unknown) flows.     “Missing gage” analyses, based on examination of censoring subset results where the streamflow gage of interest was omitted from the calibration data set, were done to better understand the true error characteristics for ungaged flow lines as a function of network size. Results examined for 2 water years indicated that the probability of computing a monthly streamflow estimate within 10 percent of the true value with AFINCH decreased from greater than 0.9 at about a 10-percent network

Ball mounting fixture for a roundness gage

Science.gov (United States)

Gauler, Allen L.; Pasieka, Donald F.

1983-01-01

A ball mounting fixture for a roundness gage is disclosed. The fixture includes a pair of chuck assemblies oriented substantially transversely with respect to one another and mounted on a common base. Each chuck assembly preferably includes a rotary stage and a wobble plate affixed thereto. A ball chuck affixed to each wobble plate is operable to selectively support a ball to be measured for roundness, with the wobble plate permitting the ball chuck to be tilted to center the ball on the axis of rotation of the rotary stage. In a preferred embodiment, each chuck assembly includes a vacuum chuck operable to selectively support the ball to be measured for roundness. The mounting fixture enables a series of roundness measurements to be taken with a conventional rotating gagehead roundness instrument, which measurements can be utilized to determine the sphericity of the ball.

Experience Transformed into Nuclear Regulatory Improvements in Russia

International Nuclear Information System (INIS)

Sapozhnikov, A.

2016-01-01

The third International Conference on Effective Nuclear Regulatory Systems (Canada, 2013) identified the main action items that should be addressed, implemented and followed up. The key technical and organizational areas important to strengthening reactor and spent fuel safety have been determined as following: • Regulatory lessons learned and actions taken (since the accident at the Fukushima Daiichi NPP); • Waste management and spent fuel safety; • Emergency management; • Emerging programmes; • Human and organizational factors, safety and security culture. Over time many activities based on results of the IAEA Integrated Regulatory Review Service in the Russian Federation, 2019, and post-mission, 2013, have been implemented. At present there is progress for the national action plan on nuclear safety, preparation and conducting of long term spent fuel management, complementary reviews for nuclear facilities other than Nuclear Power Plants, emergency exercises with the regulatory body participation, improving communication, development of national regulations and improvement of regulatory system in the whole. The regulatory body ensures assistance in development of national regulatory infrastructure, safety culture to the countries planning to construct Russian design facilities (NPPs, RRs). The report outlines the results and future actions to improve nuclear regulation based on systematic approach to safety and particularly reflects the specificity of taking measures for the research reactors. (author)

A improved tidal method without water level

Science.gov (United States)

Luo, xiaowen

2017-04-01

Now most tide are obtained use water Level and pressure type water gage, but it is difficult to install them and reading is in low accuracy in this method . In view of above-mentioned facts, In order to improve tide accuracy, A improved method is introduced.sea level is obtained in given time using high-precision GNSS buoy combined instantaneous position from pressure gage. two steps are as following, (1) the GNSS time service is used as the source of synchronization reference in tidal measurement; (2) centimeter-level sea surface positions are obtained in real time using difference GNSS The improved method used in seafloor topography survey，in 145 cross points, 95% meet the requirements of the Hydrographic survey specification. It is effective method to obtain higher accuracy tide.

Precipitation data for water years 1992 and 1993 from a network of nonrecording gages at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Ambos, D.S.; Flint, A.L.; Hevesi, J.A.

1995-01-01

This report presents precipitation data collected in a storage gage network at Yucca Mountain, Nevada, from October 1, 1991, to September 30, 1993. The measured values indicate total accumulated precipitation for specified time intervals approximately corresponding to separate storm events. Installation of a precipitation monitoring network was initiated in January 1990, and was continually expanded and upgraded throughout the period ending in September 1993. The final network included 3 different gage types for a total of 133 gages at 108 locations within the three drainages overlying the potential repository site. Measured precipitation indicated above average accumulations for water years 1992 and 1993 relative to the most recent estimate of 6.7 inches for long-term average annual precipitation over the area of the network. The total precipitation averaged over the network in 1992 was about 8.2 inches with a maximum of about 11.2 inches measured at borehole USW GA-1. The total precipitation averaged over the network in 1993 was about 10.3 inches with a maximum of about 12.1 inches at neutron-access borehole UE-25 UZN number-sign 4

Evaluating a slope-stability model for shallow rain-induced landslides using gage and satellite data

Science.gov (United States)

Yatheendradas, S.; Kirschbaum, D.; Baum, Rex L.; Godt, Jonathan W.

2014-01-01

Improving prediction of landslide early warning systems requires accurate estimation of the conditions that trigger slope failures. This study tested a slope-stability model for shallow rainfall-induced landslides by utilizing rainfall information from gauge and satellite records. We used the TRIGRS model (Transient Rainfall Infiltration and Grid-based Regional Slope-stability analysis) for simulating the evolution of the factor of safety due to rainfall infiltration. Using a spatial subset of a well-characterized digital landscape from an earlier study, we considered shallow failure on a slope adjoining an urban transportation roadway near the Seattle area in Washington, USA.We ran the TRIGRS model using high-quality rain gage and satellite-based rainfall data from the Tropical Rainfall Measuring Mission (TRMM). Preliminary results with parameterized soil depth values suggest that the steeper slope values in this spatial domain have factor of safety values that are extremely close to the failure limit within an extremely narrow range of values, providing multiple false alarms. When the soil depths were constrained using a back analysis procedure to ensure that slopes were stable under initial condtions, the model accurately predicted the timing and location of the landslide observation without false alarms over time for gage rain data. The TRMM satellite rainfall data did not show adequately retreived rainfall peak magnitudes and accumulation over the study period, and as a result failed to predict the landslide event. These preliminary results indicate that more accurate and higher-resolution rain data (e.g., the upcoming Global Precipitation Measurement (GPM) mission) are required to provide accurate and reliable landslide predictions in ungaged basins.

Streamflow characteristics based on data through water year 2009 for selected streamflow-gaging stations in or near Montana: Chapter E in Montana StreamStats

Science.gov (United States)

McCarthy, Peter M.

2016-04-05

Chapter E of this Scientific Investigations Report documents results from a study by the U.S. Geological Survey, in cooperation with the Montana Department of Environmental Quality and the Montana Department of Natural Resources and Conservation, to provide an update of statewide streamflow characteristics based on data through water year 2009 for streamflow-gaging stations in or near Montana. Streamflow characteristics are presented for 408 streamflow-gaging stations in Montana and adjacent areas having 10 or more years of record. Data include the magnitude and probability of annual low and high streamflow, the magnitude and probability of low streamflow for three seasons (March–June, July–October, and November–February), streamflow duration statistics for monthly and annual periods, and mean streamflows for monthly and annual periods. Streamflow is considered to be regulated at streamflow-gaging stations where dams or other large-scale human modifications affect 20 percent or more of the contributing drainage basin. Separate streamflow characteristics are presented for the unregulated and regulated periods of record for streamflow-gaging stations with sufficient data.

Improvements in the nuclear accident response system in Brazil

International Nuclear Information System (INIS)

Estrada, J.J.S.; Azevedo, E.M.; Knofel, T.M.J.; Recio, J.C.A.; Alves, R.N.

1998-01-01

The National Commission on Nuclear Energy has been making outstanding effort to improve its nuclear and radiological accident response systems since the tragic accident in Goiania. Most of this effort is related to nuclear area although the radiological accident has been also considered. This paper describes the improvements in the CNEN response system structure, discusses several topics involving those related to emergency planning and preparedness, and points out some deficiencies that need to be corrected also. The situation during the Goiania accident was more disadvantageous than nowadays, so it is believed that none of the actual deficiencies are sufficient to guess that the population and the environment will not be protected in case of a nuclear or radiological accident

Doses of personnel employed in the manufacture of radioisotope thickness gages

International Nuclear Information System (INIS)

Kostenetskij, M.I.

1981-01-01

Doses of the personnel of one of the plants manifacturing radioisotope thickness gages of different types are determined. Annual doses to the body protected by shielding screens are low and according to the data of individual dosimetry constitute 5x10 -3 -6x10 -3 J/kg (0.5-0.6 rem). A table of radiation doses to hands obtained during all kind of operations, is given. Measures for the further reduction of radiation doses of the personnel are suggested [ru

Cost benefit justification of nuclear plant reliability improvement

International Nuclear Information System (INIS)

El-Sayed, M.A.H.; Abdelmonem, N.M.

1985-01-01

The design of the secondary steam loop of the nuclear power plant has a significant effect on the reliability of the plant. Moreover, the necessity to cool a reactor safely has increased the reliability demanded from the system. The rapidly rising construction costs and fuel prices in recent years have stimulated a great deal in optimizing the productivity of a nuclear power plant through reliability improvement of the secondary steamloop and the reactor cooling system. A method for evaluating the reliability of steam loop and cooling system of a nuclear power plant is presented. The method utilizes the cut-set technique. The developed method can be easily used to show to what extent the overall reliability of the nuclear plant is affected by the possible failures in the steam and cooling subsystem. A model for calculating the increase in the nuclear plant productivity resulting from a proposed improvement in the two subsystems reliability is discussed. The model takes into account the capital cost of spare parts for several components, replacement energy, operating and maintenance costs

IAEA-EU Joint Action Partnership in Improving Nuclear Security

International Nuclear Information System (INIS)

2011-12-01

Nuclear and other radioactive material is on the move and in demand. Used in peaceful applications such as energy, medicine, research and industry, it improves the daily lives of individuals worldwide. Nonetheless, the risk posed by it falling into the wrong hands is a real and growing concern of the international community and one that demands improved nuclear security. Steps to bolster nuclear security and mitigate this risk include accounting for and securing nuclear and radioactive material as well as their related facilities, and helping to prevent theft, sabotage and use with malicious intent. Strong legislative, regulatory and enforcement frameworks, enhanced national capacity, and increased international cooperation in protecting against, and preparing for, any scenario strengthens these measures further. As a result, the Board of Governors of the International Atomic Energy Agency (IAEA) approved a plan of activities in 2002 to improve nuclear security worldwide. In 2003, the Council of the European Union (EU) adopted its Strategy against Proliferation of Weapons of Mass Destruction. Since then, five Contribution Agreements between the European Commission (EC) and the IAEA have been undertaken to provide financial support to IAEA activities in the areas of nuclear security and verification. These 'Joint Actions' assist States in strengthening their nuclear security infrastructure and underscore both the EU and IAEA's commitment to effective cooperation. IAEA-EU JOINT ACTION. The IAEA works to improve and strengthen national nuclear security programmes worldwide. EU support helps to advance the IAEA's efforts by raising awareness and improving understanding of nuclear security and its many component parts. Priority is given to those States that need to determine what radioactive and nuclear material they have, how to control it and how to reduce the risk it poses. Efforts focus on three main areas, strengthening: (i) States' legislative and regulatory

Human performance improvement in organizations: Potential application for the nuclear industry

International Nuclear Information System (INIS)

2005-11-01

This publication is primarily intended for managers and specialists in nuclear facility operating organizations working in the area of human performance improvement. It is intended to provide them with practical information they can use to improve human performance in their organizations. While some of the information provided in this publication is based upon the experience of nuclear facility operating organizations, most of it comes from human performance improvement initiatives in non-nuclear organizations and industries. The nuclear industry has a long tradition of sharing good management practices in order to foster continuous improvement. However, it is not always realized that many of the practices that are now well established initially came from non-nuclear industries and were subsequently adapted for application to nuclear power plant operating organizations. There is, therefore, good reason to periodically review non-nuclear industry practices for ideas that might have direct or indirect application to the nuclear industry in order to potentially gain benefits such as the following: new approaches to certain problem areas, insights into new or impending challenges, improvements in existing practices, benchmarking of opportunities, development of learning organizations and avoidance of collective blind spots. The preparation of this report was an activity of the project on Effective Training to Achieve Excellence in the Performance of NPP Personnel. The objective of this project is to enhance the capability of Member States to utilize proven practices developed and transferred by the IAEA for improving personnel performance. The expected outcome from this project is the increased use by organizations in Members States of proven engineering and management practices and methodologies developed and transferred by the IAEA to improve personnel performance

Regional Relations in Bankfull Channel Characteristics determined from flow measurements at selected stream-gaging stations in West Virginia, 1911-2002

Science.gov (United States)

Messinger, Terence; Wiley, Jeffrey B.

2004-01-01

Three bankfull channel characteristics?cross-sectional area, width, and depth?were significantly correlated with drainage area in regression equations developed for two regions in West Virginia. Channel characteristics were determined from analysis of flow measurements made at 74 U.S. Geological Survey stream-gaging stations at flows between 0.5 and 5.0 times bankfull flow between 1911 and 2002. Graphical and regression analysis were used to delineate an 'Eastern Region' and a 'Western Region,' which were separated by the boundary between the Appalachian Plateaus and Valley and Ridge Physiographic Provinces. Streams that drained parts of both provinces had channel characteristics typical of the Eastern Region, and were grouped with it. Standard error for the six regression equations, three for each region, ranged between 8.7 and 16 percent. Cross-sectional area and depth were greater relative to drainage area for the Western Region than they were for the Eastern Region. Regression equations were defined for streams draining between 46.5 and 1,619 square miles for the Eastern Region, and between 2.78 and 1,354 square miles for the Western Region. Stream-gaging stations with two or more cross sections where flow had been measured at flows between 0.5 and 5.0 times the 1.5-year flow showed poor replication of channel characteristics compared to the 95-percent confidence intervals of the regression, suggesting that within-reach variability for the stream-gaging stations may be substantial. A disproportionate number of the selected stream-gaging stations were on large (drainage area greater than 100 square miles) streams in the central highlands of West Virginia, and only one stream-gaging station that met data-quality criteria was available to represent the region within about 50 miles of the Ohio River north of Parkersburg, West Virginia. Many of the cross sections were at bridges, which can change channel shape. Although the data discussed in this report may not be

Research on the improvement of nuclear safety

International Nuclear Information System (INIS)

Yoo, Keon Joong; Kim, Dong Soo; Kim, Hui Dong; Park, Chang Kyu

1993-06-01

To improve the nuclear safety, this project is divided into three areas which are the development of safety analysis technology, the development of severe accident analysis technology and the development of integrated safety assessment technology. 1. The development of safety analysis technology. The present research aims at the development of necessary technologies for nuclear safety analysis in Korea. Establishment of the safety analysis technologies enables to reduce the expenditure both by eliminating excessive conservatisms incorporated in nuclear reactor design and by increasing safety margins in operation. It also contributes to improving plant safety through realistic analyses of the Emergency Operating Procedures (EOP). 2. The development of severe accident analysis technology. By the computer codes (MELCOR and CONTAIN), the in-vessel and the ex-vessel severe accident phenomena are simulated. 3. The development of integrated safety assessment technology. In the development of integrated safety assessment techniques, the included research areas are the improvement of PSA computer codes, the basic study on the methodology for human reliability analysis (HRA) and common cause failure (CCF). For the development of the level 2 PSA computer code, the basic research for the interface between level 1 and 2 PSA, the methodology for the treatment of containment event tree are performed. Also the new technologies such as artificial intelligence, object-oriented programming techniques are used for the improvement of computer code and the assessment techniques

Improved technical specifications and related improvements to safety in commercial Nuclear power plants

International Nuclear Information System (INIS)

Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C.

2004-01-01

Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

Improved technical specifications and related improvements to safety in commercial Nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

2004-07-01

Many of the commercial nuclear power plants in the United States (US) have been converting a portion of the plant operating license known as the Technical Specifications (TS) in accordance with a document published by the US Nuclear Regulatory Commission (NRC). The TS prescribe commercial nuclear power plant operating requirements. There are several types of nuclear power plants in the US, based on the technology of different vendors, and there is an NRC document that supports each of the five different vendor designs. The NRC documents are known as the Improved Standard Technical Specifications (ISTS) and are contained in a separate document (NUREG series) for each one of the designs. EXCEL Services Corporation (hereinafter EXCEL) has played a major role in the development of the ISTS and in the development, licensing, and implementation of the plant specific Improved Technical Specifications (ITS) (which is based on the ISTS) for the commercial nuclear power plants in the US that have elected to make this conversion. There are currently 103 operating commercial nuclear power plants in the US and 68 of them have successfully completed the conversion to the ITS and are now operating in accordance with their plant specific ITS. The ISTS is focused mainly on safety by ensuring the commercial nuclear reactors can safely shut down and mitigate the consequences of any postulated transient and accident. It accomplishes this function by including requirements directly associated with safety in a document structured systematically and taking into account some key human factors and technical initiatives. This paper discusses the ISTS including its format, content, and detail, the history of the ISTS, the ITS development, licensing, and implementation process, the safety improvements resulting from a plant conversion to ITS, and the importance of the ITS Project to the industry. (Author)

Improved dose estimates for nuclear criticality accidents

International Nuclear Information System (INIS)

Wilkinson, A.D.; Basoglu, B.; Bentley, C.L.; Dunn, M.E.; Plaster, M.J.; Dodds, H.L.; Yamamoto, T.

1995-01-01

Slide rules are improved for estimating doses and dose rates resulting from nuclear criticality accidents. The original slide rules were created for highly enriched uranium solutions and metals using hand calculations along with the decades old Way-Wigner radioactive decay relationship and the inverse square law. This work uses state-of-the-art methods and better data to improve the original slide rules and also to extend the slide rule concept to three additional systems; i.e., highly enriched (93.2 wt%) uranium damp (H/ 235 U = 10) powder (U 3 O 8 ) and low-enriched (5 wt%) uranium mixtures (UO 2 F 2 ) with a H/ 235 U ratio of 200 and 500. Although the improved slide rules differ only slightly from the original slide rules, the improved slide rules and also the new slide rules can be used with greater confidence since they are based on more rigorous methods and better nuclear data

Gage for gas flow measurement especially in gas-suction pipes

International Nuclear Information System (INIS)

Renner, K.; Stegmanns, W.

1978-01-01

The gage utilizes the differential pressure given by a differential pressure producer to generate, in a bypass, a partial gas flow measured by means of a direct-reading anemometer of windmill type. The partial gas flow is generated between pressure pick-up openings in the gas-suction pipe in front of a venturi insert and pressure pick-up openings at the bottleneck of the venturi insert. The reading of the anemometer is proportional to the main gas flow and independent of the variables of state and the properties of the gases to be measured. (RW) [de

Leadership Actions to Improve Nuclear Safety Culture

International Nuclear Information System (INIS)

Clewett, L.K.

2016-01-01

The challenge many leaders face is how to effectively implement and then utilise the results of Safety Culture surveys. Bruce Power has recently successfully implemented changes to the Safety Culture survey process including how corrective actions were identified and implemented. The actions taken in response to the latest survey have proven effective with step change performance noted. Nuclear Safety is a core value for Bruce Power. Nuclear Safety at Bruce Power is based on the following four pillars: reactor safety, industrial safety, radiological safety and environmental safety. Processes and practices are in place to achieve a healthy Nuclear Safety Culture within Bruce Power such that nuclear safety is the overriding priority. This governance is based on industry leading practices which monitor, asses and take action to drive continual improvements in the Nuclear Safety Culture within Bruce Power.

Improvement of communications in nuclear power plants

International Nuclear Information System (INIS)

Depigny, C.; Ghertman, F.; Lestien, A.

1986-01-01

Since 1983, Electricite de France (EDF) has been engaged in a major project to improve nuclear power plant communications. This project was launched following a series of incidents in which inappropriate communications practices and equipment were shown to be an aggravating, or in some cases, the determining factor. This paper presents the program established by EDF to resolve communications problems in its nuclear power stations

Near Net Manufacturing Using Thin Gage Friction Stir Welding

Science.gov (United States)

Takeshita, Jennifer; Potter, David; Holquin, Michael

2006-01-01

Friction Stir Welding (FSW) and near net spin forming of FSW aluminumn blanks were investigated for large-scale pressure vessel applications. With a specific focus on very thin gage 2xxx and 7xxx aluminum alloys, the program concentrated on the following: the criteria used for material selection, a potential manufacturing flow, and the effectiveness and associated risks of near net spin forming. Discussion will include the mechanical properties of the friction stir welds and the parent material from before and after the spin forming process. This effort was performed under a NASA Space Exploration initiative focused on increasing the affordability, reliability and performance of pressure vessels larger than 10 ft. diameter.

Good practices for improved nuclear power plant performance

International Nuclear Information System (INIS)

1989-04-01

This report provides an overview of operational principles, practice and improvements which have contributed to good performance of eight selected world nuclear power stations. The IAEA Power Reactor Information System (PRIS) was used to identify a population of good performers. It is recognized that there are many other good performing nuclear power stations not included in this report. Specific criteria described in the introduction were used in selecting these eight stations. The information contained in this report was obtained by the staff from IAEA, Division of Nuclear Power. This was accomplished by visits to the stations and visits to a number of utility support groups and three independent organizations which provide support to more than one utility. The information in this report is intended as an aid for operating organizations to identify possible improvement initiatives to enhance plant performance. Figs and tabs

Effectively Managing Nuclear Risk Through Human Performance Improvement

International Nuclear Information System (INIS)

Coe, Richard; Lake, Patricia

2003-01-01

The U.S. commercial nuclear industry has just completed an outstanding decade of plant performance. Safety levels and electric production are at unprecedented high levels and continue to exceed even high industry goals. Nuclear energy continues to keep the highest priority on performance improvement programs and highly trained and qualified people that maintain its record setting safety and reliability of operations. While the industry has maintained a high level of performance, the advent of deregulation and the consolidation of nuclear power plant ownership, as well as the current climate for concern about both rising energy costs and the availability of power, have raised the standard for nuclear energy's level of competitiveness in today's market place. The resulting challenge is how to more effectively manage risk and to improve performance even further in a generally high-performing industry. One of the most effective ways to develop this culture is to apply the principles of Hum an Performance Technology, or HPT. HPT is a relatively new field. Its principles are derived from the research and practice of behavioral and cognitive psychologists, instructional technologists, training designers, organizational developers, and various human resource specialists. Using the principles of HPT can help the nuclear industry successfully meet ever-changing environmental and business demands

New Improved Nuclear Data for Nuclear Criticality and Safety

International Nuclear Information System (INIS)

Guber, Klaus H.; Leal, Luiz C.; Lampoudis, C.; Kopecky, S.; Schillebeeckx, P.; Emiliani, F.; Wynants, R.; Siegler, P.

2011-01-01

The Geel Electron Linear Accelerator (GELINA) was used to measure neutron total and capture cross sections of 182,183,184,186 W and 63,65 Cu in the energy range from 100 eV to ∼200 keV using the time-of-flight method. GELINA is the only high-power white neutron source with excellent timing resolution and ideally suited for these experiments. Concerns about the use of existing cross-section data in nuclear criticality calculations using Monte Carlo codes and benchmarks were a prime motivator for the new cross-section measurements. To support the Nuclear Criticality Safety Program, neutron cross-section measurements were initiated using GELINA at the EC-JRC-IRMM. Concerns about data deficiencies in some existing cross-section evaluations from libraries such as ENDF/B, JEFF, or JENDL for nuclear criticality calculations were the prime motivator for new cross-section measurements. Over the past years many troubles with existing nuclear data have emerged, such as problems related to proper normalization, neutron sensitivity backgrounds, poorly characterized samples, and use of improper pulse-height weighting functions. These deficiencies may occur in the resolved- and unresolved-resonance region and may lead to erroneous nuclear criticality calculations. An example is the use of the evaluated neutron cross-section data for tungsten in nuclear criticality safety calculations, which exhibit discrepancies in benchmark calculations and show the need for reliable covariance data. We measured the neutron total and capture cross sections of 182,183,184,186 W and 63,65 Cu in the neutron energy range from 100 eV to several hundred keV. This will help to improve the representation of the cross sections since most of the available evaluated data rely only on old measurements. Usually these measurements were done with poor experimental resolution or only over a very limited energy range, which is insufficient for the current application.

Improving operator quality at Genkai Nuclear Power Plant

International Nuclear Information System (INIS)

Kuwano, Takeshi.

1989-01-01

Improvement in operator quality, or improvement in an operator's skill and professional knowledge, is of prime importance because of its great influence on safe and steady plant operation. This paper describes the education and training of reactor operators at the Genkai pressurized water reactor nuclear power plant with respect to the following topics: organization of Genkai power plant; education and training program management; training at the Nuclear Training Center; training and education on-site including emergency procedures training, normal operating procedures training, informational study of emergency conditions in existing plants, and all-around training of operators; qualifying tests for supervisors; and operator motivation

Improving the economics and competitiveness of nuclear power in China

International Nuclear Information System (INIS)

Jing Chunning; Tian Jiashu

2005-01-01

A cost structure of nuclear power plant is introduced in this paper. Various factors that influence the nuclear power economics are discussed in detail. A preliminary study is carried out for the short-term new nuclear power plants in China. Focusing on the Chinese nuclear power development strategy, the short term and mid-long term economics of nuclear power in China is analyzed. Based on analysis and comparison, suggestions and proposals for improving the economics and competitiveness of nuclear power in China are provided. (authors)

Alternative off-site power supply improves nuclear power plant safety

International Nuclear Information System (INIS)

Gjorgiev, Blaže; Volkanovski, Andrija; Kančev, Duško; Čepin, Marko

2014-01-01

Highlights: • Additional power supply for mitigation of the station blackout event in NPP is used. • A hydro power plant is considered as an off-site alternative power supply. • An upgrade of the probabilistic safety assessment from its traditional use is made. • The obtained results show improvement of nuclear power plant safety. - Abstract: A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source

Additional improvements needed in physical security at nuclear powerplants

International Nuclear Information System (INIS)

1983-01-01

Since the middle 1970's, the Nuclear Regulatory Commission and powerplant operators have taken measures to reduce the vulnerability of powerplants to attempted acts of sabotage. GAO's evaluation disclosed that further improvements can be made by screening nuclear plant employees to reduce the number of potential saboteurs and strengthening the physical security systems to ensure their compatibility with other plant safety systems. The Commission has taken two initiatives addressing these improvements. Therefore, GAO is not making recommendations at this time

The importance of capital cost reduction in improving nuclear economics

International Nuclear Information System (INIS)

Langmo, A.; Braun, C.

1996-01-01

In the developed countries having existing nuclear programs, the situation necessitates lower total power generation cost. The restructuring of utility industry due to the deregulation causes to reorganize the ownership of some nuclear plants, and the overall economics of nuclear plants in relation to their local competition is reexamined. The reluctance to make any new long term capital cost commitment arises, and it makes new plant construction less likely in near future, and plant upgrading and improvement to be put to intense scrutiny. The capital cost recovery in existing nuclear plants in USA is discussed. It is important to recognize that there is very little that can be done to affect already expended capital, and only that can be done is to improve plant capacity factors, besides write-off. The roles of architects and engineers in improved plant economics are now evaluated by the various organizations which are interested in the participation in new nuclear industry reorganization and restructuring. The reduction of operation and maintenance costs and capital investment, and the improvement of capacity factor are reported. In new ALWR construction program, architects and engineers can significantly support the control of plant capital costs by the selection of the plant design and the sites, and the strategies of procurement and contract, construction schedule and others. (K.I.)

MAGE-A1, GAGE and NY-ESO-1 cancer/testis antigen expression during human gonadal development

DEFF Research Database (Denmark)

Gjerstorff, Morten F; Kock, Kirsten; Nielsen, Ole

2007-01-01

BACKGROUND: Cancer/testis antigens (CTAs) are expressed in several cancers and during normal adult male germ cell differentiation. Little is known about their role in fetal development of human germ cells. METHODS: We examined expression of the CTAs MAGE-A1, GAGE and NY-ESO-1 in fetal gonads...

USSR orders computers to improve nuclear safety

International Nuclear Information System (INIS)

Anon.

1990-01-01

Control Data Corp (CDC) has received an order valued at $32-million from the Soviet Union for six Cyber 962 mainframe computer systems to be used to increase the safety of civilian nuclear powerplants. The firm is now waiting for approval of the contract by the US government and Western Allies. The computers, ordered by the Soviet Research and Development Institute of Power Engineering (RDIPE), will analyze safety factors in the operation of nuclear reactors over a wide range of conditions. The Soviet Union's civilian nuclear program is one of the largest in the world, with over 50 plants in operation. Types of safety analyses the computers perform include: neutron-physics calculations, radiation-protection studies, stress analysis, reliability analysis of equipment and systems, ecological-impact calculations, transient analysis, and support activities for emergency response. They also include a simulator with realistic mathematical models of Soviet nuclear powerplants to improve operator training

Geoscience Workforce Development at UNAVCO: Leveraging the NSF GAGE Facility

Science.gov (United States)

Morris, A. R.; Charlevoix, D. J.; Miller, M.

2013-12-01

Global economic development demands that the United States remain competitive in the STEM fields, and developing a forward-looking and well-trained geoscience workforce is imperative. According to the Bureau of Labor Statistics, the geosciences will experience a growth of 19% by 2016. Fifty percent of the current geoscience workforce is within 10-15 years of retirement, and as a result, the U.S. is facing a gap between the supply of prepared geoscientists and the demand for well-trained labor. Barring aggressive intervention, the imbalance in the geoscience workforce will continue to grow, leaving the increased demand unmet. UNAVCO, Inc. is well situated to prepare undergraduate students for placement in geoscience technical positions and advanced graduate study. UNAVCO is a university-governed consortium facilitating research and education in the geosciences and in addition UNAVCO manages the NSF Geodesy Advancing Geosciences and EarthScope (GAGE) facility. The GAGE facility supports many facets of geoscience research including instrumentation and infrastructure, data analysis, cyberinfrastructure, and broader impacts. UNAVCO supports the Research Experiences in the Solid Earth Sciences for Students (RESESS), an NSF-funded multiyear geoscience research internship, community support, and professional development program. The primary goal of the RESESS program is to increase the number of historically underrepresented students entering graduate school in the geosciences. RESESS has met with high success in the first 9 years of the program, as more than 75% of RESESS alumni are currently in Master's and PhD programs across the U.S. Building upon the successes of RESESS, UNAVCO is launching a comprehensive workforce development program that will network underrepresented groups in the geosciences to research and opportunities throughout the geosciences. This presentation will focus on the successes of the RESESS program and plans to expand on this success with broader

Measuring and improving the public perceptions on nuclear energy

International Nuclear Information System (INIS)

Choi, Young Sung

2001-01-01

The purpose of this paper is to measure the public's perception on risk and benefit of nuclear power and to find ways to improve the perceptions. Latent Class Analysis is adopted for the perception measures, which quantify people's perception and reveal the perception structure. The measures resulted from Latent Class Analysis show that women perceive risks to be more existent and benefits to be less than men do. Moreover there is a tendency that if education level is high, perceived risk is low and perceived benefit is high. The perception of risk and benefit also depends on different channels through which people get information about nuclear energy. Comparing seven different information channels, the most effective ways of communicating with people to improve the risk and benefit perception of nuclear energy are found to be the visit to nuclear plants and the education through the regular schooling. Information dissemination through mass media is only effective to the benefit perception

Improving practical training ability at Nuclear Research Institute oriented to nuclear human resource development within First Phase

International Nuclear Information System (INIS)

Nguyen Xuan Hai; Nguyen Nhi Dien; Pham Dinh Khang; Pham Ngoc Tuan; Tuong Thi Thu Huong

2016-01-01

This report presents results of a research project “Improving practical training ability at Nuclear Research Institute oriented to nuclear human resource development within first phase”. In the frameworks of the project, a guiding document on 27 Ortec’s experiments was translated into Vietnamese. Several equipment are used in the experiments such as neutron howitzer, gamma counter, multi-channel analyzer and alpha-gamma coincidence spectroscopy were designed and fabricated. These products contributed to improving the ability of research and training of Training and Education Center, Nuclear Research Institute (NRI). (author)

A photoelastic study of the effects of an impulsive seismic wave on a nuclear containment vessel

International Nuclear Information System (INIS)

Burger, C.P.

1981-01-01

A dynamic photoelastic study of the progressive movement of a dilatational P-wave into a model of a nuclear containment vessel,is studied. The reflections at the dome abutments are observed and the strong flexural wave that deforms the dome itself is studied with photoelasticity and with dynamic strain gage procedures. (E.G.) [pt

Technical and metrological service improvement of measurement channels with flow-type transducers of ionic impurities for water chemical control in nuclear reactors

International Nuclear Information System (INIS)

Vilkov, Nicolay Ya.; Voronina, N.V.; Matveyev, V.N.; Sorokin, N.M.; Sidorchuk, A.N.

2012-09-01

Improvement of sampling process, including sample taking, transport, and preparation, and optimization of on-line metrological maintenance on measuring chains containing flow-type sensors is very important for obtaining high quality information about NPP coolant water composition. Sample preparation and measurement errors almost cannot be eliminated by data processing in top level computers. For on-line measurements of the coolant water ion composition, nuclear plants commonly use sampling lines with gage pressure regulators provided at inlets of flow type sensors. The major part of sample fluid is drained via bypass outside the flow path through the sensors. A better alternative is to form flows at the inlets of flow type sensors using outlet pressure feedback devices. This sampling scheme ensures fully representative samples that are transported to the sensor inlets with a given time delay. In such a scheme, the sample fluid returns into the coolant system without change in composition. The paper presents test results for the prototype model of the pressure and flow control device. Alexandrov NITI has patented a method and apparatus for comprehensively calibrating measuring chains with flow type ion analyzers which are used in nuclear power plants to measure on line the ion composition of high-purity and other water streams. The patented dynamical method generates calibration solutions as binary electrolytes with a given analyte concentration. The method is easy to implement and requires no dosing equipment. Calibration solutions are generated directly in the water flow through the sampling line connected to the coolant line or high-purity water feed line. Unlike the concentration of buffer solutions used in pH measurements, the total ion concentration in generated electrolyte solutions is close to that in actual water streams at nuclear plants. With the proposed method and equipment, a reference pH value can be obtained with accuracy which is close to the

Discussion on establishment and improvement of the nuclear safety culture system

International Nuclear Information System (INIS)

Lu Weiqiang; Na Fuli

2010-01-01

By discussion of the problems in the manufacture process of nuclear power equipment enterprisers, puts forwards the tentative idea of establishment the nuclear safety culture system, meanwhile, gives some suggestions in order to improving the nuclear safety culture system. (authors)

Improving communication between nuclear communities

International Nuclear Information System (INIS)

Pethes, George

1995-01-01

of an agreement between Paks Nuclear Power Station and several mayors of neighbouring villages. The mayors formed an Association for Social Control and Information, called in Hungarian TEIT. Steady flow of information on the plant reaches these villages. A round-the-clock background radiation monitoring station was also set up for the public in the near downwind town of Kalocsa, showing the situation every 10 minutes. Another anti-nuclear approach is to build up a 'Pavlovian type of conditioned reflex' in the population to make them afraid of nuclear energy. For example, Hungary is far from the sea, has no real nuclear problems, but you will find in Hungarian papers news on a sunken Soviet submarine. While not overlooking and underestimating the danger of such sunken submarine(s) it is worth mentioning that, such reports in our press in 1994 were three times greater than in 1992. It is important to recognize that in the former Soviet-influenced areas there are no basically professional nuclear communicators as compared to the Western countries. Therefore, I suggest, that a communication system be created by the nuclear community, probably named WANIS, World Association of Nuclear Information Specialists. A two-way International electronic mail system - built up similar to those run by the anti-nuclear forces - should help nuclear communicators of Central and Eastern Europe to exchange arguments and tactics against everyday arguments raised by anti-nuclear militants. In other words, a common armoury of arguments, I call 'Inter lingua Nucleare', should be created within the nuclear community to improve the countering of misleading, hostile statements and actions. In Hungary, the Hungarian Nuclear Society has launched a corrective programme. If very severely distorted opinions on nuclear electricity production or on nuclear techniques or on radiation appear in the media, the concerned Learned Societies (e.g. Energy, Nuclear Medicine, Food Science, Radiation Protection

Improving nuclear regulation. NEA regulatory guidance booklets volumes 1-14

International Nuclear Information System (INIS)

2011-01-01

; Regulatory Effectiveness: 10. Improving Nuclear Regulatory Effectiveness, 11. Direct Indicators of Nuclear Regulatory Efficiency and Effectiveness, 12. Improving Versus Maintaining Nuclear Safety, Regulatory Assessment: 13. Nuclear Regulatory Decision Making; 14. The Regulatory Goal of Assuring Nuclear Safety. (authors)

EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

Energy Technology Data Exchange (ETDEWEB)

Erven, Ulrich (ed.) [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard (ed.) [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De (ed.) [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

2005-07-01

The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

Energy Technology Data Exchange (ETDEWEB)

Erven, Ulrich [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

2005-07-01

The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

Nuclear Fuel Cycle Options Catalog: FY16 Improvements and Additions

Energy Technology Data Exchange (ETDEWEB)

Price, Laura L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Barela, Amanda Crystal [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walkow, Walter M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-08-31

The United States Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Program sponsors nuclear fuel cycle research and development. As part of its Fuel Cycle Options campaign, the DOE has established the Nuclear Fuel Cycle Options Catalog. The catalog is intended for use by the Fuel Cycle Technologies Program in planning its research and development activities and disseminating information regarding nuclear energy to interested parties. The purpose of this report is to document the improvements and additions that have been made to the Nuclear Fuel Cycle Options Catalog in the 2016 fiscal year.

Nuclear Fuel Cycle Options Catalog FY15 Improvements and Additions.

Energy Technology Data Exchange (ETDEWEB)

Price, Laura L. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Barela, Amanda Crystal [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Walkow, Walter M. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

2015-11-01

The United States Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Program sponsors nuclear fuel cycle research and development. As part of its Fuel Cycle Options campaign, the DOE has established the Nuclear Fuel Cycle Options Catalog. The catalog is intended for use by the Fuel Cycle Technologies Program in planning its research and development activities and disseminating information regarding nuclear energy to interested parties. The purpose of this report is to document the improvements and additions that have been made to the Nuclear Fuel Cycle Options Catalog in the 2015 fiscal year.

Analysis of economy characteristics and improvement ways for China nuclear power

International Nuclear Information System (INIS)

Li Yong

2010-01-01

For the nuclear power industry, due to characteristics of its own, its economy is quite different from that of the traditional fossil-fuel power. This paper studied the basic characteristics of the nuclear power economy and the status of economy of domestic nuclear power, and analyzed the main ways to improve the nuclear power economy. (authors)

Effectively managing nuclear risk through human performance improvement

International Nuclear Information System (INIS)

Coe, R.P.

2004-01-01

Full text: The US commercial nuclear industry has just completed an outstanding decade of plant performance. Safety levels and electric production are at unprecedented high levels and continue to exceed even high industry goals. Nuclear energy continues to keep the highest priority on performance improvement programs and highly trained/qualified people that maintain its record setting safety and reliability of operations. While the industry has maintained a consistently high level of performance, the advent of deregulation and the consolidation of NPP ownership, as well as the current climate of concern about both rising energy costs and availability of power, has raised the standard for nuclear energy's level of competitiveness in today's market place. The resulting challenge is how to more effectively manage risk and improve performance even further in a generally high performing organization. Newer technology and more training by themselves are not the answer. Rather, the answer will lie in the human side of the organization and management's ability to tap into the unused potential of employee commitment and productivity. It is people who offer the greatest potential for organizational success. Given the fact that human performance has been demonstrated to yield higher rates of return than physical capital, it makes good business sense to determine how to encourage the behaviors in the workplace to manage the risk that will accompany efforts to boost the nuclear industry to new heights of excellence. This means effectively developing a performance improvement culture through identifying measurable performance indicators and determining how behaviors can best be influenced to improve those indicators. It also means seeing a culture of performance improvement and risk management as a strategic planning tool rather than a solution to a particular problem. One of the most effective ways to develop this culture of performance improvement and effectively managing risk

Issues to improve the prospects of financing nuclear power plants

International Nuclear Information System (INIS)

2009-01-01

A changing global environment with increasing energy consumption and a need for international energy security is influencing nuclear power projects and the means of obtaining financial backing for such projects. The development of a national nuclear infrastructure can provide significant benefits that influence financial resources. The effects of other factors - such as financing arrangements for capital intensive plants, international design acceptance, harmonization of codes and standards, and assurances of fuel cycle services - need to be considered. An improvement in international cooperation may lower investment risks and contribute to reducing costs. The effects of all these issues need to be assessed and means for supporting the application of nuclear power in the current changing social and commercial environment need to be developed. A key question addressed in this publication is whether financing is the real barrier to nuclear power development or if financing difficulties are simply a consequence of other barriers. It recognizes that there is no single solution and that circumstances in different countries, with different starting points, ambitions and drivers, inevitably affect the balance of approaches followed. The importance of credible, practical, costed and substantiated plans is emphasized. Risks have to be mitigated through an effective strategy and the allocation of risks between parties must be logical. A project has to be demonstrably viable to attract financing. There are three broad areas which must be addressed to improve prospects of investment in nuclear power reactor construction. The first area, and probably the most important, is government and utility commitment and preparedness to adopt and implement a nuclear power programme using internationally recognized standards of safety. The second area is the application of lessons learned from technological and project developments. The third area is financing itself. The conclusions

Improving nuclear generating station response for electrical grid islanding

International Nuclear Information System (INIS)

Chou, Q.B.; Kundur, P.; Acchione, P.N.; Lautsch, B.

1989-01-01

This paper describes problems associated with the performance characteristics of nuclear generating stations which do not have their overall plant control design functions co-ordinated with the other grid controls. The paper presents some design changes to typical nuclear plant controls which result in a significant improvement in both the performance of the grid island and the chances of the nuclear units staying on-line following the disturbance. This paper focuses on four areas of the overall unit controls and turbine governor controls which could be modified to better co-ordinate the control functions of the nuclear units with the electrical grid. Some simulation results are presented to show the performance of a typical electrical grid island containing a nuclear unit with and without the changes

The continuous improvement system of nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Rivera C, A.

2009-10-01

This paper describes the continuous improvement system of nuclear power plant of Laguna Verde and the achievements in implementing the same and additionally two study cases are presents. In February 2009 is noteworthy because the World Association of Nuclear Operators we identified as a learning organization, qualification which shows that the continuous improvement system has matured, and this system will expose as I get to learn to capitalize on our own experiences and external experiences diffused by the nuclear industry. In 2007 the management of nuclear power plants integrates its improvement systems and calls it continuous improvement system and is presented in the same extensive report that won the National Quality Award. This system is made up of 5 subsystems operating individually and are also related 1) human performance; 2) referential comparison or benchmarking; 3) self-assessment; 4) corrective action and 5) external operating experience. Five subsystems that plan, generate, capture, manage, communicate and protect the knowledge generated during the processes execution of nuclear power plant of Laguna Verde, as well as from external sources. The target set in 2007 was to increase the intellectual capital to always give response to meeting the security requirements, but creating a higher value to quality, customer, environment protection and society. In brief each of them, highlighting the objective, expectations management, implementation and some benefits. At the end they will describe two study cases selected to illustrate these cases as the organization learns by their continuous improvement system. (Author)

Improving the safety of future nuclear fission power plants

International Nuclear Information System (INIS)

Frisch, W.; Gros, G.

2001-01-01

The main objectives and principles in nuclear fission reactor safety are presented, e.g. the defence in depth strategy and technical principles such as redundancy, diversity and physical separation. After a brief historical review of the continuous development of safety improvement, the most recent international discussion is presented. This includes mainly the international activities within IAEA and its International Nuclear Safety Advisory Group (INSAG). The safety improvement, presented in recommendations of IAEA and INSAG is expressed as an improvement of all elements and all levels of the defence in depth concept. Special emphasis is put on improvement of the highest level, which requires the implementation of means to mitigate consequences of accidents with severe core damage. The different future concepts are briefly characterised. Some examples from the French-German safety approach are taken to demonstrate how requirements for safety improvement by means of an enhancement of the defence in depth principle are developed

Designing nuclear power plants for improved operation and maintenance

International Nuclear Information System (INIS)

1996-09-01

The purpose of this publication is to compile demonstrated, experience based design guidelines for improving the operability and maintainability of nuclear power plants. The guidelines are for use principally in the design of new nuclear power plants, but should also be useful in upgrading existing designs. The guidelines derive from the experience of operating and maintaining existing nuclear power plants as well as from the design of recent plants. In particular these guidelines are based on and consistent with both the EPRI advanced Light Water Reactor Utility Requirements Document, Volume 1, and the European Utility Requirements for LWR Nuclear Power Plants. 6 refs, 1 fig

Designing nuclear power plants for improved operation and maintenance

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

The purpose of this publication is to compile demonstrated, experience based design guidelines for improving the operability and maintainability of nuclear power plants. The guidelines are for use principally in the design of new nuclear power plants, but should also be useful in upgrading existing designs. The guidelines derive from the experience of operating and maintaining existing nuclear power plants as well as from the design of recent plants. In particular these guidelines are based on and consistent with both the EPRI advanced Light Water Reactor Utility Requirements Document, Volume 1, and the European Utility Requirements for LWR Nuclear Power Plants. 6 refs, 1 fig.

Evaluation of the improvement suggestion system in a nuclear facility

International Nuclear Information System (INIS)

Carnaval, Joao Paulo Rodrigues; Moraes, Geice Almeida

2017-01-01

This work evaluated methods for processing improvement suggestions of a nuclear factory, with the intention to verify those which best fits to the company purposes. Two methods for processing improvement suggestions were applied in the studied organization. The first one was guided to the processing suggestions by specific independent sectors of the company and the second one was conducted to the processing of suggestions by a multidisciplinary team. It has been concluded that a multidisciplinary team focused on research and development would be the best option to the implementation of improvement suggestions and technological innovation on this facility, instead of multi sector processing which revealed to be excessive bureaucratic before the expected goals. This study can be used by nuclear facilities to optimize an existing system of improvements analysis or even guide them for the implantation of a new one. It is more significant for the companies certified on ISO and OHSAS standards for the quality management, environmental and safety and occupational health systems which requires that the continuous improvement must exist and to be demonstrated. But it is also relevant for nuclear plants aiming to implement an Integrated Management System certified on ISO Standards. (author)

Evaluation of the improvement suggestion system in a nuclear facility

Energy Technology Data Exchange (ETDEWEB)

Carnaval, Joao Paulo Rodrigues; Moraes, Geice Almeida, E-mail: joaocarnaval@inb.gov.br, E-mail: geice@inb.gov.br [Industrias Nucleares do Brasil S.A (INB), Resende, RJ (Brazil)

2017-11-01

This work evaluated methods for processing improvement suggestions of a nuclear factory, with the intention to verify those which best fits to the company purposes. Two methods for processing improvement suggestions were applied in the studied organization. The first one was guided to the processing suggestions by specific independent sectors of the company and the second one was conducted to the processing of suggestions by a multidisciplinary team. It has been concluded that a multidisciplinary team focused on research and development would be the best option to the implementation of improvement suggestions and technological innovation on this facility, instead of multi sector processing which revealed to be excessive bureaucratic before the expected goals. This study can be used by nuclear facilities to optimize an existing system of improvements analysis or even guide them for the implantation of a new one. It is more significant for the companies certified on ISO and OHSAS standards for the quality management, environmental and safety and occupational health systems which requires that the continuous improvement must exist and to be demonstrated. But it is also relevant for nuclear plants aiming to implement an Integrated Management System certified on ISO Standards. (author)

Technological improvements to high temperature thermocouples for nuclear reactor applications

International Nuclear Information System (INIS)

Schley, R.; Leveque, J.P.

1980-07-01

The specific operating conditions of thermocouples in nuclear reactors have provided an incentive for further advances in high temperature thermocouple applications and performance. This work covers the manufacture and improvement of existing alloys, the technology of clad thermocouples, calibration drift during heat treatment, resistance to thermal shock and the compatibility of insulating materials with thermo-electric alloys. The results lead to specifying improved operating conditions for thermocouples in nuclear reactor media (pressurized water, sodium, uranium oxide) [fr

A Study on the Improvement of Nuclear Forensics Legal Regime in Korea

International Nuclear Information System (INIS)

Lee, Jung Hyun; Baek, Ye Ji; Kim, Jae Kwang; Chang, Sun Young; Hwang, Yong Soo

2016-01-01

Nuclear forensics is a critical component of security of these materials and an effective investigatory tool in providing evidence for the prosecution of these malicious acts related to the illicit materials. Because nuclear forensic enhances a State's ability to assess and establish linkages between nuclear and radioactive materials, and those who have attempted to transport, possess, or use it without legitimate State control. However, nuclear forensics is not yet reflected in the domestic laws. Therefore, in this study, we examined related international laws and other important efforts. We compared legal regime improvement options between amending existing legislations and introducing new legislation. Then, based on the analysis, we suggested draft provisions of highest level national legislation on nuclear forensics. We reviewed the analysis of international laws and other important efforts on nuclear forensics to improve of domestic legislations on the nuclear forensics. Through the review of current international movement on the nuclear forensics, we concluded as follows; (a) The state government must be responsible for the nuclear forensics (b) Appropriate administrative regulations on nuclear forensics is required within the highest level legislation

A Study on the Improvement of Nuclear Forensics Legal Regime in Korea

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Hyun; Baek, Ye Ji; Kim, Jae Kwang; Chang, Sun Young; Hwang, Yong Soo [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

Nuclear forensics is a critical component of security of these materials and an effective investigatory tool in providing evidence for the prosecution of these malicious acts related to the illicit materials. Because nuclear forensic enhances a State's ability to assess and establish linkages between nuclear and radioactive materials, and those who have attempted to transport, possess, or use it without legitimate State control. However, nuclear forensics is not yet reflected in the domestic laws. Therefore, in this study, we examined related international laws and other important efforts. We compared legal regime improvement options between amending existing legislations and introducing new legislation. Then, based on the analysis, we suggested draft provisions of highest level national legislation on nuclear forensics. We reviewed the analysis of international laws and other important efforts on nuclear forensics to improve of domestic legislations on the nuclear forensics. Through the review of current international movement on the nuclear forensics, we concluded as follows; (a) The state government must be responsible for the nuclear forensics (b) Appropriate administrative regulations on nuclear forensics is required within the highest level legislation.

Improvement of nuclear power plant management applying the lessons learned

International Nuclear Information System (INIS)

Lyon, P.W.

1987-01-01

Active managment participation is a common thread among nuclear power plants with superior performance. Plants that benefit from the hands-on attention of senior managers are typically more reliable and can be expected to have higher margins of safety. There are numerous ways in which utilities are promoting management involvement in the day-to-day operations of their nuclear plants. The Institute of Nuclear Power Operations' (INPO) Plant Performance Indicator Program provides utilities with data in key performance areas, allowing management to monitor performance and concentrate on areas needing attention. Utilities are also setting ambitious short and long-term goals in several performance areas. This increased management attention to nuclear plant operations is reflected in improved nuclear plant performance across the coutry. For instance, over the past five years, the number of significant events per unit has declined, unplanned automatic scrams have been reduced, equivalent availability is about the same (however, many units and the industry median has improved) and collentive radiation exposure and volume of low-level waste shipped per unit are both showing a decreasing trend. (author)

Availability improvement factors at Taipower's nuclear power plant system

International Nuclear Information System (INIS)

Chen, J.H.

1985-01-01

Sufficient electricity to meet the needs of a growing industrial economy, is one of the most important factors in the total economic development of a nation. Currently, nuclear power is considered one of the most economical and available sources of energy. To keep pace with Taiwan's rapid economic development, while also observing our government's policy of diversifying the requirements for imported forms of energy, Taiwan Power Company has embarked upon an ambitious of nuclear power plant construction. This paper discusses the improvement of Taiwan's nuclear power plants. At the present time, Taipower has completed three nuclear power plants. Two of these are located in northern Taiwan, along the East China Sea, while the third is on the southern tip of Taiwan, bordering the South China Sea. These three plants, each with two nuclear generating units, comprise a total nuclear generating capacity of 5144 MWe

A study on the improvement of nuclear emergency countermeasure technology for local government

International Nuclear Information System (INIS)

Khang, Byung Oui; Lee, J. T.; Lee, G. Y.

2005-01-01

There were necessities of the establishment of the regional nuclear emergency plan on the nuclear disaster of nuclear facilities according to the 'nuclear facilities physical protection and emergency preparedness act' and the strengthening of the regional nuclear disaster management system to get confidence on the related national policy from the public and the defining and improving the relationship between local government and other organizations on responsibilities, authorities, duties and support. So, the project was started, the Results of the project are the establishment of Regional Nuclear Emergency Plan (Draft) connected to the national safety management basic plan and national radiological emergency plan which contains the description of the emergency preparedness to respond nuclear disaster and the duty description of related organizations to respond a nuclear disaster and several description of nuclear emergency preparedness. And this report describes the regional nuclear disaster countermeasure technology improvement and the emergency training, drill, exercise methodology

The basic planning for the environmental relationship of improved nuclear power plant

International Nuclear Information System (INIS)

Choi, Seungho; Jung, Hoonseok; Lee, Dongheup

2003-01-01

The Improved Nuclear Power Plant (INPP) which design has been emphasized on the safety, technology and environmental relationship is about to be realized after hard works of design improvements, largely changes made from existing PWR nuclear power plants for three years. It will undoubtedly play a leading role of nuclear power generation industry as a main electric power source and secure a place as a successful issue between development and environment throughout nation-wide understanding and support. (author)

Improvements of reforming performance of a nuclear heated steam reforming process

International Nuclear Information System (INIS)

Hada, Kazuhiko

1996-10-01

Performance of an energy production process by utilizing high temperature nuclear process heat was not competitive to that by utilizing non-nuclear process heat, especially fossil-fired process heat due to its less favorable chemical reaction conditions. Less favorable conditions are because a temperature of the nuclear generated heat is around 950degC and the heat transferring fluid is the helium gas pressurized at around 4 MPa. Improvements of reforming performance of nuclear heated steam reforming process were proposed in the present report. The steam reforming process, one of hydrogen production processes, has the possibility to be industrialized as a nuclear heated process as early as expected, and technical solutions to resolve issues for coupling an HTGR with the steam reforming system are applicable to other nuclear-heated hydrogen production systems. The improvements are as follows: As for the steam reformer, (1) increase in heat input to process gas by applying a bayonet type of reformer tubes and so on, (2) increase in reforming temperature by enhancing heat transfer rate by the use of combined promoters of orifice baffles, cylindrical thermal radiation pipes and other proposal, and (3) increase in conversion rate of methane to hydrogen by optimizing chemical compositions of feed process gas. Regarding system arrangement, a steam generator and superheater are set in the helium loop as downstream coolers of the steam reformer, so as to effectively utilize the residual nuclear heat for generating feed steam. The improvements are estimated to achieve the hydrogen production rate of approximately 3800 STP-m 3 /h for the heat source of 10 MW and therefore will provide the potential competitiveness to a fossil-fired steam reforming process. Those improvements also provide the compactness of reformer tubes, giving the applicability of seamless tubes. (J.P.N.)

Soil moisture determination with Tesla NZK 203 neutron gage

International Nuclear Information System (INIS)

Hally, J.

1977-01-01

Soil moisture was measured using the NZK 203 neutron probe manufactured by Tesla Premysleni. The individual measuring sites were spaced at a distance of 100 m. The NZK 203 set consists of a NPK 202 moisture gage and a NSK 301 scintillation detector and features the following specifications: moisture density measuring range 20 to 500 kg/m 3 , 241 Am-Be fast neutron source having a neutron flux of 7.5x10 4 n.sec -1 +-10%, operating temperature -10 to +45 degC. The measured counting rate was primarily affected by the statistical fluctuation of ionizing radiation and by instrument instability. In order that these effects should be limited each measurement was repeated 10 times with the optimum measurement time at an interval of 20 to 100 sec. The NZK 203 Tesla set was proven to be suitable for rapid and reproducible determination of moisture profiles. (J.P.)

Characterization and improvement of the nuclear safety culture through self-assessment

International Nuclear Information System (INIS)

Levin, H.A.; McGehee, R.B.; Cottle, W.T.

1996-01-01

Organizational culture has a powerful influence on overall corporate performance. The ability to sustain superior results in ensuring the public's health and safety is predicated on an organization's deeply embedded values and behavioral norms and how these affect the ability to change and seek continuous improvement. The nuclear industry is developing increased recognition of the relationship of culture to nuclear safety performance as a critical element of corporate strategy. This paper describes a self-assessment methodology designed to characterize and improve the nuclear safety culture, including processes for addressing employee concerns. This methodology has been successfully applied on more than 30 occasions in the last several years, resulting in measurable improvements in safety performance and quality and employee motivation, productivity, and morale. Benefits and lessons learned are also presented

Resilience improvements to UK nuclear power plants

International Nuclear Information System (INIS)

Pepper, Kevin

2015-01-01

Following the events at Fukushima, the Office for Nuclear Regulation (ONR), the UK nuclear safety regulator, undertook a series of reviews into the resilience of UK nuclear power plants to severe events. These reviews highlighted a number of areas in relation to electrical infrastructure where it considered licensees should review their arrangements, considering both onsite and offsite infrastructure as well as the ability to recover following a complete loss of site infrastructure. In response, UK licensees have been exploring four parallel approaches to improving the resilience for each of their sites. Firstly, through modifications on-site such as enhancements to the installed diesel generators and related systems. Secondly through improvements to the resilience of essential instrumentation to Station Black Out events. Thirdly, through the provision of off-site backup equipment that can be deployed to any site following a severe event. Finally, the provision of event qualified connection points on site to enable timely restoration of long term essential electrical supplies and cooling to key systems. This last item gives a central focus to the issues of switchboard availability and the resilience of the whole network to large potentially common cause internal and external hazards. This paper will discuss the electrically related findings of the ONR reviews, explore the reasoning behind those decisions, and describe the approaches being taken by UK licensees. (authors)

Summary of trial design of improved marine nuclear reactors

International Nuclear Information System (INIS)

1984-01-01

In order to carry out the research and development of improved marine nuclear reactors, the Japan Nuclear Ship Research and Development Agency decided the project for the purpose in accordance with the procedure of research and development shown by the Nuclear Ship Research and Development Committee of Atomic Energy Commission in December, 1979, and along the basic plan regarding the development of nuclear ships of the Agency decided in February, 1981. As the first step, the Agency has been advancing the research on the design evaluation comprising the trial design and conceptual design to establish the concept of the marine reactor plant with excellent economical efficiency and reliability, which will be developed as the practical plant for future nuclear ships. The trial design started as a three-year project from 1983 is related to a 100 MWt marine reactor, and it is to obtain the concept of improved marine reactors which can be realized after adequate development period based on the pressurized water reactors of separate type, one-body type and semi-one-body type. In this summary, the works carried out in fiscal year 1983 are reported, that is, the design and calculation of the reactor core and the equipment of primary cooling system, and the selection of the required items of research and development. (Kako, I.)

Guidelines for using sensitivity analysis and auto-calibration tools for multi-gage or multi-step calibration in SWAT

Science.gov (United States)

Autocalibration of a water quality model such as SWAT (Soil and Water Assessment Tool) can be a powerful, labor-saving tool. When multi-gage or multi-pollutant calibration is desired, autocalibration is essential because the time involved in manual calibration becomes prohibitive. The ArcSWAT Interf...

Efficiency improvement of nuclear power plant operation: the significant role of advanced nuclear fuel technologies

International Nuclear Information System (INIS)

Velde Van de, A.; Burtak, F.

2001-01-01

Due to the increased liberalisation of the power markets, nuclear power generation is being exposed to high cost reduction pressure. In this paper we highlight the role of advanced nuclear fuel technologies to reduce the fuel cycle costs and therefore increase the efficiency of nuclear power plant operation. The key factor is a more efficient utilisation of the fuel and present developments at Siemens are consequently directed at (i) further increase of batch average burnup, (ii) improvement of fuel reliability, (iii) enlargement of fuel operation margins and (iv) improvement of methods for fuel design and core analysis. As a result, the nuclear fuel cycle costs for a typical LWR have been reduced during the past decades by about US$ 35 million per year. The estimated impact of further burnup increases on the fuel cycle costs is expected to be an additional saving of US$10 - 15 million per year. Due to the fact that the fuel will operate closer to design limits, a careful approach is required when introducing advanced fuel features in reload quantities. Trust and co-operation between the fuel vendors and the utilities is a prerequisite for the common success. (authors)

Establishing a Multi-scale Stream Gaging Network in the Whitewater River Basin, Kansas, USA

Science.gov (United States)

Clayton, J.A.; Kean, J.W.

2010-01-01

Investigating the routing of streamflow through a large drainage basin requires the determination of discharge at numerous locations in the channel network. Establishing a dense network of stream gages using conventional methods is both cost-prohibitive and functionally impractical for many research projects. We employ herein a previously tested, fluid-mechanically based model for generating rating curves to establish a stream gaging network in the Whitewater River basin in south-central Kansas. The model was developed for the type of channels typically found in this watershed, meaning that it is designed to handle deep, narrow geomorphically stable channels with irregular planforms, and can model overbank flow over a vegetated floodplain. We applied the model to ten previously ungaged stream reaches in the basin, ranging from third- to sixth-order channels. At each site, detailed field measurements of the channel and floodplain morphology, bed and bank roughness, and vegetation characteristics were used to quantify the roughness for a range of flow stages, from low flow to overbank flooding. Rating curves that relate stage to discharge were developed for all ten sites. Both fieldwork and modeling were completed in less than 2 years during an anomalously dry period in the region, which underscores an advantage of using theoretically based (as opposed to empirically based) discharge estimation techniques. ?? 2010 Springer Science+Business Media B.V.

Summit on Improving the Economics of America's Nuclear Power Plants

International Nuclear Information System (INIS)

Collins, John; Mason, Charles

2016-01-01

The Summit on Improving the Economics of America's Nuclear Power Plants was convened May 19, 2016, by Secretary of Energy Ernest Moniz and co-sponsored by Idaho Senator Mike Crapo to stress the importance of existing nuclear reactors in meeting our nation's energy goals. The summit was also designed to identify and discuss policy options that can be pursued at federal and state levels to address economic challenges, as well as technical options that utilities can use to improve the economic competitiveness of operating nuclear power plants (NPPs) and avoid early plant retirements that are driven by temporary market conditions. The owners of NPPs face difficult economic decisions and are working to improve the performance of existing NPPs. However, it soon became clear that some of the actions taken by states and regional markets have had an impact on the economic viability of existing power plants, including carbon free NPPs. Summit speakers identified concepts and actions that could be taken at state and federal levels to improve the economics of the existing fleet within these regulated and restructured electricity markets. This report summarizes the speeches, concepts, and actions taken.

What can industry do to improve acceptance of nuclear energy?

International Nuclear Information System (INIS)

Panossian, J.

1990-01-01

Even though nuclear energy covers approximately a third of the energy needs of Western Europe without having injured anyone or damaging the environment, its development is considerably hindered in many countries by the opposition of a significant part of the public. The majority of those responsible for the energy supply though, is of the opinion that nuclear energy should continue to play at least as great a role in coming years. In order to lead the public to a positive stand towards nuclear energy, the industry must perfect its product and improve the quality of its communication. One cannot afford to be afraid of admitting that the product, nuclear energy, can be even further improved, even if it is currently at a very high level. Experienced suppliers in the field of nuclear energy have great sums of money with which to work, and should continue to invest in development. It is especially important that the existing nuclear power plants demonstrate exemplary company behavior in respect to safety, availability and economy: this is the best proof of the advantages of nuclear energy and that it is harmless. In regards to communication, it is important to remember that resistance disappears if the public can be directly acquainted with the object of its fears. This explains the special interest in tours of nuclear power plants. The manner in which risk is understood also needs our attention. Risk is not easily understood. It is more easily grasped if it is identified with a highest unsurmountable limit value which corresponds with acceptable consequences. Finally, the public must be informed that nuclear energy is the most environmentally safe means of energy production. (author)

Nuclear energy: benefits versus risks

International Nuclear Information System (INIS)

Jordan, W.H.

1975-01-01

Of the benefits of nuclear power three are described briefly. 1. It offers virtually an inexhaustible supply of cheap electricity, so the real reason for its installation in the U.S. (80 nuclear power plants on order and 15 in operation) is to save money. (2) Nuclear power would offer a chance to clean up the atmosphere; it has been observed that the carbon dioxide concentration in the atmosphere is increasing at about 2 percent per decade, a change that may have implications for long-term effects on climate. (3) Power reactors will undoubtedly be the major producers of radioisotopes in the future; estimates of the benefits of these isotopes are of the order of $1000 million a year from such applications as fluid flow measurements, thickness gages, leak detection, well logging, deformation determinations, agricultural application, biological applications, and in medicine. Risks of operating nuclear power plants can be classified as: thermal pollution of the rivers and lakes; low level release of radioactivity into the air and ground waters caused by the normal operation of nuclear power and reprocessing plants; and the accidental release of large amounts of radioactivity. These risks are put in perspective by comparing them with common risks that man accepts daily--transportation, cigarette smoking, mountain climbing, etc.-- after which nuclear power seems not so risky after all

Advanced digital technology - improving nuclear power plant performance through maintainability

International Nuclear Information System (INIS)

Ford, J.L.; Senechal, R.R.; Altenhein, G.D.; Harvey, R.P.

1998-01-01

In today's energy sector there is ever increasing pressure on utilities to operate power plants at high capacity factors. To ensure nuclear power is competitive into the next century, it is imperative that strategic design improvements be made to enhance the performance of nuclear power plants. There are a number of factors that affect a nuclear power plant's performance; lifetime maintenance is one of the major contributors. The maturing of digital technology has afforded ABB the opportunity to make significant design improvements in the area of maintainability. In keeping with ABB's evolutionary advanced nuclear plant design approach, digital technology has systematically been incorporated into the control and protection systems of the most recent Korean nuclear units in operation and under construction. One example of this was the multi-functional design team approach that was utilized for the development of ABB's Digital Plant Protection System (DPPS). The design team consisted of engineers, maintenance technicians, procurement specialists and manufacturing personnel in order to provide a complete perspective on all facets of the design. The governing design goals of increased reliability and safety, simplicity of design, use of off-the-shelf products and reduced need for periodic surveillance testing were met with the selection of proven ABB-Advant Programmable Logic Controllers (PLCs) as the heart of the DPPS. The application of digital PLC technology allows operation for extended periods without requiring routine maintenance or re-calibration. A well documented commercial dedication program approved by the United States Nuclear Regulatory Commission (US NRC) as part of the System 80+ TM Advanced Light Water Reactor Design Certification Program, allowed the use of off-the shelf products in the design of the safety protection system. In addition, a number of mechanical and electrical improvements were made which support maintainability. The result is a DPPS

Total quality drives nuclear plant improvements

International Nuclear Information System (INIS)

Richey, R.B.

1991-01-01

Total quality (TQ) at Carolina Power and Light (CP and L) is fulfilling a 1985 vision of Sherwood H. Smith, Jr., CP and L's chairman, president, and chief executive officer. The TQ concept has provided a way for employees to align their creative energies toward meeting the business needs of the company. Throughout CP and L, TQ has been recognized as the vehicle for reducing operating costs and improving customer satisfaction. Within the nuclear organization, application of the TQ process has helped to improve communications, resolve challenges, and provide more consistent work practices among CP and L's three nuclear plants. Total quality was introduced from the top down, with initial benefits coming from team interactions. Senior management at CP and L defined the corporate expectations and outlined the training requirements for implementing TQ. Management staffs at each organizational level became steering committees for TQ team activities within their departments. Teams of employees most knowledgeable about a given work area were empowered to solve problems or overcome obstacles related to that work area. Employees learned to become better team players and to appreciate the quality of decisions reached through group consensus. Now, formalized methods that started TQ are becoming part of the day-to-day work ethic

Use of visualization technology to improve decision-making performance in nuclear power plants

International Nuclear Information System (INIS)

Hanes, Lewis F.; Naser, Joseph

2005-01-01

This paper contains a description of modern 2.5-D and 3-D visualization technology that may be applied to improve human situation awareness and decision-making in nuclear power plants. Visualization technology is being applied widely and successfully in several industries. Examples are presented of successful applications in the military, aviation, medical, entertainment, and nuclear industries. Additional opportunities are identified in the nuclear industry that may benefit from improved visualization

Nuclear and radiation techniques - state of art and development trends; Techniki jadrowe i radiacyjne - stan obecny oraz kierunki rozwoju

Energy Technology Data Exchange (ETDEWEB)

Chmielewski, A.G. [Institute of Nuclear Chemistry and Technology, Warsaw (Poland)

1995-12-31

The state of art and development trends of nuclear and radiation techniques in Poland and worldwide have been presented. Among them the radiometric gages, radiation technologies, radiotracer methods and measuring systems for pipeline and vessels, brightness control have been described and their applications in industry, agriculture, health and environment protection have been shown and discussed. 35 refs, 1 fig.

Some predicted peak ground motions for nuclear cratering explosions along the Qattara alignment in Egypt

International Nuclear Information System (INIS)

Bryan, J.B.

1980-01-01

Some predicted peak free-field ground motions at shot depth for the nuclear explosive excavation of a canal in Egypt are summarized. Peak values of displacement, velocity, acceleration, and radial stress are presented as a function of slant range from the working point. Results from two-dimensional TENSOR cratering calculations are included. Fits to ground motion measurements in other media are also shown. This summary is intended to help specify engineering design requirements for detonating nuclear explosive salvos which are required to efficiently excavate the canal. It also should be useful in guiding estimates for gage response ranges in ground motion measurements

CIVAC CV-01 type pressure gage for middle vacuum pumps

International Nuclear Information System (INIS)

Olaru, Grigore; Aculai, Agustin

1997-01-01

The digital display pressure gage CIVAC CV-01 measures absolute pressures in vacuum range of 10 2 - 10 -3 mbar in any installation or equipment generating or using low pressures. It uses a transducer type PIRANI, model TR-02. It is a portable device, easy to exploit and handle. It is applied in research, chemistry, metallurgical industry, mechanical engineering. The system of coupling the transducer to the enclosure where the pressure is to be measured is of type ISO-PNEUROP with flange, collar and adjusting ring with a DN 25 ring gasket. The technical and functional features are: - Measuring error: ± 35% of real conventional value ; - Response time: 20 ms; - Number of measuring points: 1; - Output signal: 0 - 10 V d.c.; - Repeatability error: 5%; - Max weight: 1,600 Kg; Size: 91 x 117 x 187 mm. (authors)

Lessons learned from the Fukushima accident to improve the performance of the national nuclear preparedness system

International Nuclear Information System (INIS)

Dewi Apriliani

2013-01-01

A study of emergency response failure in the early phase of a nuclear accident in Fukushima, Japan has conducted. This study aimed to obtain lesson learned from the problems and constraints that exist at the time of the Fukushima emergency response. This lesson learned will be adjusted to the situation, conditions and problems in nuclear preparedness systems in Indonesia, so that it can obtain the necessary recommendations to improve the performance of SKNN (National Nuclear Emergency Preparedness System). Recommendations include: improvements in coordination and information systems, including early warning systems and dissemination of information; improvements in the preparation of emergency plans/contingency plan, which includes an integrated disaster management; improvement in the development of disaster management practice/field exercise, by extending the scenario and integrate it with nuclear disaster, chemical, biological, and acts of terrorism; and improvement in public education of nuclear emergency preparedness and also improvement in management for dissemination of information to the public and the mass media. These improvements need to be done as part of efforts in preparing a reliable nuclear emergency preparedness in order to support nuclear power plant development plan. (author)

Review of nuclear data improvement needs for nuclear radiation measurement techniques used at the CEA experimental reactor facilities

Directory of Open Access Journals (Sweden)

Destouches Christophe

2016-01-01

Full Text Available The constant improvement of the neutron and gamma calculation codes used in experimental nuclear reactors goes hand in hand with that of the associated nuclear data libraries. The validation of these calculation schemes always requires the confrontation with integral experiments performed in experimental reactors to be completed. Nuclear data of interest, straight as cross sections, or elaborated ones such as reactivity, are always derived from a reaction rate measurement which is the only measurable parameter in a nuclear sensor. So, in order to derive physical parameters from the electric signal of the sensor, one needs specific nuclear data libraries. This paper presents successively the main features of the measurement techniques used in the CEA experimental reactor facilities for the on-line and offline neutron/gamma flux characterizations: reactor dosimetry, neutron flux measurements with miniature fission chambers and Self Power Neutron Detector (SPND and gamma flux measurements with chamber ionization and TLD. For each technique, the nuclear data necessary for their interpretation will be presented, the main identified needs for improvement identified and an analysis of their impact on the quality of the measurement. Finally, a synthesis of the study will be done.

Improvement of layout and piping design for PWR nuclear power plants

International Nuclear Information System (INIS)

Nozue, Kosei; Waki, Masato; Kashima, Hiroo; Yoshioka, Tsuyoshi; Obara, Ichiro.

1983-01-01

For a nuclear power plant, a period of nearly ten years is required from the initial planning stage to commencement of transmission after passing through the design, manufacturing, installation and trial running stages. In the current climate there is a trend that the time required for nuclear power plant construction will further increase when locational problems, thorough explanation to residents in the neighborhood of the construction site and their under-standing, subsequent safety checks and measures to be taken in compliance with various controls and regulations which get tighter year after year, are taken into account. Under such circumstances, in order to satisfy requirements such as improving the reliability of the nuclear power plant design, manufacturing and construction departments, improvements in the economy as well as the quality and shortening of construction periods, the design structure for Mitsubishi PWR nuclear power plants was thoroughly consolidated with regard to layout and piping design. At the same time, diversified design improvements were made with the excellent domestic technology based on plant designs imported from the U.S.A. An outline of the priority items is introduced in this paper. (author)

Referring to IAEA system to improve Chinese standards system on nuclear and radiation safety

International Nuclear Information System (INIS)

Shang Zhaorong; Wang Wenhai

2010-01-01

Referring to the standards system of IAEA, to build and improve the Chinese standards system of nuclear and radiation safety is a long term infrastructure work and an assurance to keep sustainable development of nuclear industry and nuclear technology application in China. The paper analyses the current main problem, and gives some suggestions on developing and improving the system. (authors)

Measures to improve nuclear power project management

International Nuclear Information System (INIS)

Ma Xinchao

2012-01-01

Focusing on correct application of ability level principle in setting organizational structure, the effective management system has been established, and 8 practical management regimes have been developed. Personnel training and management work shall be well done and enhanced. Experience feedback in construction management shall be well done for all systems. Exchange of construction and management techniques shall be actively carried out. All staff shall participate in safety management. KPI system is adopted for assessing stakeholders' project management method, and PDCA cycle is adopted for continued improved. Management level upgrading measures are proposed to ensure the smooth construction of nuclear power project. Setting forth and popularizing management theory can provide reference for and promote the smooth progress of various nuclear power projects. (author)

Some possibilities for improvement of fuel utilization in nuclear power plants

International Nuclear Information System (INIS)

Kocic, A.; Marinkovic, N.

1983-01-01

Methods for improving the nuclear fuel utilization with the emphasis on LWRs are being dealt with in this paper. Some basic results concerning tubular fuel pellets of the Krsko nuclear power plants are presented, showing promising possibilities for uranium saving from the neutronics point of view. (author)

A study in improvement of administrative system in the nuclear safety regulation

International Nuclear Information System (INIS)

Yook, Dong Il; Kuk, Doe Hyeong; Lee, Seong Min; Kim, Jong Sam; Hwang, Sun Ho

2001-03-01

One of the most important tasks to improve nuclear safety regulation system is to separate nuclear regulatory institutes from public agencies which promote the development nuclear power. Moreover, nuclear safety regulation should be not only specialized but optimized to be adapted for new environments such as high-tech information age. Especially, it is necessary to reform the current nuclear safety regulation systems both to be effective under the local self-administration which began to operate in recent years and to be supported by local residents

A study in improvement of administrative system in the nuclear safety regulation

Energy Technology Data Exchange (ETDEWEB)

Yook, Dong Il; Kuk, Doe Hyeong; Lee, Seong Min; Kim, Jong Sam; Hwang, Sun Ho [Chungnam National Univ., Taejon (Korea, Republic of)

2001-03-15

One of the most important tasks to improve nuclear safety regulation system is to separate nuclear regulatory institutes from public agencies which promote the development nuclear power. Moreover, nuclear safety regulation should be not only specialized but optimized to be adapted for new environments such as high-tech information age. Especially, it is necessary to reform the current nuclear safety regulation systems both to be effective under the local self-administration which began to operate in recent years and to be supported by local residents.

Nuclear safety improvement activities related to WWER-440 units in Bulgaria

International Nuclear Information System (INIS)

Gantchev, T.

1998-01-01

The systematic evaluation of the deficiencies of the original design of the WWER reactors brought to the development of a Short Term Programme for Safety Upgrading and Modernisation of Kozloduy WWER-440 units. The implementation of this Programme was completed in 1997. The strive for continuos improvement of Kozloduy Nuclear Power Plant (NPP) safety level, the new requirements of the Bulgarian Nuclear Safety Authority and the public concern initiated the development of new Complex Programme for Safety Improvement (PRG'97), now in a process of implementation. (author)

Nuclear-derived techniques improve cattle productivity and milk quality in Cameroon

International Nuclear Information System (INIS)

Dixit, Aabha

2016-01-01

Increasing agricultural production and improving the quality of milk and meat are key to combating poverty and increasing food security in Africa. Countries such as Cameroon are increasingly turning to innovative, nuclear and nuclear-derived techniques to control and prevent diseases among livestock, and boost cattle and milk production.

Strain measurements of nuclear power plant steam generator antiseismic supports

International Nuclear Information System (INIS)

Kulichevsky, R.

1997-01-01

The nuclear power plants steam generators have different types of structural supports. One of these types are the antiseismic supports, which are intended to be under stress only if a seismic event takes place. Nevertheless, the antiseismic supports lugs, that are welded to the steam generator vessel, are subjected to thermal fatigue because of the temperature cycles related with the shut down and start up operations performed during the life of the nuclear power plant. In order to evaluate the stresses that the lugs are subjected to, several strain gages were welded on two supports lugs, positioned at two heights of one of the Embalse nuclear power plant steam generators. In this paper, the instrumentation used and the strain measurements obtained during two start up operations are presented. The influence of the plant start up operation parameters on the lugs strain evolution is also analyzed. (author) [es

Improvement of uranium production efficiency to meet China's nuclear power requirements

International Nuclear Information System (INIS)

Zhang, R.

1997-01-01

Recently China put the Qinshan Nuclear Power Plant, with an installed capacity of 300 MW, in the province of Zhejiang and the Daya Bay Nuclear Power Plant, with a total installed capacity of 2 x 900 MW, in commercial operation. China plans a rapid growth in nuclear power from 1995 to 2010. China's uranium production will therefore also enter a new period with nuclear power increasing. In order to meet the demand of nuclear power for uranium special attention has been paid to both technical progress improvement using management with the aim of reducing the cost of uranium production. The application of the trackless mining technique has enhanced the uranium mining productivity significantly. China has produced a radiometric sorter, model 5421-2 for pre-concentrating uranium run-of-mine ore. This effectively increases the uranium content in mill feed and decreases the operating cost of hydrometallurgical treatment. The in situ leach technique after blasting is applied underground in the Lantian Mine, in addition to the surface heap leaching, and has obtained a perfect result. The concentrated acid-curing, and ferric sulphate trickle leaching process, will soon be used in commercial operation for treating uranium ore grading -5 to -7 mm in size. The annual production capability of the Yining Mine will be extended to 100 tonnes U using improving in situ leaching technology. For the purpose of improving the uranium production efficiency much work has been done optimizing the distribution of production centres. China plans to expand its uranium production to meet the uranium requirements of the developing nuclear power plants. (author). 4 tabs

Enabling benchmarking and improving operational efficiency at nuclear power plants through adoption of a common process model: SNPM (standard nuclear performance model)

International Nuclear Information System (INIS)

Pete Karns

2006-01-01

To support the projected increase in base-load electricity demand, nuclear operating companies must maintain or improve upon current generation rates, all while their assets continue to age. Certainly new plants are and will be built, however the bulk of the world's nuclear generation comes from plants constructed in the 1970's and 1980's. The nuclear energy industry in the United States has dramatically increased its electricity production over the past decade; from 75.1% in 1994 to 91.9% by 2002 (source NEI US Nuclear Industry Net Capacity Factors - 1980 to 2003). This increase, coupled with lowered production costs; $2.43 in 1994 to $1.71 in 2002 (factored for inflation source NEI US Nuclear Industry net Production Costs 1980 to 2002) is due in large part to a focus on operational excellence that is driven by an industry effort to develop and share best practices for the purposes of benchmarking and improving overall performance. These best-practice processes, known as the standard nuclear performance model (SNPM), present an opportunity for European nuclear power generators who are looking to improve current production rates. In essence the SNPM is a model for the safe, reliable, and economically competitive nuclear power generation. The SNPM has been a joint effort of several industry bodies: Nuclear Energy Institute, Electric Cost Utility Group, and Institute of Nuclear Power Operations (INPO). The standard nuclear performance model (see figure 1) is comprised of eight primary processes, supported by forty four sub-processes and a number of company specific activities and tasks. The processes were originally envisioned by INPO in 1994 and evolved into the SNPM that was originally launched in 1998. Since that time communities of practice (CoPs) have emerged via workshops to further improve the processes and their inter-operability, CoP representatives include people from: nuclear power operating companies, policy bodies, industry suppliers and consultants, and

Building, measuring and improving public confidence in the nuclear regulator

International Nuclear Information System (INIS)

2006-01-01

An important factor for public confidence in the nuclear regulator is the general public trust of the government and its representatives, which is clearly not the same in all countries. Likewise, cultural differences between countries can be considerable, and similar means of communication between government authorities and the public may not be universally effective. Nevertheless, this workshop identified a number of common principles for the communication of nuclear regulatory decisions that can be recommended to all regulators. They have been cited in particular for their ability to help build, measure and/or improve overall public confidence in the nuclear regulator. (author)

A Study on Nonconformance and Construction Method Improvement for Nuclear Power Plant

International Nuclear Information System (INIS)

Kim, Jong Yeob; Roh, Myung Sub

2014-01-01

Advanced power reactor was developed by domestic technology, and finally exported to abroad. In order to place the current nuclear power industrial base, construction has played a big role. Without magnificent construction technology, it would have been impossible to get a safe nuclear power plant on time and in budget. Construction industry occupies very large portion of the economy in South Korea and it has been a core of South Korea's economic growth. With a competitive construction industry and advanced nuclear power plant construction know-how, South Korea could provide safe and reliable nuclear power plants in domestic and world. However there are many repairs and number of corrective actions are in actual construction. Thus, this paper suggested the result of nonconformance and construction method improvement for nuclear power plant. Constructional engineering is a kind of science that has a variety of disciplines including structure, geology, mechanical equipment and other fields. Thus, the development of constructional engineering is closely associated with experience from failure and application advanced construction method. The recent experience in nuclear power plants construction has shown that those improved methods are fully applicable and can help shorten the construction schedule. The future of nuclear power plant construction seems to be more encouraged, even though it has many obstacles

International Conference on Effective Nuclear Regulatory Systems: Sustaining Improvements Globally. Book of Abstracts

International Nuclear Information System (INIS)

2016-01-01

The objective of this conference is to review and assess ways of further improving the effectiveness of regulatory systems for nuclear facilities and activities for both nuclear safety and nuclear security. The action items in the summary presented by the President of the conference held in 2013 in Ottawa, the lessons of the Fukushima Daiichi accident, the discussions at other international conferences and at international experts’ meetings conducted within the framework of the IAEA Action Plan on Nuclear Safety, as well as the CNS and the principles outlined in the Vienna Declaration on Nuclear Safety, will continue to have a significant impact on regulatory systems. All the aforementioned need to be taken into account to sustain improvements to regulatory systems. The expected outcomes of the conference are: - Enhanced safety and security of nuclear installations worldwide; - Challenges in regulating radiation sources and radioactive waste addressed; - Enhanced international cooperation for sustaining regulatory effectiveness; - Strengthened and sustained regulatory competence for nuclear safety and security; and - Strategies and actions for the future identified, as well as issues for consideration by governments, regulatory bodies and international organizations.

Improvement of nuclear power plant operation and maintenance in Japan

International Nuclear Information System (INIS)

Kazushige Hamazaki

1987-01-01

Following the inauguration of commercial nuclear power generation in Japan in 1966, capacity factors were held in the relatively low level until around 1975 due to initial-period troubles. With subsequent improvement, however, capacity factors have climbed steadily and recently been sustaining more than 70%. To obtain this successful result, a various kind of improvement have been made not only for the operation management area but also for the maintenance management area in conjunction with the successive effort to reflect the operating experiences to the early stage design. Nowadays nuclear generation has assumed increasing importance for Japan's electrical power needs, and is making a great contribution to stabilizing power supply costs. (author)

Improving nuclear safety of VVER-440 units

International Nuclear Information System (INIS)

Nochev, T.; Sabinov, S.

2001-01-01

In this paper authors deals with improvement of nuclear safety of WWER-440 units in Kozloduy NPP. Main directions for improving nuclear safety of WWER-440 units were: - to expand number of the design accident; - to increase reliability of equipment important for the safety; - to decrease the probability of initiating events; - improvements the integrity of the primary circuit (application LBB concept, qualification of the pressure safety valves to avoid pressurized thermal shock); - improvement of the fire protection; - improvement of the operation including upgrading and improvement of operational documents, implementation of new system for training the operators and etc.; - reassessment of the seismic response of the plant. Main actions were made at NPP Kozloduy to increase nuclear safety of VVER-440 units. 1. Modernization of Emergency High Pressure Safety Injection System. The modernization includes dividing of independent channels with reservation of active elements. Pumps were exchanged with more effective and reliable ones. HPSIS was increased reliability in general through decrease number of active elements and exchanged with passive. 2. For the purpose of avoiding fast cooling at the primary circuit and obtaining thermal shock of reactor vessel, Main Safety Insulation Valves are installed at NPP Kozloduy. 3. Modernization of Emergency power supplies AC. Oil breakers VMP-10 are exchanged with gas FS-4. 4. Generator breakers are installed to decrease probability of loss power supply and blackout. They provide reliable power supply to the system important for the safety in case of failure on generator. 5. I and C system has been qualified and optimized. 6. Reassessments of Limiting Conditions of Operation and new scram signals have been introduced. 7. An operators-oriented Informational System has been developed. It includes ensuring and updating of equipment data, new informational support of operator and etc. 8. A new auxiliary independent system for

Improvement program of state supervision system for radioactive and nuclear installations

International Nuclear Information System (INIS)

Cardenas, J.

1993-01-01

The current program begins as part of a policy to take care of the development of the cuban nuclear program and with the objective of improving the state supervision system of nuclear and radioactive facilities on the basis of the national experience, good skills internationally accepted and taking into account IAEA recommendations. The program develops the following topics: reorientation and restructure of state supervision, review of the current nuclear legislature, update of regulations of facility safety and qualification and training of state supervision personnel

Improvement of management systems for nuclear facilities

International Nuclear Information System (INIS)

2005-01-01

The area of Quality Management/ Quality Assurance has been changed dramatically over the past years. The nuclear facilities moved from the 'traditional' Quality Assurance approach towards Quality Management Systems, and later a new concept of Integrated Management Systems was introduced. The IAEA is developing a new set of Standards on Integrated Management Systems, which will replace the current 50-C-Q/SG-Q1-Q14 Code. The new set of document will require the integration of all management areas into one coherent management system. The new set of standards on Management Systems promotes the concept of the Integrated Management Systems. Based on new set a big number of documents are under preparation. These documents will address the current issues in the management systems area, e.g. Management of Change, Continuous Improvement, Self-assessment, and Attributes of effective management, etc. Currently NPES is providing a number of TC projects and Extra Budgetary Programmes to assist Member States in this area. The new Standards on Management Systems will be published in 2006. A number of Regulatory bodies already indicated that they would take the new Management System Standards as a basis for the national regulation. This fact will motivate a considerable change in the management of nuclear utilities, requiring a new approach. This activity is suitable for all IAEA Members States with large or limited nuclear capabilities. The service is directed to provide assistance for the management of all organizations carrying on or regulating nuclear activities and facilities

Nuclear power plant licensing: opportunities for improvement

International Nuclear Information System (INIS)

1977-06-01

On April 20, 1977, the Commission directed that recently completed licensing actions be reviewed by the staff for the purpose of identifying ways to improve the effectiveness and efficiency of NRC nuclear power plant licensing activities. This report summarizes the results of a study undertaken by an internal ad hoc Study Group established in response to that directive. The Study Group limited its considerations to safety and environmental review activities. The background, scope, assumptions and objectives of the study are discussed. A prime assumption of this study was that improvements in the efficiency should not be permitted to reduce the current quality achieved in the licensing process. This consideration underlies the conclusions and recommendations of the study

Issues of improving quality of training personnel for nuclear power facilities

International Nuclear Information System (INIS)

Jacko, J.

1987-01-01

The basic stages are characterized of the development of a standard system of personnel training for the start-up, operation and maintenance of nuclear power facilities. The experience is analyzed gained by the Branch Training Centre of the Nuclear Power Plant Research Institute. Suggestions are submitted for improving the quality of personnel training based on Czechoslovak and foreign experiences. (author). 3 refs

Research on improvement of marine nuclear reactors and future perspective

International Nuclear Information System (INIS)

Yokomura, Takeyoshi

1988-01-01

The features when atomic energy is utilized on the sea are that the fuel cost is low, accordingly it is suitable to the power sources of large output, that the volume and weight of fuel are small, accordingly it is suitable to the continuous operation for a long period without refueling, and that oxygen is not required for the burning, accordingly it is suitable to undersea power sources. In USSR, four nuclear icebreakers have been in use, and four more are under construction. A nuclear LASH ship has been operated, and one more is under construction. As the other fields than sea transportation, an electricity generation barge MH-1A of USA used as the auxiliary power source for the Panama Canal and a research submarine NR-1 of USA have been in practical use. With the advance of ocean development in future, the creation of needs such as deep sea power stations, deep sea research ships and deep sea work ships is expected. Marine nuclear reactor technology was begun in the form of the nuclearization of merchant ships, and Savannah of USA, Otto Hahn of West Germany and Mutsu of Japan were built. The marine nuclear reactors built so far and of which the conceptual design was carried out are shown. The improvement of marine reactors is the reduction of size and weight, the simplification of the system, the adoption of self pressurization and self compensation and so on. The research on the improvement in Japan Atomic Energy Research Institute is reported. (Kako, I.)

Preparing for the future by improving the performance of today's nuclear stations: The WANO perspective

International Nuclear Information System (INIS)

Tsutsumi, R.

1999-01-01

The World Association of Nuclear Operators, (WANO) was established in 1989 in the aftermath of the Chernobyl accident with the mission of maximizing the safety and reliability of nuclear power plants by exchanging information and encouraging communication, comparison and emulation among its members. All nuclear power stations in the world are WANO members. WANO conducted an Internal Review in 1997 and its report issued this January confirms that the WANO mission is still valid. As a result of the Internal Review, WANO is taking actions to further improve its programmes. WANO's effort to keep members conscious of safety culture in their daily work at plants is a key element for improving operational safety. WANO will be able to contribute to the future of the nuclear industry by encouraging members to actively participate in WANO programmes which are aimed at improving nuclear safety and plant performance. (author)

A basic plan for the environment-friendly aspects of improved Korean standard nuclear power plant

International Nuclear Information System (INIS)

Jung, Hoon-Seok; Lee, Yong-Koo; Kim, Kwang-Ho

2006-01-01

The Improved Korean Standard Nuclear Power Plant (KSNP+) design has been made possible on the basis of engineering experiences and referring to an in-depth analysis of the design and construction of all the domestic nuclear power plants in operation. The KSNP+ is designed for improved safety, better economics, operability and maintainability by means of advanced technology expecting to demonstrate enhanced performance. The plant also has incorporated several environmentally friendly features through the restoration of excavated areas using an ecological approach, external coloring, figure of turbine generator building and landscaping around nuclear power plant. This is the first time that KOPEC has embarked on inducing environmentally friendly features into the basic plan. This is expected to mitigate the negative perceptions held by the residents in the vicinity of nuclear power plants and will contribute to a new and improved image of nuclear power plants. (authors)

Proceedings of the nuclear safety seminar, 2013: With the spirit of togetherness we improve the synergy of nuclear power control

International Nuclear Information System (INIS)

Heryudo Kusumo; Judi Pramono; Amin Zarkasi; Azhar; Novijanti Noor; Sihana; Djarwani S; Syahrir; Eri Hiswara

2013-06-01

The Proceedings of the nuclear safety seminar was held on Jakarta 19 June 2013 by Nuclear Energy Regulatory Agency. The seminar theme of the spirit with togetherness to improve the synergy of nuclear power control in Indonesia. The presented papers in this proceeding are divided into oral and poster group as follows: 1). Safety and monitoring of radiation facilities and radioactive substances (health, industry, research, environment), and radioactive sources security. 2). Safety and control of nuclear installation and materials (reactor, research reactor, nuclear mining, process and utilization of nuclear material, radioactive waste management, introduction of NPP) and security of nuclear installation and materials. The proceeding consist of 3 handouts from keynotes’ speaker, 23 oral articles and 15 poster articles from BAPETEN, BATAN and outside participants. (PPIKSN)

Aging mitigation and improved programs for nuclear service diesel generators

International Nuclear Information System (INIS)

Hoopingarner, K.R.; Zaloudek, F.R.

1989-12-01

Recent NRC sponsored aging research work on nuclear service diesel generators has resulted in a recommendation that an improved engine management program should be adopted for aging mitigation and reliability improvement. The center of attention should be to ensure diesel-generator operational readiness. This report emphasizes a ''healthy engine concept'' and recommends parameters to be monitored to determine engine condition. The proposed program and approach recommended in this report represent balanced management where diesel generator testing, inspections, monitoring, trending, training, and maintenance all have appropriate importance. Fast-starting and fast-loading test of nuclear service diesels causes very rapid wear of certain engine components. This report documents this aging and wear mechanism and recommends ways to largely eliminate this unique aging stressor. Current periodic intrusive maintenance and engine overhaul practice have been found to be less favorable for safety assurance than engine overhauls based on monitoring and trending results or on a need to correct specific engine defects. This report recommends that the periodic overhaul requirements be re-evaluated. Diesel generator research on aging and wear is sponsored by the US Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research. The research reported in this report was conducted by Pacific Northwest Laboratory (PNL), which is operated for the Department of Energy by Battelle Memorial Institute. 23 refs., 3 figs., 8 tabs

Summit on Improving the Economics of America's Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Collins, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Mason, Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-09-01

The Summit on Improving the Economics of America’s Nuclear Power Plants was convened May 19, 2016, by Secretary of Energy Ernest Moniz and co-sponsored by Idaho Senator Mike Crapo to stress the importance of existing nuclear reactors in meeting our nation’s energy goals. The summit was also designed to identify and discuss policy options that can be pursued at federal and state levels to address economic challenges, as well as technical options that utilities can use to improve the economic competitiveness of operating nuclear power plants (NPPs) and avoid early plant retirements that are driven by temporary market conditions. The owners of NPPs face difficult economic decisions and are working to improve the performance of existing NPPs. However, it soon became clear that some of the actions taken by states and regional markets have had an impact on the economic viability of existing power plants, including carbon free NPPs. Summit speakers identified concepts and actions that could be taken at state and federal levels to improve the economics of the existing fleet within these regulated and restructured electricity markets. This report summarizes the speeches, concepts, and actions taken.

INPO's role in the improvement of nuclear plant safety and reliability

International Nuclear Information System (INIS)

Pate, Z.T.

1985-01-01

The Institute of Nuclear Power Operations (INPO) is a nonprofit, nongovernment corporation dedicated to promoting safe and reliable operation and quality construction of nuclear power plants. The institute is supported by the US nuclear utility industry. All US utilities building or operating nuclear power plants are INPO members. INPO's many activities fall within four major program areas: (1) Evaluations: INPO conducts detailed evaluations of all US operating plants, utility corporate support of nuclear programs, and nuclear projects under active construction. Events analysis and information exchange: INPO reviews plant reports of abnormal or unusual events and reports the lessons learned to the industry. INPO also fosters improved industry communications through a worldwide telecommunications network. (3) Training and accreditation: INPO assists utilities, including international participants, in developing quality training programs; and (4) Assistance: the Institute provides various forms of assistance to members and participants. INPO places emphasis on visits to facilities to aid members and participants in various program or operational areas

Efforts in improvement of nuclear knowledge and information management in Croatia

International Nuclear Information System (INIS)

Pleslic, S.; Novosel, N.

2005-01-01

The IAEA was authorised for exchange of technical and scientific information on peaceful uses of atomic energy and established INIS in 1970 as an international bibliographic database in the nuclear field and in nuclear related areas. Countries at different levels of technological development could derive benefits from INIS output products. The use of nuclear technology relies on the accumulation of knowledge in nuclear science and technology, including both technical information in documents and databases, and knowledge in human resources. Nuclear knowledge and information exchange are important for the process of decision-making. The IAEA supports all Members in systematic knowledge preservation and information exchange, who want to transfer their practical experience to the younger generation and to archive important information. Croatia is involved in activities in knowledge and information management since 1994 when she joined INIS. Thanks to development and application of new information technologies within the INIS information management framework, Members improve the collection, production and dissemination of nuclear knowledge and information. (author)

Improved nuclear fuel element

International Nuclear Information System (INIS)

Klepfer, H.H.

1974-01-01

A nuclear fuel element is described which comprises: 1) an elongated clad container, 2) a layer of high lubricity material being disposed in and adjacent to the clad container, 3) a low neutron capture cross section metal liner being disposed in the clad container and adjacent to the layer, 4) a central core of a body of nuclear fuel material disposed in and partially filling the container and forming an internal cavity in the container, 5) an enclosure integrally secured and sealed at each end of the container, and a nuclear fuel material retaining means positioned in the cavity. (author)

Improvements to secondary coolant circuits of a liquid metal cooled nuclear reactor

International Nuclear Information System (INIS)

Brachet, Alain.

1981-01-01

This invention concerns improvements to secondary coolant-systems for sodium cooled nuclear reactors. It further concerns a protective device for a free level mechanical pump which prevents any gas bubbles due to leaks of the working gas of the pump from entering the secondary system of the nuclear reactor [fr

Improving Insider Threat Training Awareness and Mitigation Programs at Nuclear Facilities.

Energy Technology Data Exchange (ETDEWEB)

Abbott, Shannon [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-06-01

In recent years, insider threat programs have become an important aspect of nuclear security, and nuclear security training courses. However, many nuclear security insider threat programs fail to address the insider threat attack and monitoring potential that exists on information technology (IT) systems. This failure is critical because of the importance of information technology and networks in today’s world. IT systems offer an opportunity to perpetrate dangerous insider attacks, but they also present an opportunity to monitor for them and prevent them. This paper suggests a number of best practices for monitoring and preventing insider attacks on IT systems, and proposes the development of a new IT insider threat tabletop that can be used to help train nuclear security practitioners on how best to implement IT insider threat prevention best practices. The development of IT insider threat best practices and a practical tabletop exercise will allow nuclear security practitioners to improve nuclear security trainings as it integrates a critical part of insider threat prevention into the broader nuclear security system.

The continuous improvement in quality management for nuclear fuel manufacturing in CNNC

International Nuclear Information System (INIS)

Wang Xiaoling

2004-01-01

The nuclear fuel plant has been keeping good records in quality. Only one pot failure has been found in the fuels loaded in the reactors at more than ten years. The paper describes quality management in nuclear fuel manufacturing and focuses on the continuous improvement on quality system and process by running the quality management system, process by quality control group, and data analyze, the requirements and the improvements for the quality system, the measurement system and the standardization system, the importance of clearance system. It also describes the future plans in quality management

Improved people detection in nuclear plants by video processing for safety purpose

Energy Technology Data Exchange (ETDEWEB)

Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A.; Carvalho, Paulo Victor R., E-mail: calexandre@ien.gov.br, E-mail: mol@ien.gov.br, E-mail: paulov@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Seixas, Jose M.; Silva, Eduardo Antonio B., E-mail: seixas@lps.ufrj.br, E-mail: eduardo@smt.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Eletrica; Waintraub, Fabio, E-mail: fabiowaintraub@hotmail.com [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Escola Politecnica. Departamento de Engenharia Eletronica e de Computacao

2013-07-01

This work describes improvements in a surveillance system for safety purposes in nuclear plants. The objective is to track people online in video, in order to estimate the dose received by personnel, during working tasks executed in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a nuclear research reactor, Argonauta. Cameras have been installed within Argonauta room, supplying the data needed. Video processing methods were combined for detecting and tracking people in video. More specifically, segmentation, performed by background subtraction, was combined with a tracking method based on color distribution. The use of both methods improved the overall results. An alternative approach was also evaluated, by means of blind source signal separation. Results are commented, along with perspectives. (author)

Improved people detection in nuclear plants by video processing for safety purpose

International Nuclear Information System (INIS)

Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A.; Carvalho, Paulo Victor R.; Seixas, Jose M.; Silva, Eduardo Antonio B.; Waintraub, Fabio

2013-01-01

This work describes improvements in a surveillance system for safety purposes in nuclear plants. The objective is to track people online in video, in order to estimate the dose received by personnel, during working tasks executed in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a nuclear research reactor, Argonauta. Cameras have been installed within Argonauta room, supplying the data needed. Video processing methods were combined for detecting and tracking people in video. More specifically, segmentation, performed by background subtraction, was combined with a tracking method based on color distribution. The use of both methods improved the overall results. An alternative approach was also evaluated, by means of blind source signal separation. Results are commented, along with perspectives. (author)

Efficiency improvement of nuclear power plant operation: the significant role of advanced nuclear fuel technologies

International Nuclear Information System (INIS)

Van Velde, AA. de; Burtak, F.

2000-01-01

In this paper authors deals with nuclear fuel cycle and their economic aspects. At Siemens, the developments focusing on the reduction of fuel cycle costs are currently directed on .further batch average burnup increase, .improvement of fuel reliability, .enlargement of fuel operation margins, .improvement of methods for fuel design and core analysis. These items will be presented in detail in the full paper and illustrated by the global operating experience of Siemens fuel for both PWRs and BWRs. (authors)

Basic information to improve public acceptance to nuclear energy in Brazil

International Nuclear Information System (INIS)

Gibelli, Sonia M.O.; Lima e Silva, Pedro Paulo de; Xavier, Ana Maria

1997-01-01

In Brazil, the current production of nuclear energy is restricted to Angra I plant, a 657 MW pressurized water reactor, in operation since 1982. Among the eight units predicted in 1975 within the Brazil Germany nuclear agreement, only two have been effectively contracted, namely Angra 2 and 3. The nuclear alternative, likewise all other energy sources, is very much dependable on the assessment of their own benefits compared to the associated risks posed to the population and the environment. The main goal of this article is to provide information to enable the improvement of public acceptance of the use of nuclear energy in the country, by comparing risks associated with different sources as well as pointing out aspects related to risk perception by the public. (author)

Cost benefit justification of nuclear plant reliability improvement

International Nuclear Information System (INIS)

El-Sayed, M.A.H.; Abdelmonem, N.M.

1986-01-01

Nuclear power costs are evaluated on the bases of general ground rules (a) vary from time to time (b) vary from country to another (c) even vary from one reactor type to another. The main objective of an electric utility is to provide the electric energy to the different consummers at the lowest possible cost with reasonable reliability level. Rapid increase of the construction costs and fuel prices in recent years have stimulated a great deal of interest in improving the reliability and productivity of new and existing power plants. One of the most important areas is the improvement of the secondary steam loop and the reactor cooling system. The method for evaluating the reliability of steam loop and cooling system utilizes the cut-set technique. The developed method can be easily used to show to what extent the overall reliability of the nuclear plant is affected by the possible failures in the steam and cooling subsystem. The cost reliability trade-off analysis is used to evaluate alternative schemes in the design with a view towards meeting a high reliability goal. Based on historical or estimated failure and repair rate, the reliability of the alternate scheme can be calculated

Application of improved topsis method to accident emergency decision-making at nuclear power station

International Nuclear Information System (INIS)

Zhang Jin; Cai Qi; Zhang Fan; Chang Ling

2009-01-01

Given the complexity in multi-attribute decision-making on nuclear accident emergency, and by integrating subjective weight and impersonal weight of each evaluating index, a decision-making model for emergency plan at nuclear power stations is established with the application of improved TOPSIS model. The testing results indicated that the improved TOPSIS-based multi-attribute decision-making has a better assessment results. (authors)

Emergency operating instruction improvements at San Onofre Nuclear Generating Station Units 2 and 3

International Nuclear Information System (INIS)

Trillo, M.W.; Smith, B.H.

1989-01-01

In late 1987, San Onofre nuclear generating station (SONGS) began an extensive upgrade of the units 2 and 3 emergency operating instructions (EOIs). The original intent of this program was to incorporate revised generic guidance and to correct problems that were identified by operators. While this program was in progress, the US Nuclear Regulatory Commission (NRC) conducted a series of audits of emergency operating procedure (EOP) development and maintenance programs as 16 commercial nuclear facilities in the United States. These audits included four stations with Combustion Engineering-designed nuclear steam supply systems. (One of these audits included a review of preupgrade SONGS units 2 and 3 EOIs.) Significant industrywide comments resulted from these audits. The NRC has stated its intent to continue the review and audit of EOIs and the associated maintenance programs at all US commercial nuclear facilities. The units 2 and 3 EOI upgrade program developed procedural improvements and procedural program maintenance improvements that address many of the existing audit comments that have been received by the industry. Other resulting improvements may be useful in minimizing NRC comments in future such audits. Specific improvements are discussed. The upgrade program resulted in benefits that were not originally anticipated. The results of this program can be of significant use by other utilities in addressing the industrywide concerns that have been raised in recent NRC audits of EOP development and maintenance programs

Improvements MOIRA system for application to nuclear sites Spanish river

International Nuclear Information System (INIS)

Gallego Diaz, E.; Iglesias Ferrer, R.; Dvorzhak, A.; Hofman, D.

2011-01-01

Possible consequences of a nuclear accident must have radioactive contamination in the medium and long-term freshwater aquatic systems. Faced with this problem, it is essential to have a realistic assessment of the radiological impact, ecological, social and economic potential management strategies, to take the best decisions rationally. MOIRA is a system of decision support developed in the course of the European Framework Programmes with participation of the UPM, which has been improved and adapted to Spanish nuclear sites in recent years in the context ISIDRO Project, sponsored by the Council Nuclear, with the participation of CIEMAT and UPM. The paper focuses on these advances, primarily related to complex hydraulic systems such as rivers Tajo, Ebro and Jucar, which are located several Spanish plants.

Improvement of impact-resistance of a nuclear containment building using fiber reinforced concrete

International Nuclear Information System (INIS)

Jeon, Se-Jin; Jin, Byeong-Moo

2016-01-01

Highlights: • Impact-resistance of a structure can be improved by fiber reinforced concrete (FRC). • Material modeling of FRC is incorporated into finite element analysis of a structure. • A new index for impact-resistance is proposed based on plastic dissipation energy. • A nuclear power plant made of FRC shows improved resistance against aircraft crashes. - Abstract: Since the act of terrorism that occurred in the USA on September 11, 2001, the protection of nuclear power plants against large commercial aircraft crashes has been an emerging issue. Besides the verification of the safety of nuclear power plants in operation or in design, efficient methods for improving the impact-resistance of these structures have been investigated. Fiber reinforced concrete (FRC) has been generally accepted as an effective material for this purpose. In particular, FRC has been developed to improve the tensile behavior of concrete such as tensile strength, ductility and toughness. One of the main fields of application of FRC can be found in blast-protective or blast-resistant concrete structures. It is expected, therefore, that safety-related structures in a nuclear power plant can also be effectively protected from external blast, aircraft crash, etc. by applying FRC. In order to analytically verify the effect on structural behavior of applying FRC, the particular material properties of FRC should be incorporated into the material modeling of a structural analysis program. This study investigates the mathematical modeling of FRC, which represents various aspects of material behavior. Two numerical examples are provided to show the improved impact-resistance of a nuclear containment building that is expected when applying FRC in comparison with ordinary concrete. The analysis results show that the displacement decreases by 43–67% while the impact-resistance increases by 40–82%, depending on a fiber type.

Improvement of impact-resistance of a nuclear containment building using fiber reinforced concrete

Energy Technology Data Exchange (ETDEWEB)

Jeon, Se-Jin, E-mail: conc@ajou.ac.kr [Ajou University, 206, World cup-ro, Yeongtong-gu, Suwon-si, Gyeonggi-do 16499 (Korea, Republic of); Jin, Byeong-Moo [DAEWOO E& C, Institute of Construction Technology, 20, Suil-ro 123beon-gil, Jangan-gu, Suwon-si, Gyeonggi-do 16297 (Korea, Republic of)

2016-08-01

Highlights: • Impact-resistance of a structure can be improved by fiber reinforced concrete (FRC). • Material modeling of FRC is incorporated into finite element analysis of a structure. • A new index for impact-resistance is proposed based on plastic dissipation energy. • A nuclear power plant made of FRC shows improved resistance against aircraft crashes. - Abstract: Since the act of terrorism that occurred in the USA on September 11, 2001, the protection of nuclear power plants against large commercial aircraft crashes has been an emerging issue. Besides the verification of the safety of nuclear power plants in operation or in design, efficient methods for improving the impact-resistance of these structures have been investigated. Fiber reinforced concrete (FRC) has been generally accepted as an effective material for this purpose. In particular, FRC has been developed to improve the tensile behavior of concrete such as tensile strength, ductility and toughness. One of the main fields of application of FRC can be found in blast-protective or blast-resistant concrete structures. It is expected, therefore, that safety-related structures in a nuclear power plant can also be effectively protected from external blast, aircraft crash, etc. by applying FRC. In order to analytically verify the effect on structural behavior of applying FRC, the particular material properties of FRC should be incorporated into the material modeling of a structural analysis program. This study investigates the mathematical modeling of FRC, which represents various aspects of material behavior. Two numerical examples are provided to show the improved impact-resistance of a nuclear containment building that is expected when applying FRC in comparison with ordinary concrete. The analysis results show that the displacement decreases by 43–67% while the impact-resistance increases by 40–82%, depending on a fiber type.

The prospects of improving nuclear power station's safety based on nanotechnology

International Nuclear Information System (INIS)

Klyuchnikov, A.A.; Sharaevskij, I.G.; Fialko, N.M.; Zimin, L.B.

2012-01-01

The article describes the main areas of application of modern high-tech developments in nanothermophysics to improve the safety of nuclear power plants. Performed an analysis of the possibilities of practical applications of efficient nanotechnology for nuclear energy.The article describes the complex issues of concern with the use of nanofluids as a coolant for the most critical equipment of nuclear power plants. It's examined among these equipment the first line of water-cooled nuclear reactor, as well as its emergency cooling system. Performed an analysis of the main issues that relate to the definition of the critical heat flux at boiling liquid on the work surface. From these positions, evaluated the known results on the data og the critical heat flux using nanofluids. In this article was given the main tasks of advanced research in nano-thermal physics for increase nuclear power plant safety in Ukraine

Improvement of computer complex and interface system for compact nuclear simulator

International Nuclear Information System (INIS)

Lee, D. Y.; Park, W. M.; Cha, K. H.; Jung, C. H.; Park, J. C.

1999-01-01

CNS(Compact Nuclear Simulator) was developed at the end of 1980s, and have been used as training simulator for staffs of KAERI during 10 years. The operator panel interface cards and the graphic interface cards were designed with special purpose only for CNS. As these interface cards were worn out for 10 years, it was very difficult to get spare parts and to repair them. And the interface cards were damaged by over current happened by shortage of lamp in the operator panel. To solve these problem, the project 'Improvement of Compact Nuclear Simulator' was started from 1997. This paper only introduces about the improvement of computer complex and interface system

Five Years after the Fukushima Daiichi Accident: Nuclear Safety Improvements and Lessons Learnt

International Nuclear Information System (INIS)

Magwood, William D. IV; Niel, Jean-Christophe; Fuketa, Toyoshi; Sheron, Brian; Boyd, Michael; McGarry, Ann; Dussart-Desart, Roland; Reig, Javier; Hah, Yeonhee; Nieh, Ho; Vasquez-Maignan, Ximena; Salgado, Nancy; White, Andrew; Lazo, Edward; Creswell, Len; Leeds, Eric; Gannon-Picot, Cynthia; Griffiths, Janice

2016-01-01

Countries around the world continue to implement safety improvements and corrective actions based on lessons learnt from the 11 March 2011 accident at the Fukushima Daiichi nuclear power plant. This report provides a high-level summary and update on these activities, and outlines further lessons learnt and challenges identified for future consideration. It focuses on actions taken by NEA committees and NEA member countries, and as such is complementary to reports produced by other international organisations. It is in a spirit of openness and transparency that NEA member countries share this information to illustrate that appropriate actions are being taken to maintain and enhance the level of safety at their nuclear facilities. Nuclear power plants are safer today because of these actions. High-priority follow-on items identified by NEA committees are provided to assist countries in continuously benchmarking and improving their nuclear safety practices. (authors)

To improve nuclear plant safety by learning from accident's experience

International Nuclear Information System (INIS)

Matsumoto, Hidezo; Kida, Masanori; Kato, Hiroyuki; Hara, Shin-ichi

1994-01-01

The ultimate goal of this study is to produce an expert system that enables the experience (records and information) gained from accidents to be put to use towards improving nuclear plant safety. A number of examples have been investigated, both domestic and overseas, in which experience gained from accidents was utilized by utilities in managing and operating their nuclear power stations to improve safety. The result of investigation has been used to create a general 'basic flow' to make the best use of experience. The ultimate goal is achieved by carrying out this 'basic flow' with artificial intelligence (AI). To do this, it is necessary (1) to apply language analysis to process the source information (primary data base; domestic and overseas accident's reports) into the secondary data base, and (2) to establish an expert system for selecting (screening) significant events from the secondary data base. In the processing described in item (1), a multi-lingual thesaurus for nuclear-related terms become necessary because the source information (primary data bases) itself is multi-lingual. In the work described in item (2), the utilization of probabilistic safety assessment (PSA), for example, is a candidate method for judging the significance of events. Achieving the goal thus requires developing various new techniques. As the first step of the above long-term study project, this report proposes the 'basic flow' and presents the concept of how the nuclear-related AI can be used to carry out this 'basic flow'. (author)

Tubular gage for a liquid-metal-cooled fast breeder reactor

International Nuclear Information System (INIS)

Hutter, E.; Tuma, L.A.

1977-01-01

Spring-loaded plungers are arranged about a housing for insertion into a polygonal tube, one plunger for each side of the tube. Each plunger has a locking cam and sliding wedge mechanism which can overcome the spring force associated with the plunger and lock it in any position. The wedges are operated by a rod movable axially in the housing. Several housings with their associated plungers can be stacked. The stack is lowered into the polygonal tube with all of the plungers locked in a fully inward position. When the stack is in the tube, each wedge is moved to release its locking cam, allowing each of the plungers to spring outward against an inner side of the tube. Each housing will thus gage the internal dimensions of the tube at its elevation. The plungers are locked in position, the entire stack is rotated to bring the plungers into the corners described by the intersections of the flat sides, and the stack is removed from the tube whereupon the dimensions across opposite locked plungers may be read by a micrometer

Spiking Phineas Gage: a neurocomputational theory of cognitive-affective integration in decision making.

Science.gov (United States)

Wagar, Brandon M; Thagard, Paul

2004-01-01

The authors present a neurological theory of how cognitive information and emotional information are integrated in the nucleus accumbens during effective decision making. They describe how the nucleus accumbens acts as a gateway to integrate cognitive information from the ventromedial prefrontal cortex and the hippocampus with emotional information from the amygdala. The authors have modeled this integration by a network of spiking artificial neurons organized into separate areas and used this computational model to simulate 2 kinds of cognitive-affective integration. The model simulates successful performance by people with normal cognitive-affective integration. The model also simulates the historical case of Phineas Gage as well as subsequent patients whose ability to make decisions became impeded by damage to the ventromedial prefrontal cortex.

Improving human reliability through better nuclear power plant system design: Program for advanced nuclear power studies

International Nuclear Information System (INIS)

Golay, M.W.

1993-01-01

The project on ''Development of a Theory of the Dependence of Human Reliability upon System Designs as a Means of Improving Nuclear Power Plant Performance'' was been undertaken in order to address the problem of human error in advanced nuclear power plant designs. Lack of a mature theory has retarded progress in reducing likely frequencies of human errors. Work being pursued in this project is to perform a set of experiments involving human subjects who are required to operate, diagnose and respond to changes in computer-simulated systems, relevant to those encountered in nuclear power plants, which are made to differ in complexity in a systematic manner. The computer program used to present the problems to be solved also records the response of the operator as it unfolds

Ten years of real-time streamflow gaging of turkey creek - where we have been and where we are going

Science.gov (United States)

Paul Conrads; Devendra Amatya

2016-01-01

The Turkey Creek watershed is a third-order coastal plain stream system draining an area of approximately 5,240 hectares of the Francis Marion National Forest and located about 37 miles northwest of Charleston near Huger, South Carolina. The U.S. Department of Agriculture (USDA) Forest Service maintained a streamflow gaging station on Turkey Creek from 1964 to 1981....

Efforts in improvement of nuclear knowledge and information management in Croatia

International Nuclear Information System (INIS)

Pleslic, S.; Novosel, N.

2004-01-01

the purpose of promoting and developing scientific, educational and cultural activities in the field of radiation protection and related fields of science. The aim of the Croatian Nuclear Society is to improve science and procedures by the peaceful use of nuclear sciences, technologies, and the appropriate security, as well as to introduce the public with the need and specialities of using nuclear technology. The Croatian Society of Nuclear Medicine and the Croatian Energy Association work with similar goals as previous societies: to improve the general knowledge in society of the benefits of nuclear science and technology and their applications in related fields; to promote all scientific and professional activities by organization and participation on international meetings and conferences; to work on popularisation of nuclear science, its results and applications through organization of popular lectures, editing of publications and participation in manifestations of broader social importance. Croatian Young Generation Network (YGN) as a part of Croatian Nuclear Society was founded in 1999 with goals of attracting young people, education and training of the young experts, knowledge and experience transition between the generations, international contacts and engagement in the international projects, encouraging young experts to join conferences, workshops and seminars, students involvement in the YGN activities and popularisation of the nuclear studies among the students. During almost 10 years Croatian membership in INIS was established as a decentralized system following in this way the INIS philosophy. This decentralized approach to input and output was selected because it represents the most comprehensive coverage of nuclear literature including effective handling of information and the most satisfactory services for users of the INIS Database (DB). Since 1994 input submitting in Croatia was continuous with significant increase of input records satisfying in the

Assessing and improving the safety culture of non-power nuclear installations

International Nuclear Information System (INIS)

Bastin, S.J.; Cameron, R.F.; McDonald, N.R.; Adams, A.; Williamson, A.

2000-01-01

The development and application of safety culture principles has understandably focused on nuclear power plant and fuel cycle facilities and has been based on studies in Europe, North America, Japan and Korea. However, most radiation injuries and deaths have resulted from the mishandling of radioactive sources, inadvertent over-exposure to X-rays and critically incidents, unrelated to nuclear power plant. Within the Forum on Nuclear Cooperation in Asia (FNCA), Australia has been promoting initiatives to apply safety culture principles across all nuclear and radiation application activities and in a manner that is culturally appropriate for Asian countries. ANSTO initiated a Safety Culture Project in 1996 to develop methods for assessing and improving safety culture at nuclear and radiation installations other than power reactors and to trial these at ANSTO and in the Asian region. The project has sensibly drawn on experience from the nuclear power industry, particularly in Japan and Korea. There has been a positive response in the participating countries to addressing safety culture issues in non-power nuclear facilities. This paper reports on the main achievements of the project. Further goals of the project are also identified. (author)

Implementing 'Continuous Improvement' in the U.S. Nuclear Regulatory Commission's Decommissioning Program

International Nuclear Information System (INIS)

Orlando, D. A.; Buckley, J. T.; Johnson, R. L.; Gillen, D. M.

2006-01-01

The United States Nuclear Regulatory Commission's (US NRC's) comprehensive decommissioning program encompasses the decommissioning of all US NRC licensed facilities, ranging from the termination of routine licenses for sealed sources, to the closure of complex materials sites and nuclear power reactor facilities. Of the approximately 200 materials licenses that are terminated each year, most are routine and require little, if any, remediation to meet the US NRC unrestricted release criteria. However, some present technical and policy challenges that require large expenditures of resources, including a few complex materials sites that have requested license termination under the restricted-use provisions of 10 CFR 20.1403. Fiscal constraints to reduce budgeted resources in the decommissioning program, as well as concerns over the time to complete the decommissioning process have led to actions to improve the program and use resources more efficiently. In addition, the US NRC's Strategic Plan requires efforts to identify and implement improvements to US NRC programs in order to improve efficiency, effectiveness, timeliness, and openness, of the US NRC's activities, while maintaining the necessary focus on safety. Decommissioning regulations, and more recently the analysis of several issues associated with implementing those regulations, also have been significant catalysts for improvements in the decommissioning program. Actions in response to these catalysts have resulted in a program focused on the management of complex sites in a comprehensive, consistent, and risk-informed manner, as opposed to the past practice of focusing on sites deemed to be problematic. This paper describes the current status of the decommissioning of US NRC-licensed nuclear facilities, including an overview of recent decommissioning project completion efforts. It provides a detailed summary of past, current, and future improvements in the US NRC decommissioning program including the

Improving nuclear envelope dynamics by EBV BFRF1 facilitates intranuclear component clearance through autophagy.

Science.gov (United States)

Liu, Guan-Ting; Kung, Hsiu-Ni; Chen, Chung-Kuan; Huang, Cheng; Wang, Yung-Li; Yu, Cheng-Pu; Lee, Chung-Pei

2018-02-26

Although a vesicular nucleocytoplasmic transport system is believed to exist in eukaryotic cells, the features of this pathway are mostly unknown. Here, we report that the BFRF1 protein of the Epstein-Barr virus improves vesicular transport of nuclear envelope (NE) to facilitate the translocation and clearance of nuclear components. BFRF1 expression induces vesicles that selectively transport nuclear components to the cytoplasm. With the use of aggregation-prone proteins as tools, we found that aggregated nuclear proteins are dispersed when these BFRF1-induced vesicles are formed. BFRF1-containing vesicles engulf the NE-associated aggregates, exit through from the NE, and putatively fuse with autophagic vacuoles. Chemical treatment and genetic ablation of autophagy-related factors indicate that autophagosome formation and autophagy-linked FYVE protein-mediated autophagic proteolysis are involved in this selective clearance of nuclear proteins. Remarkably, vesicular transport, elicited by BFRF1, also attenuated nuclear aggregates accumulated in neuroblastoma cells. Accordingly, induction of NE-derived vesicles by BFRF1 facilitates nuclear protein translocation and clearance, suggesting that autophagy-coupled transport of nucleus-derived vesicles can be elicited for nuclear component catabolism in mammalian cells.-Liu, G.-T., Kung, H.-N., Chen, C.-K., Huang, C., Wang, Y.-L., Yu, C.-P., Lee, C.-P. Improving nuclear envelope dynamics by EBV BFRF1 facilitates intranuclear component clearance through autophagy.

PHITS code improvements by Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority

International Nuclear Information System (INIS)

Goko, Shinji

2017-01-01

As for the safety analysis to be carried out when a nuclear power company applies for installation permission of facility or equipment, business license, design approval etc., the Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority continuously conducts safety research for the introduction of various technologies and their improvement in order to evaluate the adequacy of this safety analysis. In the field of the shielding analysis of nuclear fuel transportation materials, this group improved the code to make PHITS applicable to this field, and has been promoting the improvement as a tool used for regulations since FY2013. This paper introduced the history and progress of this safety research. PHITS 2.88, which is the latest version as of November 2016, was equipped with the automatic generation function of variance reduction parameters [T-WWG] etc., and developed as the tool equipped with many effective functions in practical application to nuclear power regulations. In addition, this group conducted the verification analysis against nuclear fuel packages, which showed a good agreement with the analysis by MCNP, which is extensively used worldwide and abundant in actual results. It also shows a relatively good agreement with the measured values, when considering differences in analysis and measurement. (A.O.)

Optimal improvement of graphs related to nuclear safeguards problems

International Nuclear Information System (INIS)

Jacobsen, S.E.

1977-08-01

This report develops the methodology for optimally improving graphs related to nuclear safeguards issues. In particular, given a fixed number of dollars, the report provides a method for optimally allocating such dollars over the arcs of a weighted graph (the weights vary as a function of dollars spent on arcs) so as to improve the system effectiveness measure which is the shortest of all shortest paths to several targets. Arc weights can be either clock times or detection probabilities and the algorithm does not explicitly consider all paths to the targets

A performance improvement program applied to the Perry Nuclear Power Plant instrumentation and control section

International Nuclear Information System (INIS)

Anderson, G.R.

1987-01-01

The management at Cleveland Electric Illuminating Company sought to avoid problems typically encountered in the start-up of new nuclear generating units. In response to early indications that such problems may have been developing at their Perry Nuclear Power Plant, several performance improvement initiatives were undertaken. One of these initiatives was a performance improvement evaluation (PIE) for the instrumentation and control (IandC) section at Perry. The IandC PIE, which used a method designed to be adaptable to other disciplines as well, had important results that are applicable to other nuclear power plants

Improved nuclear power plant operations through performance-based safety regulation

International Nuclear Information System (INIS)

Golay, M.W.

1998-01-01

The US Nuclear Regulatory Commission (NRC) has recently instituted use of Risk-Informed, Performance-Based Regulation (RIPBR) for protecting public safety in the use of nuclear power. This was done most importantly during June 1997 in issuance of revised Regulatory Guides and Standard Review Plan (SRP) guidance to licensees and the NRC staff. The propose of RIPBR is to replace the previously-used system of prescriptive regulation, which focuses upon what licensees must do, to a system which focuses upon what they must achieve. RIPBR is goals-oriented and the previous system is means-oriented. This regulatory change is potentially revolutionary, and offers many opportunities for improving the efficiency of improving both nuclear power operations and safety. However, it must be nurtured carefully if is to be successful. The work reported in this paper is concerned with showing how RIPBR can be implemented successfully, with benefits in both areas being attained. It is also concerned with how several of the practical barriers to establishing a workable new regulatory system can be overcome. This work, sponsored by the US Dept. of Energy, is being performed in collaboration with Northeast Utilities Services Crop. and the Idaho National Engineering Laboratory. In our work we have examined a practical safety-related example at the Millstone 3 nuclear power station for implementation of RIPBR. In this examination we have formulated a set of modifications to the plant's technical specifications, and are in the process of investigating their bases and refining the modifications. (author)

Nuclear units operating improvement by using operating experience

International Nuclear Information System (INIS)

Rotaru, I.; Bilegan, I.C.

1997-01-01

The paper presents how the information experience can be used to improve the operation of nuclear units. This areas include the following items: conservative decision making; supervisory oversight; teamwork; control room distraction; communications; expectations and standards; operator training and fundamental knowledge, procedure quality and adherence; plant status awareness. For each of these topics, the information illustrate which are the principles, the lessons learned from operating experience and the most appropriate exemplifying documents. (authors)

Method of operating nuclear power plant

International Nuclear Information System (INIS)

Kodama, Tasuku.

1991-01-01

The present invention concerns a method of operating a plant in which the inside of a reactor container is filled with inert gases. That is, the pressure at the inside of the pressure vessel is controlled based on the values sent from an absolute pressure gage and a pressure low gage during usual operation. A pressure high alarm and a pressure high scram signal are generated from a pressure high detector and a scram pressure detector. With such a constitution, since the pressure at the inside of the reactor is always kept at a slightly positive level relative to the surrounding atmospheric pressure even when high atmospheric pressure approaches to the plant site, air does not flow into the reactor container. Accordingly, the oxygen concentration is not increased. When a low atmospheric pressure approaches, the control operation for the pressure at the inside of the container is not necessary. The amount of the inert gases consumed and the amount of radioactive materials released to the atmosphere are decreased. The method of the present invention improves the safety and the reliability of the reactor operation. (N.H.)

Improvement of Off-site Dose Assessment Code for Operating Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Kim, Juyub; Kim, Juyoul; Shin, Kwangyoung [FNC Technology Co. Ltd., Yongin (Korea, Republic of); You, Songjae; Moon, Jongyi [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2014-05-15

XOQDOQ code which calculates atmospheric Dispersion factor was included into INDAC also. A research on the improvement of off-site dose assessment system for an operating nuclear power plant was performed by KINS in 2011. As a result, following improvements were derived: - Separation of dose assessment for new and existing facilities - Update of food ingestion data - Consideration of multi-unit operation and so on In order to reflect the results, INDAC is under modification. INDAC is an integrated dose assessment code for an operating nuclear power plant and consists of three main modules: XOQDOQ, GASDOS and LIQDOS. The modules are under modification in order to improve the accuracy of assessment and usability. Assessment points for multi-unit release can be calculated through the improved code and the method on dose assessment for multi-unit release has been modified, so that the dose assessment result of multi-unit site becomes more realistic by relieving excessive conservatism. Finally, as the accuracy of calculation modules has been improved, the reliability of dose assessment result has been strengthened.

Indium tin oxide thin film strain gages for use at elevated temperatures

Science.gov (United States)

Luo, Qing

A robust ceramic thin film strain gage based on indium-tin-oxide (ITO) has been developed for static and dynamic strain measurements in advanced propulsion systems at temperatures up to 1400°C. These thin film sensors are ideally suited for in-situ strain measurement in harsh environments such as those encountered in the hot sections of gas turbine engines. A novel self-compensation scheme was developed using thin film platinum resistors placed in series with the active strain element (ITO) to minimize the thermal effect of strain or apparent strain. A mathematical model as well as design rules were developed for the self-compensated circuitry using this approach and close agreement between the model and actual static strain results has been achieved. High frequency dynamic strain tests were performed at temperatures up to 500°C and at frequencies up to 2000Hz to simulate conditions that would be encountered during engine vibration fatigue. The results indicated that the sensors could survive extreme test conditions while maintaining sensitivity. A reversible change in sign of the piezoresistive response from -G to +G was observed in the vicinity of 950°C, suggesting that the change carrier responsible for conduction in the ITO gage had been converted from a net "n-carrier" to a net "p-carrier" semiconductor. Electron spectroscopy for chemical analysis (ESCA) of the ITO films suggested they experienced an interfacial reaction with the Al2O3 substrate at 1400°C. It is likely that oxygen uptake from the substrate is responsible for stabilizing the ITO films to elevated temperatures through the interfacial reaction. Thermo gravimetric analysis of ITO films on alumina at elevated temperatures showed no sublimation of ITO films at temperature up to 1400°C. The surface morphology of ITO films heated to 800, 1200 and 1400°C were also evaluated by atomic force microscopy (AFM). A linear current-voltage (I--V) characteristic indicated that the contact interface

Analysis on nuclear power plant control room system design and improvement based on human factor engineering

International Nuclear Information System (INIS)

Gao Feng; Liu Yanzi; Sun Yongbin

2014-01-01

The design of nuclear power plant control room system is a process of improvement with the implementation of human factor engineering theory and guidance. The method of implementation human factor engineering principles into the nuclear power plant control room system design and improvement was discussed in this paper. It is recommended that comprehensive address should be done from control room system function, human machine interface, digital procedure, control room layout and environment design based on the human factor engineering theory and experience. The main issues which should be paid more attention during the control room system design and improvement also were addressed in this paper, and then advices and notices for the design and improvement of the nuclear power plant control room system were afforded. (authors)

Safety improvement of Paks nuclear power plant

International Nuclear Information System (INIS)

Vamos, G.

1999-01-01

Safety upgrading completed in the early nineties at the Paks NPP include: replacement of steam generator safety valves and control valves; reliability improvement of the electrical supply system; modification of protection logic; enhancement of the fire protection; construction of full scope Training Simulator. Design safety upgrading measures achieved in recent years were concerned with: relocation of steam generator emergency feed-water supply; emergency gas removal from the primary coolant system; hydrogen management in the containment; protection against sumps; preventing of emergency core cooling system tanks from refilling. Increasing seismic resistance, containment assessment, refurbishment of reactor protection system, improving reliability of emergency electrical supply, analysis of internal hazards are now being implemented. Safety upgrading measures which are being prepared include: bleed and feed procedures; reactor over-pressurisation protection in cold state; treatment of steam generator primary to secondary leak accidents. Operational safety improvements are dealing with safety culture, training measures and facilities; symptom based emergency operating procedures; in-service inspection; fire protection. The significance of international cooperation is emphasised in view of achieving nuclear safety standards recognised in EU

Reliability database development and plant performance improvement effort at Korea Hydro and Nuclear Power Co

International Nuclear Information System (INIS)

Oh, S. J.; Hwang, S. W.; Na, J. H.; Lim, H. S.

2008-01-01

Nuclear utilities in recent years have focused on improved plant performance and equipment reliability. In U.S., there is a movement toward process integration. Examples are INPO AP-913 equipment reliability program and the standard nuclear performance model developed by NEI. Synergistic effect from an integrated approach can be far greater than as compared to individual effects from each program. In Korea, PSA for all Korean NPPs (Nuclear Power Plants) has been completed. Plant performance monitoring and improvement is an important goal for KHNP (Korea Hydro and Nuclear Power Company) and a risk monitoring system called RIMS has been developed for all nuclear plants. KHNP is in the process of voluntarily implementing maintenance rule program similar to that in U.S. In the future, KHNP would like to expand the effort to equipment reliability program and to achieve highest equipment reliability and improved plant performance. For improving equipment reliability, the current trend is moving toward preventive/predictive maintenance from corrective maintenance. With the emphasis on preventive maintenance, the failure cause and operation history and environment are important. Hence, the development of accurate reliability database is necessary. Furthermore, the database should be updated regularly and maintained as a living program to reflect the current status of equipment reliability. This paper examines the development of reliability database system and its application of maintenance optimization or Risk Informed Application (RIA). (authors)

Review of Trackside Monitoring Solutions: From Strain Gages to Optical Fibre Sensors

Directory of Open Access Journals (Sweden)

Georges Kouroussis

2015-08-01

Full Text Available A review of recent research on structural monitoring in railway industry is proposed in this paper, with a special focus on stress-based solutions. After a brief analysis of the mechanical behaviour of ballasted railway tracks, an overview of the most common monitoring techniques is presented. A special attention is paid on strain gages and accelerometers for which the accurate mounting position on the track is requisite. These types of solution are then compared to another modern approach based on the use of optical fibres. Besides, an in-depth discussion is made on the evolution of numerical models that investigate the interaction between railway vehicles and tracks. These models are used to validate experimental devices and to predict the best location(s of the sensors. It is hoped that this review article will stimulate further research activities in this continuously expanding field.

Human-centred radiological software techniques supporting improved nuclear safety

International Nuclear Information System (INIS)

Szoeke, Istvan; Johnsen, Terje

2013-01-01

The Institute for Energy Technology (IFE) is an international research foundation for energy and nuclear technology. IFE is also the host for the international OECD Halden Reactor Project. The Software Engineering Department in the Man Technology Organisation at IFE is a leading international centre of competence for the development and evaluation of human-centred technologies, process visualisation, and the lifecycle of high integrity software important to safety. This paper is an attempt to give a general overview of the current, and some of the foreseen, research and development of human-centred radiological software technologies at the Software Engineering department to meet with the need of improved radiological safety for not only nuclear industry but also other industries around the world. (author)

Improved nuclear fuel element

International Nuclear Information System (INIS)

1974-01-01

A nuclear fuel element for use in the core of a nuclear reactor is disclosed and has a metal liner disposed between the cladding and the nuclear fuel material and a high lubricity material in the form of a coating disposed between the liner and the cladding. The liner preferably has a thickness greater than the longest fission product recoil distance and is composed of a low neutron capture cross-section material. The liner is preferably composed of zirconium, an alloy of zirconium, niobium or an alloy of niobium. The liner serves as a preferential reaction site for volatile impurities and fission products and protects the cladding from contact and reaction with such impurities and fission products. The high lubricity material acts as an interface between the liner and the cladding and reduces localized stresses on the cladding due to fuel expansion and cracking of the fuel

Evaluation and proposed improvements to effectiveness of US Nuclear Regulatory Commission generic communications

International Nuclear Information System (INIS)

Thurber, J.A.; Melber, B.D.; Geisendorfer, C.L.; Vallario, R.W.

1988-01-01

This report describes an evaluation of NRC generic communications with industry concerning safety related issues of commercial nuclear power plandts. The analysis builds on the findings presented in the 1986 Office of Analysis and Evaluation of Operational Data (AEOD) Special Study Report, ''An Overview of Nuclear Power Plant Operating Experience Feedback Programs'' (AEOD/S602). The primary objective of the report is to present practical recommendations for improving NRC's documents and generic communications system. The report is based upon a systematic review and evaluation of NRC and industry operating experience documents. It also includes an analysis of interviews with licensee personnel at five utilities and their nuclear power plants. NRC regional and headquarters managers and staff were also interviewed for the study. NRC and licensee personnel interviewed are generally satisfied with the current NRC-industry communications system; however, several problems and potential solutions to those problems are identified in this study. The report makes seven major recommendations for improvement in the effectiveness of NRC-industry generic communications about nuclear power plant operating experience

Peak-flow frequency analyses and results based on data through water year 2011 for selected streamflow-gaging stations in or near Montana: Chapter C in Montana StreamStats

Science.gov (United States)

Sando, Steven K.; McCarthy, Peter M.; Dutton, DeAnn M.

2016-04-05

Chapter C of this Scientific Investigations Report documents results from a study by the U.S. Geological Survey, in cooperation with the Montana Department of Transportation and the Montana Department of Natural Resources, to provide an update of statewide peak-flow frequency analyses and results for Montana. The purpose of this report chapter is to present peak-flow frequency analyses and results for 725 streamflow-gaging stations in or near Montana based on data through water year 2011. The 725 streamflow-gaging stations included in this study represent nearly all streamflowgaging stations in Montana (plus some from adjacent states or Canadian Provinces) that have at least 10 years of peak-flow records through water year 2011. For 29 of the 725 streamflow-gaging stations, peak-flow frequency analyses and results are reported for both unregulated and regulated conditions. Thus, peak-flow frequency analyses and results are reported for a total of 754 analyses. Estimates of peak-flow magnitudes for 66.7-, 50-, 42.9-, 20-, 10-, 4-, 2-, 1-, 0.5-, and 0.2-percent annual exceedance probabilities are reported. These annual exceedance probabilities correspond to 1.5-, 2-, 2.33-, 5-, 10-, 25-, 50-, 100-, 200-, and 500-year recurrence intervals.

Safety improvements at Canadian nuclear power plants in the aftermath of Fukushima accident

International Nuclear Information System (INIS)

Rzentkowski, G.; Khouaja, H.

2014-01-01

This paper describes the safety review of operating nuclear power plants undertaken by the Canadian Nuclear Safety Commission in light of the March 11, 2011 accident at the Fukushima Daiichi Nuclear Power Plants (NPPs). The review confirmed that the Canadian NPPs are robust and have a strong design relying on multiple layers of defence to protect the public from credible external events. Nevertheless, in the spirit of continuous safety improvements, the review identified a number of recommendations to further strengthen reactor defence-in-depth in preventing and mitigating the consequences of beyond design basis accidents, enhance onsite and offsite emergency response, and improve the CNSC regulatory framework. Progress achieved to date, in implementing these measures, is described in this paper along with a summary of safety benefits for each level of the reactor defence-in-depth. (author)

Safety improvements at Canadian nuclear power plants in the aftermath of Fukushima accident

Energy Technology Data Exchange (ETDEWEB)

Rzentkowski, G.; Khouaja, H. [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

2014-07-01

This paper describes the safety review of operating nuclear power plants undertaken by the Canadian Nuclear Safety Commission in light of the March 11, 2011 accident at the Fukushima Daiichi Nuclear Power Plants (NPPs). The review confirmed that the Canadian NPPs are robust and have a strong design relying on multiple layers of defence to protect the public from credible external events. Nevertheless, in the spirit of continuous safety improvements, the review identified a number of recommendations to further strengthen reactor defence-in-depth in preventing and mitigating the consequences of beyond design basis accidents, enhance onsite and offsite emergency response, and improve the CNSC regulatory framework. Progress achieved to date, in implementing these measures, is described in this paper along with a summary of safety benefits for each level of the reactor defence-in-depth. (author)

Availability Improvement of German Nuclear Power Plants

International Nuclear Information System (INIS)

Wilhelm, Oliver

2008-01-01

High availability is important for the safety and economical performance of Nuclear Power Plants (NPP). The strategy for availability improvement in a typical German PWR shall be discussed here. Key parameters for strategy development are plant design, availability of safety systems, component reliability, preventive maintenance and outage organization. Plant design, availability of safety systems and component reliability are to a greater extent given parameters that can hardly be influenced after the construction of the plant. But they set the frame for maintenance and outage organisation which have shown to have a large influence on the availability of the plant. (author)

Plan for research to improve the safety of light-water nuclear power plants

International Nuclear Information System (INIS)

1978-03-01

This is the U.S. Nuclear Regulatory Commission's first annual report to Congress on recommendations for research on improving the safety of light-water nuclear power plants. Suggestions for reactor safety research were identified in, or received from, various sources, including the Advisory Committee on Reactor Safeguards, the NRC regulatory staff, and the consultants to the Research Review Group. After an initial screening to eliminate those not related to improved reactor safety, all the suggestions were consolidated into research topics. It is recommended that the following research projects be carried out: alternate containment concepts, especially vented containments; alternate decay heat removal concepts, especially add-on bunkered systems; alternate emergency core cooling concepts; improved in-plant accident response; and advanced seismic designs

Technical improvement of ATE system of Ling'ao Nuclear Power Plant Phase II

International Nuclear Information System (INIS)

Zhu Xingbao; Xiong Jingchuan; Liang Qiaohong

2009-01-01

In order to solve the problem that the content of SO 4 2- in Steam Generator significantly increased beyond the criteria after the use of the condensate treatment (ATE) system in Daya Bay Nuclear Power Plant and Ling'ao Nuclear Power Plant Phase I, technical improvement have been conducted on the sizes of the fore cation bed and the mixed bed, water distributing devices, ion exchange resins and separation facility. The effectiveness for the ion exchange of the mixed bed is improved, the resolved substance of cation resin is decreased; it is more impossible for fragments and powder which would lead high SO 4 2- content in Steam Generator. Finally, the quality of the steam-water could be improved and ensured. (authors)

Near-term improvements for nuclear power plant control room annunciator systems

International Nuclear Information System (INIS)

Rankin, W.L.; Duvernoy, E.G.; Ames, K.R.; Morgenstern, M.H.; Eckenrode, R.J.

1983-04-01

This report sets forth a basic design philosophy with its associated functional criteria and design principles for present-day, hard-wired annunciator systems in the control rooms of nuclear power plants. It also presents a variety of annunciator design features that are either necessary for or useful to the implementation of the design philosophy. The information contained in this report is synthesized from an extensive literature review, from inspection and analysis of control room annunciator systems in the nuclear industry and in related industries, and from discussions with a variety of individuals who are knowledgeable about annunciator systems, nuclear plant control rooms, or both. This information should help licensees and license applicants in improving their hard-wired, control room annunciator systems as outlined by NUREG-0700

Involvement of WHO in the improvement of nuclear medicine in developing countries

International Nuclear Information System (INIS)

Souchkevitch, G.N.

1986-01-01

The World Health Organization's programme on nuclear medicine deals with the organization of nuclear medicine services, the training of personnel, the efficacy and efficiency of nuclear medicine, and quality assurance in nuclear medicine, instrumentation and radiopharmaceuticals. An analysis of the present situation in diagnostic imaging shows that new techniques and especially ultrasonography (US) may successfully compete with nuclear medicine. WHO is therefore concerned to stimulate objective evaluations of the appropriate role of each diagnostic imaging technology and to make relevant recommendations. In diagnostic nuclear medicine, the following main objectives are included in the WHO strategy: to restrict diagnostic nuclear medicine to those diseases where it cannot be substituted by other less costly and complicated methods; to decrease the cost of diagnostic procedures; and to prevent radiation hazard to patients, personnel and the public from the expanded use of radiopharmaceuticals. In the developing world this strategy may be carried out in two stages: (1) implementation of US in diagnostic services and the initiation of a comparative study of the diagnostic value of US and nuclear medicine imaging techniques in common diseases; (2) working out appropriate recommendations on a rational approach in imaging diagnostics and substitution of nuclear medicine by US in appropriate areas. The Intercomparison Study on Quality Performance of Nuclear Medicine Imaging Devices, established by WHO jointly with the International Atomic Energy Agency, and the organization of training workshops are examples of a successful approach to quality improvement in nuclear medicine in developing countries. (author)

Using international experience to improve performance of nuclear power plants

International Nuclear Information System (INIS)

Calori, F.; Csik, B.J.; Strickert, R.J.

1989-01-01

Information on performance achievements will assist nuclear power plant operating organizations to develop initiatives for improved or continued high performance of their plants. The paper describes the activities of the IAEA in reviewing and analysing the reasons for good performance by contacting operating organizations identified by its Power Reactor Information System as showing continued good performance. Discussions with operations personnel of utilities have indicated practices which have a major positive impact on good performance and which are generally common to all well performing organizations contacted. The IAEA also promotes further activities directed primarily to the achievement of standards of excellence in nuclear power operation. These are briefly commented

Communicating about nuclear events: Some suggestions to improve INES

International Nuclear Information System (INIS)

Kermisch, Céline; Labeau, Pierre-Etienne

2013-01-01

This paper provides a critical analysis of the International Nuclear and Radiological Event Scale (INES) and its use, both from an epistemic and an ethical perspective. As very few papers have been dedicated to this subject, our critical analysis is mainly based on the INES 2009 User's Manual and on technical information issued by different nuclear agencies. Our critical analysis leads to suggest several elements, which could contribute to the improvement of the INES scale and thereby to a better communication about nuclear events. First, we show that multiple criteria are used to assign an INES rating, which could lead to an insufficient differentiation between events. In order to avoid this issue, we suggest to clarify the criteria that are used to assess the level of the event. Then, we show that level 7 of the INES scale is ill-defined as it does not allow to properly take differences in severity between disasters into account. In this regard, we recommend to use an open scale instead. Moreover, we highlight the fact that INES is able to take into account neither events with long-term evolution nor events involving multiple initiators. In this respect, we suggest providing additional guidelines and reflecting about the data on which to rely, in order to assess an INES level. Furthermore, we reflect on who should be rating a nuclear event and we recommend that, for severe events, an independent and plural agency should be in charge. Finally, we show why INES appears to be insufficient for a global communication, and we suggest to complement the INES rating with additional information in parallel. -- Highlights: •We provide a critical analysis of the INES scale and suggestions to improve it. •The rating criteria should be clarified to allow differentiation between events. •An open scale should be used to differentiate between level-7 accidents. •Additional guidelines should be provided for complex and evolving events. •We provide suggestions to satisfy

National symposium: nuclear technique in industry, medicine, agriculture and environment protection. Abstracts of papers

International Nuclear Information System (INIS)

1995-01-01

The National Symposium 'Nuclear Techniques in Industry, Medicine, Agriculture and Environment Protection' has been held in Rynia near Warsaw from 24 to 27 April 1995. Totally 94 lectures have been presented. The actual state of art in Polish investigations have been shown in all branches of applied nuclear sciences. The plenary session devoted to general topics has began the symposium. Further conference has been divided into 18 subject sessions. There were: 1) radiation technologies in environment protection; 2) radiation technologies in materials engineering; 3) radiation preservation in food; 4) radiation techniques for medical use; 5) radiotracers in industrial investigations; 6) radiotracers in water and sewage management and leak control; 7) tracers in hydrology; 8) radiotracers in materials testing; 9) instruments for environment protection, 10) radiometric industrial gages; 11) diagnostic and testing instruments; 12) application of nuclear techniques in materials testing; 13) applications of nuclear techniques in geology and hydrogeology; 14) radioanalytical methods; 15) radiation detectors; 16) radiation measurements; 17) data processing from radiometric experiments; 18) accelerators, isotopes manufacturing, INIS

Thermal expansion and magnetostriction measurements at cryogenic temperature using the strain gage method

Science.gov (United States)

Wang, Wei; Liu, Huiming; Huang, Rongjin; Zhao, Yuqiang; Huang, Chuangjun; Guo, Shibin; Shan, Yi; Li, Laifeng

2018-03-01

Thermal expansion and magnetostriction, the strain responses of a material to temperature and a magnetic field, especially properties at low temperature, are extremely useful to study electronic and phononic properties, phase transitions, quantum criticality, and other interesting phenomena in cryogenic engineering and materials science. However, traditional dilatometers cannot provide magnetic field and ultra low temperature (＜77 K) environment easily. This paper describes the design and test results of thermal expansion and magnetostriction at cryogenic temperature using the strain gage method based on a Physical Properties Measurements System (PPMS). The interfacing software and automation were developed using LabVIEW. The sample temperature range can be tuned continuously between 1.8 K and 400 K. With this PPMS-aided measuring system, we can observe temperature and magnetic field dependence of the linear thermal expansion of different solid materials easily and accurately.

Evaluation of barriers and resilience to improve organizational performance in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Nelson, P. F.; Martin del Campo, C., E-mail: pnelson_007@yahoo.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, Jiutepec 62550, Morelos (Mexico)

2014-10-15

In this study, several models are built from the information contained in the Condition Reports from the Corrective Action Program ar a nuclear power plant. Condition Reports are seen as indications of organizational stress levels with consequential Condition Reports being further evidence of organizational resilience being exceeded. Also contained in this paper is an examination of methods used to assess organizational resilience thresholds to preclude consequential events, based on examination of the number and severity of the Condition Reports. In combination with PSA risk insights, it is possible to identify risk significant procedures and their corresponding risk significant steps. Leading indicators can be used to identify the need for installing a barrier or defense to reduce human errors in a nuclear power plant. These indicators are developed from the Corrective Action Program data by detecting increases in events. Organizational barriers can then be identified to improve performance. The resulting identified barriers are evaluated to rank the value of each possible barrier, and determine the best barrier(s) to implement. The tool described in this paper is designed to provide a systematic approach to identify areas where improvements in organizational effectiveness best reduce the likelihood of consequential events. Due to the uncertainty of many of the factors that influence the performance of humans in nuclear power plant activities, we propose using Bayesian networks to identify sources of organizational errors leading to consequential events. This study, using actual nuclear power plant data, includes a method for data processing and highlights some potential uses of Bayesian networks for improving organizational effectiveness in the nuclear power industry. (Author)

Evaluation of barriers and resilience to improve organizational performance in nuclear power plants

International Nuclear Information System (INIS)

Nelson, P. F.; Martin del Campo, C.

2014-10-01

In this study, several models are built from the information contained in the Condition Reports from the Corrective Action Program ar a nuclear power plant. Condition Reports are seen as indications of organizational stress levels with consequential Condition Reports being further evidence of organizational resilience being exceeded. Also contained in this paper is an examination of methods used to assess organizational resilience thresholds to preclude consequential events, based on examination of the number and severity of the Condition Reports. In combination with PSA risk insights, it is possible to identify risk significant procedures and their corresponding risk significant steps. Leading indicators can be used to identify the need for installing a barrier or defense to reduce human errors in a nuclear power plant. These indicators are developed from the Corrective Action Program data by detecting increases in events. Organizational barriers can then be identified to improve performance. The resulting identified barriers are evaluated to rank the value of each possible barrier, and determine the best barrier(s) to implement. The tool described in this paper is designed to provide a systematic approach to identify areas where improvements in organizational effectiveness best reduce the likelihood of consequential events. Due to the uncertainty of many of the factors that influence the performance of humans in nuclear power plant activities, we propose using Bayesian networks to identify sources of organizational errors leading to consequential events. This study, using actual nuclear power plant data, includes a method for data processing and highlights some potential uses of Bayesian networks for improving organizational effectiveness in the nuclear power industry. (Author)

A method for systematic resource allocation for improved nuclear power plant performance

International Nuclear Information System (INIS)

Doboe, L.; Golay, M.; Todreas, N.; Li, F.

2000-01-01

An investigation was made on plant improvement investments in terms of the methods and criteria used in cooperation with the staffs of a group of nuclear power plants, aiming to understand better the methods used within US nuclear power plants for allocating investments. Cost analyses were being used the authors translated the process into a mathematical format. A spectrum of practices, ranging from use of informal power relationship-based processes to format benefit was found among different organizations. Cost-based processes structured to take into account a broad range of decision factors. Factors such as cost results, risk aversion and required uncertainty premiums were included in the treatment. Ultimately, competing investments can be ranked using the method presented in order of their return upon investment at an equivalent level of uncertainty. A method for ranking the attractiveness of nuclear power plant investments is presented which takes into account consistently factors of return upon investment, uncertainty and decision-maker risk aversion. Hopefully its use will result in improved decisions. (M.N.)

Instrumentation of a prestressed concrete containment vessel model

International Nuclear Information System (INIS)

Hessheimer, M.F.; Rightley, M.J.; Matsumoto, T.

1995-01-01

A series of static overpressurization tests of scale models of nuclear containment structures is being conducted by Sandia National Laboratories for the Nuclear Power Engineering Corporation of Japan and the U.S. Nuclear Regulatory Commission. At present, two tests are being planned: a test of a model of a steel containment vessel (SCV) that is representative of an improved, boiling water reactor (BWR) Mark II design; and a test of a model of a prestressed concrete containment vessel (PCCV). This paper discusses plans and the results of a preliminary investigation of the instrumentation of the PCCV model. The instrumentation suite for this model will consist of approximately 2000 channels of data to record displacements, strains in the reinforcing steel, prestressing tendons, concrete, steel liner and liner anchors, as well as pressure and temperature. The instrumentation is being designed to monitor the response of the model during prestressing operations, during Structural Integrity and Integrated Leak Rate testing, and during test to failure of the model. Particular emphasis has been placed on instrumentation of the prestressing system in order to understand the behavior of the prestressing strands at design and beyond design pressure levels. Current plans are to place load cells at both ends of one third of the tendons in addition to placing strain measurement devices along the length of selected tendons. Strain measurements will be made using conventional bonded foil resistance gages and a wire resistance gage, known as a open-quotes Tensmegclose quotes reg-sign gage, specifically designed for use with seven-wire strand. The results of preliminary tests of both types of gages, in the laboratory and in a simulated model configuration, are reported and plans for instrumentation of the model are discussed

Improved nuclear fuel element

International Nuclear Information System (INIS)

1980-01-01

The invention is of a nuclear fuel element which comprises a central core of a body of nuclear fuel material selected from the group consisting of compounds of uranium, plutonium, thorium and mixtures thereof, and an elongated composite cladding container comprising a zirconium alloy tube containing constituents other than zirconium in an amount greater than about 5000 parts per million by weight and an undeformed metal barrier of moderate purity zirconium bonded to the inside surface of the alloy tube. The container encloses the core so as to leave a gap between the container and the core during use in a nuclear reactor. The metal barrier is of moderate purity zirconium with an impurity level on a weight basis of at least 1000ppm and less than 5000ppm. Impurity levels of specific elements are given. Variations of the invention are also specified. The composite cladding reduces chemical interaction, minimizes localized stress and strain corrosion and reduces the likelihood of a splitting failure in the zirconium alloy tube. Other benefits are claimed. (U.K.)

Results of special security inspection on improvement of security management setup in Head Office and Tsuruga Nuclear Power Station of the Japan Atomic Power Company and improvement of facilities in Tsuruga Nuclear Power Station

International Nuclear Information System (INIS)

1982-01-01

In connection with the series of accidents in the Tsuruga Nuclear Power Station, the Agency of Natural Resources and Energy had instructed JAPC to make comprehensive inspection on the security management setup and to take improvement measures in the nuclear power station. The results of the subsequent inspection by ANRE confirmed that the improvements made by JAPC are adequate, and the following items are described: improvement of security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (J.P.N.)

Improvements to the sodium supply system of a nuclear reactor core

International Nuclear Information System (INIS)

Chevallier, Rene; Marchais, Christian.

1981-01-01

This invention concerns an improvement to the sodium supply system of a nuclear reactor core and, in particular, concerns the area included between the outlet of the primary circulation pumps and the core proper. A simplified structure and a lightening of all this linking area between the circulation pumps and the distribution tank under the core is achieved and this results in a very significant reduction in the risks of deterioration and in a definite increase in the reliability of the reactor. The invention is therefore an improvement to the sodium supply system of the nuclear reactor core vessel with incorporated exchangers, in which the cool sodium, after passing through the primary exchangers, is collected in a ring compartment from whence it is taken up by the pumps and moved to at least one pipe reaching a distribution tank located under the reactor core [fr

Seismic coupling of nuclear explosions

International Nuclear Information System (INIS)

Larson, D.B.

1989-01-01

The new Giant Magnet Experimental Facility employing digital recording of explosion induced motion has been constructed and successfully tested. Particle velocity and piezoresistance gage responses can be measured simultaneously thus providing the capability for determining the multi-component stress-strain history in the test material. This capability provides the information necessary for validation of computer models used in simulation of nuclear underground testing, chemical explosion testing, dynamic structural response, earth penetration response, and etc. This report discusses fully coupled and cavity decoupled explosions of the same energy (0.622 kJ) were carried out as experiments to study wave propagation and attenuation in polymethylmethacrylate (PMMA). These experiments produced particle velocity time histories at strains from 2 x 10 -3 to as low as 5.8 x 10 -6 . Other experiments in PMMA, reported recently by Stout and Larson 8 provide additional particle velocity data to strains of 10 -1

Evaluating and improving nuclear power plant operating performance

International Nuclear Information System (INIS)

1999-07-01

This report aims to provide the basis for improvements in the understanding of nuclear power plants operation and ideas for improving future productivity. The purpose of the project was to identify good practices of operating performance at a few of the world's most productive plants. This report was prepared through a series of consultants meetings, a specialists meeting and an Advisory Group meeting with participation of experts from 23 Member States. The report is based on self-assessment of half a dozen plants that have been chosen as representatives of different reactor types in as many different countries, and the views and assessment of the participants on good practices influencing plant performance. Three main areas that influence nuclear power plant availability and reliability were identified in the discussions: (1) management practices, (2) personnel characteristics, and (3) working practices. These areas cover causes influencing plant performance under plant management control. In each area the report describes factors or good practices that positively influence plant availability. The case studies, presented in annexes, contain the plant self-assessment of areas that influence their availability and reliability. Six plants are represented in the case studies: (1) Dukovany (WWER, 1760 MW) in the Czech Republic; (2) Blayais (PWR, 3640 MW) in France; (3) Paks (WWER, 1840 MW) in Hungary; (4) Wolsong 1 (PHWR, 600 MW) in the Republic of Korea; (5) Trillo 1 (PWR, 1066 MW) in Spain; and (6) Limerick (BWR, 2220 MW) in the United States of America

Improvement gives the legislative and regulatory base for the use the nuclear energy in Cuba

International Nuclear Information System (INIS)

Ferrer Iglesias, R.; Sarabia Molina, I.; Guillen Campos, A.

1998-01-01

Presently work the activities are exposed that carries out the Cuban National Center of Nuclear Security in the improvement the mark regulatory for the regulation to the safety uses the nuclear energy on the implementation to the IAEA recommendations as regards security

Improving the reliability of nuclear reprocessing by application of computers and mathematical modelling

International Nuclear Information System (INIS)

Gabowitsch, E.; Trauboth, H.

1982-01-01

After a brief survey of the present and expected future state of nuclear energy utilization, which should demonstrate the significance of nuclear reprocessing, safety and reliability aspects of nuclear reprocessing plants (NRP) are considered. Then, the principal possibilities of modern computer technology including computer systems architecture and application-oriented software for improving the reliability and availability are outlined. In this context, two information systems being developed at the Nuclear Research Center Karlsruhe (KfK) are briefly described. For design evaluation of certain areas of a large NRP mathematical methods and computer-aided tools developed, used or being designed by KfK are discussed. In conclusion, future research to be pursued in information processing and applied mathematics in support of reliable operation of NRP's is proposed. (Auth.)

Inpo programs for improvement of nuclear power plant operations

International Nuclear Information System (INIS)

Edward Moore, C.

1989-01-01

The talk shows how key INPO programs help foster improved nuclear power operations. The talk focuses on the results being seen from six key efforts: evaluations, training and accreditation, assistance, events analysis and information exchange, human performance and maintenance. The talk stresses that all INPO programs are geared toward enhanced performance and that progress in key performance areas since 1980 shows that INPO and U.S. industry efforts are achieving desired results

Overview of human performance improvement initiatives in Nuclear Power Plants (NPPs )

International Nuclear Information System (INIS)

Sharma, Ashok Kumar

2006-01-01

Nuclear Power Plants (NPPs) are very complex systems. Diverse, multiple and redundant technological systems are used for effective control and safety of the NPPs. The increased numbers of such systems require increased operator attention. Additionally, the control stations (man-machine interfaces) are to be kept manageable in size. This sometimes reduces the scope for truly ergonomic design. These limitations, coupled with the shortcomings of human nature, led to unintended human performance problems and errors resulting into poor plant performance worldwide. Some organisational weaknesses, managerial decisions and latent errors also aided and abetted human errors. In view of this, a need was felt for development of performance culture at all levels in NPP organisations. Towards this end, ready-to-use performance improvement tools were developed and used for individual performers, supervisors and managers in the NPPs. This paper describes the experiences of the global nuclear electricity generating industry towards human performance improvement and error reduction. (author)

Improvement of thermo-mechanical properties of ceramic materials for nuclear applications

International Nuclear Information System (INIS)

Decroix, G.M.; Gosset, D.; Kryger, B.; Boussuge, M.; Burlet, H.

1994-01-01

In order to improve the thermo-mechanical properties of materials used as neutron absorbers in nuclear reactors, cermet or cercer have been produced with two original microstructures: micro- or macro-dispersed composites. The composites thermal shock resistance has been evaluated in an image furnace. The microstructures we obtained involve different reinforcement mechanisms, such as crack deflection, crack branching, crack bridging or microcrack toughening, and improvement of thermal conductivity. The results reveal a significant improvement of the thermo-mechanical properties of the boron base neutron absorbers whose fabrication process leads to a macro-dispersed microstructure. (authors). 8 refs., 8 figs., 2 tabs

Supplier selection based on improved MOGA and its application in nuclear power equipment procurement

International Nuclear Information System (INIS)

Yan Zhaojun; Wang Dezhong; Zhou Lei

2007-01-01

Considering the fact that there are few objective and available methods supporting the supplier selection in nuclear power equipment purchasing process, a supplier selection method based on improved multi-objective genetic algorithm (MOGA) is proposed. The simulation results demonstrate the effectiveness and efficiency of this method for the supplier selection in nuclear power equipment procurement process. (authors)

Improvement of ALARA in Taiwan Nuclear Power Plants

International Nuclear Information System (INIS)

Kao, H. M.; Chang, M.

2006-01-01

Full text: Full text: The ALARA(as low as reasonable achievable ) principle is a basic spirit of radiation safety culture and the most important element of a successful radiation safety program. In recent years, the ALARA principle and practices have been widely applied to the three operating nuclear power plants in Taiwan. Through the effective communication and fully cooperation between the authority and utility, the performance goals of improving radiation safety program have been set, and the implementation plans have been proposed and followed. Taking Chinshan nuclear power station as an example, in 2004, the occupational individual dose was 1.13mSv/ person in average,no one exceeded 20mSv ,and the collective dose was 1.03man-Sv/unit which achieved the best record of BWR plant in Taiwan. The radiation reduction approaches and tools adopted by the plants include removing radiation sources, setting radiation shieding, optimizing and controlling the schedule of radiation practices, considering the occupancy factors, and better administrative management to keep exposure ALARA will be discussed in this paper

Studies for improvement of regulatory control on the radioactive effluent released from nuclear facilities

International Nuclear Information System (INIS)

Cheong, Jae Hak; Park, H. M.; Song, M. C.; Lee, K. H.; Jang, J. K.; Chun, J. K.; Jeong, K. H.

2005-05-01

This report contains the second-year results of the research project titled 'Studies for Improvement of Regulatory Control on the Radioactive Effluent Released from Nuclear Facilities' and mainly provides technical and strategic approaches to improve performance of regulatory control on the gaseous effluent released from domestic nuclear facilities. The main result contained here includes overview and technical bases of radioactive gaseous effluent control (Chapter 1), reconsideration of the sensitivity requirements for measurement of radioactivity in gaseous effluent sample (Chapter 2), uncertainty analysis of the calculated radioactivity in gaseous effluent (Chapter 3), and improvement of quantification method of noble gas releases (Chapter 4). In addition, analysis of the impact due to combined sampling of particulate from multiple release points (Chapter 5), comparison of domestic nuclear reactors gaseous effluent data to foreign PWRs (Chapter 6), standardized sampling technique for collection of gaseous tritium (Chapter 7), and application of Xe-133 equivalent concept to gaseous effluent control (Chapter 8) are also provided. As a whole, this report provides a generic approach to improve the performance of regulatory control on the gaseous effluent. Therefore, actual enforcement of the recommendations should be preceded by establishment of a series of action plans reflecting on the site- and facility-specific design and operational features

Improvements in Defense in Depth in French Nuclear Power Plants Following Fukushima Accidents

Energy Technology Data Exchange (ETDEWEB)

Barbaud, J. [EDF SEPTEN, Villeurbanne Cedex (France); Pouget-Abadie, X., E-mail: jean.barbaud@edf.fr [EDF DIN Headquarters, Saint-Denis (France)

2014-10-15

The accidents which occurred in the nuclear power plants in Fukushima-Daiichi resulted in a complementary safety assessment (CSA or stress-tests) of all French NPPs to confirm their compliance with their design bases and to evaluate their behaviour beyond it. They have shown that nuclear facilities have a satisfactory level of safety, but it had been decided to significantly improve their robustness to extreme situations, beyond the safety margins they have already. Planned improvements include several parts, where the main ones are the implementation of a hardened safety core (HSC) of key components for the management of extreme situations resulting from a hazard beyond the design and deployment of a nuclear rapid response force (FARN). The hardened safety core aims to avoid massive releases and lasting effects in the environment. It relies on existing or new components designed or verified to hazards with significant margins compared to the design levels of NPP beyond. It also includes provisions allowing crisis management, including crisis centre and communication means. The FARN complements the HSC and the crisis organization to bring from off-site sufficient human and material resources to increase the autonomy of the site. All these improvement contribute to a better defence in depth. (author)

Use of computer codes to improve nuclear power plant operation

International Nuclear Information System (INIS)

Misak, J.; Polak, V.; Filo, J.; Gatas, J.

1985-01-01

For safety and economic reasons, the scope for carrying out experiments on operational nuclear power plants (NPPs) is very limited and any changes in technical equipment and operating parameters or conditions have to be supported by theoretical calculations. In the Nuclear Power Plant Scientific Research Institute (NIIAEhS), computer codes are systematically used to analyse actual operating events, assess safety aspects of changes in equipment and operating conditions, optimize the conditions, preparation and analysis of NPP startup trials and review and amend operating instructions. In addition, calculation codes are gradually being introduced into power plant computer systems to perform real time processing of the parameters being measured. The paper describes a number of specific examples of the use of calculation codes for the thermohydraulic analysis of operating and accident conditions aimed at improving the operation of WWER-440 units at the Jaslovske Bohunice V-1 and V-2 nuclear power plants. These examples confirm that computer calculations are an effective way of solving operating problems and of further increasing the level of safety and economic efficiency of NPP operation. (author)

Experimental analysis of a nuclear reactor prestressed concrete pressure vessels model

International Nuclear Information System (INIS)

Vallin, C.

1980-01-01

A comprehensible analysis was made of the performance of each set of sensors used to measure the strain and displacement of a 1/20 scale Prestressed Concrete Pressure Vessel (PCPV) model tested at the Instituto de Pesquisas Energeticas e Nucleares (IPEN). Among the three Kinds of sensors used (strain gage, displacement transducers and load cells) the displacement transducers showed the best behavior. The displacemente transducers data was statistically analysed and a linear behavior of the model was observed during the first pressurizations tests. By means of a linear statistical correlation between experimental and expected theoretical data it was found that the model looses the linearity at a pressure between 110-125 atm. (Author) [pt

The improvement of nuclear safety regulation : American, European, Japanese, and South Korean experiences

International Nuclear Information System (INIS)

Cho, Byung Sun

2005-01-01

Key concepts in South Korean nuclear safety regulation are safety and risk. Nuclear regulation in South Korea has required reactor designs and safeguards that reduce the risk of a major accident to less than one in a million reactor-years-a risk supposedly low enough to be acceptable. To data, in South Korean nuclear safety regulation has involved the establishment of many technical standards to enable administration enforcement. In scientific lawsuits in which the legal issue is the validity of specialized technical standards that are used for judge whether a particular nuclear power plant is to be licensed, the concept of uncertainty law is often raised with regard to what extent the examination and judgement by the judicial power affects a discretion made by the administrative office. In other words, the safety standards for nuclear power plants has been adapted as a form of the scientific technical standards widely under the idea of uncertainty law. Thus, the improvement of nuclear safety regulation in South Korea seems to depend on the rational lawmaking and a reasonable, judicial examination of the scientific standards on nuclear safety

Improvement of design and construction technology in Japanese nuclear power plants

International Nuclear Information System (INIS)

Yomei Kato; Kiyoshi Shmizu

1987-01-01

Nuclear power generation currently offers economic merits superior to those of other methods dependant on such thermal power ganeration as petroleum, LNG, or coal. However, it is essential for the nuclear power generation continuously to retain economic superiority through concurently maintaining its high safety features and outstanding reliability. For achieving this purpose, taking into account of importance explained above, we have been developing and improving those of technologies such as design, engineering, and construction regarding the both field of management and techniques useful for plant construction. This paper covers the several instructive matters which Hitachi has accomplished throughout having had his hand in the project jobs. (author)

Evaluating and improving nuclear power plant operating performance

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

This report aims to provide the basis for improvements in the understanding of nuclear power plants operation and ideas for improving future productivity. The purpose of the project was to identify good practices of operating performance at a few of the world`s most productive plants. This report was prepared through a series of consultants meetings, a specialists meeting and an Advisory Group meeting with participation of experts from 23 Member States. The report is based on self-assessment of half a dozen plants that have been chosen as representatives of different reactor types in as many different countries, and the views and assessment of the participants on good practices influencing plant performance. Three main areas that influence nuclear power plant availability and reliability were identified in the discussions: (1) management practices, (2) personnel characteristics, and (3) working practices. These areas cover causes influencing plant performance under plant management control. In each area the report describes factors or good practices that positively influence plant availability. The case studies, presented in annexes, contain the plant self-assessment of areas that influence their availability and reliability. Six plants are represented in the case studies: (1) Dukovany (WWER, 1760 MW) in the Czech Republic; (2) Blayais (PWR, 3640 MW) in France; (3) Paks (WWER, 1840 MW) in Hungary; (4) Wolsong 1 (PHWR, 600 MW) in the Republic of Korea; (5) Trillo 1 (PWR, 1066 MW) in Spain; and (6) Limerick (BWR, 2220 MW) in the United States of America Figs, tabs

Force Reconstruction from Ejection Tests of Stores from Aircraft Used for Model Predictions and Missing/Bad Gages

Energy Technology Data Exchange (ETDEWEB)

Ross, Michael; Cap, Jerome S.; Starr, Michael J.; Urbina, Angel; Brink, Adam Ray

2015-12-01

One of the more severe environments for a store on an aircraft is during the ejection of the store. During this environment it is not possible to instrument all component responses, and it is also likely that some instruments may fail during the environment testing. This work provides a method for developing these responses from failed gages and uninstrumented locations. First, the forces observed by the store during the environment are reconstructed. A simple sampling method is used to reconstruct these forces given various parameters. Then, these forces are applied to a model to generate the component responses. Validation is performed on this methodology.

POWER-GEN '90 conference papers: Volume 7 (Fossil plant performance availability and improvement) and Volume 8 (Nuclear power issues)

International Nuclear Information System (INIS)

Anon.

1990-01-01

This is book 4 of papers presented at the Third International Exhibition and Conference for the Power Generation Industries, December 4-6, 1990. This book contains Volume 7, Fossil Plant Performance Availability and Improvement, and Volume 8, Nuclear Power Issues. The topics of the papers include computer applications in plant operations and maintenance, managing aging plants, plant improvements, plant operations and maintenance, the future of nuclear power, achieving cost effective plant operation, managing nuclear plant aging and license renewal, and the factors affecting a decision to build a new nuclear plant

A study on improvement of export control system for the nuclear facility

International Nuclear Information System (INIS)

Kim, Ok Joo; Shin, Dong Hoon; Yang, Seung Hyo

2012-01-01

The Republic of Korea joined Nuclear Suppliers Group(NSG) in 1995 and became a major nuclear supplier both in name and reality by contracting the Project of UAE Braka Nuclear Power Plant(BNPP) in 2009 and the Project of Jordan Research and Training Reactor(JRTR) in 2010. And ROK is currently negotiating with several countries such as Finland and Vietnam for more projects, so it is expected to obtain more orders of commercial and research reactor. At this point of time, we found that it is difficult to apply individual export licensing system as it is for the big nuclear project such as BNPP and JRTR Project. Because the nuclear project in foreign country contains transfer of thousands of items and technical documents, including a considerable number of strategic items, issuing individual licenses for all items and documents can cause the inefficiency of the project. So, an appropriate export control system which can support such a project is necessary. In this study, we focused on how to improve the export control system to guarantee not only time efficiency but careful management of strategic goods

Nuclear fuel assembly with improved spectral shift-producing rods

International Nuclear Information System (INIS)

Ferrari, H.M.

1987-01-01

This patent describes a nuclear reactor having fuel assemblies and a moderator-coolant liquid flowing through the fuel assemblies, each fuel assembly including an organized array of nuclear fuel rods wherein the moderator-coolant liquid flows along the fuel rods, at least one improved spectral shift-producing rod disposed among the fuel rods. The spectra shift-producing rod consists of: (a) an elongated hollow hermetically-sealed tubular member; (b) a weakened region formed in a portion of the member, the portion being subject to rupture at a given level of internal pressure; and (c) burnable poison material contained in the member which generates gas in the member as operation of the reactor proceeds normally, the material being soluble in the moderator-coolant liquid when brought into contact therewith; (d) the given level of internal pressure being less than the maximum level of internal pressure normally expected to be generated within the member by the poison material by normal operation of the reactor

Improvement suggestions on license extension management for civil nuclear safety equipment activities

International Nuclear Information System (INIS)

Sun Xingjian; Liu Hongji; Han Guoli; Jia Fengcai

2013-01-01

Based on the concepts of Clear Requirements, Comprehensive Review, Objective Assessment, Dynamic Management, this paper gives improvement suggestions on license extension management for civil nuclear safety equipment design, manufacture, installation and non-destructive examination activities, which include establishing a relatively unified license extension review standard, combining multi-views and close linking license review and supervision, full utilizing the daily supervision and inspection results, as well as further improving motivation and elimination mechanism. (authors)

Improvement of gross theory of beta-decay for application to nuclear data

Science.gov (United States)

Koura, Hiroyuki; Yoshida, Tadashi; Tachibana, Takahiro; Chiba, Satoshi

2017-09-01

A theoretical study of β decay and delayed neutron has been carried out with a global β-decay model, the gross theory. The gross theory is based on a consideration of the sum rule of the β-strength function, and gives reasonable results of β-decay rates and delayed neutron in the entire nuclear mass region. In a fissioning nucleus, neutrons are produced by β decay of neutron-rich fission fragments from actinides known as delayed neutrons. The average number of delayed neutrons is estimated based on the sum of the β-delayed neutron-emission probabilities multiplied by the cumulative fission yield for each nucleus. Such a behavior is important to manipulate nuclear reactors, and when we adopt some new high-burn-up reactors, properties of minor actinides will play an important roll in the system, but these data have not been sufficient. We re-analyze and improve the gross theory. For example, we considered the parity of neutrons and protons at the Fermi surface, and treat a suppression for the allowed transitions in the framework of the gross theory. By using the improved gross theory, underestimated half-lives in the neutron-rich indium isotopes and neighboring region increase, and consequently follow experimental trend. The ability of reproduction (and also prediction) of the β-decay rates, delayed-neutron emission probabilities is discussed. With this work, we have described the development of a programming code of the gross theory of β-decay including the improved parts. After preparation finished, this code can be released for the nuclear data community.

Improving human reliability through better nuclear power plant system design. Progress report

International Nuclear Information System (INIS)

Golay, M.W.

1995-01-01

The project on open-quotes Development of a Theory of the Dependence of Human Reliability upon System Designs as a Means of Improving Nuclear Power Plant Performanceclose quotes has been undertaken in order to address the important problem of human error in advanced nuclear power plant designs. Most of the creativity in formulating such concepts has focused upon improving the mechanical reliability of safety related plant systems. However, the lack of a mature theory has retarded similar progress in reducing the likely frequencies of human errors. The main design mechanism used to address this class of concerns has been to reduce or eliminate the human role in plant operations and accident response. The plan of work being pursued in this project is to perform a set of experiments involving human subject who are required to operate, diagnose and respond to changes in computer-simulated systems, relevant to those encountered in nuclear power plants. In the tests the systems are made to differ in complexity in a systematic manner. The computer program used to present the problems to be solved also records the response of the operator as it unfolds. Ultimately this computer is also to be used in compiling the results of the project. The work of this project is focused upon nuclear power plant applications. However, the persuasiveness of human errors in using all sorts of electromechanical machines gives it a much greater potential importance. Because of this we are attempting to pursue our work in a fashion permitting broad generalizations

Analysis of the Convention on Nuclear Safety and Suggestions for Improvement

International Nuclear Information System (INIS)

Choi, K. S.; Viet, Phuong Nguyen

2013-01-01

The innovative approach of the Convention, which is based on incentive after than legal binding, had been considered successful in strengthening the nuclear safety worldwide. However, the nuclear accident at the Fukushima Dai-ichi Nuclear Power Plant (Japan) in March 2011 has exposed a number of weaknesses of the Convention. Given that context, this paper will analyse the characteristics of the CNS in order to understand the advantages and disadvantages of the Convention, and finally to suggest some possible improvements. The analysis in this paper shows that the incentive approach of the CNS has succeeded in facilitating the active roles of its Contracting Parties in making the National Reports and participating in the peer review of these reports. However, the incoherent quality of the National Reports, the different level of participation in the peer review process by different Contracting Parties, and the lack of transparency of the peer review have undermined the effectiveness of the Convention in strengthening the international safety regime as well as preventing serious regulatory errors that had happened in Japan before the Fukushima accident. Therefore, the peer review process should be reformed into a more transparent and independent direction, while an advisory group of regulators within the CNS might also be useful in improving the effectiveness of the Convention as already proven by the good practice in the European Union. Only with such effective change, the CNS can maintain its pivotal role in the international safety regime

Report of the Fukushima nuclear accident by the National Academy of Science. Lessons learned from the Fukushima nuclear accident for improving safety of U.S. nuclear plants

International Nuclear Information System (INIS)

Nariai, Hideki

2014-01-01

U.S. National Academy of Science investigated the accident at the Fukushima Daiichi nuclear plant initiated by the Great East Japan Earthquake for two years and published a draft report in July 24, 2014. Investigation results were summarized in nine new findings and made ten recommendations in a wide horizon; (1) hardware countermeasures against severe accidents and training of operators, (2) upgrade of risk assessment capability for beyond design basis accident, (3) incorporation of new information about hazards in safety regulations, (4) needed improvement of off-site emergency preparedness, and (5) improvements of nuclear safety culture. New information about hazards related with tsunami assessment, new risk assessment for beyond design basis accident, advice of foreigner resident evacuations, regulatory capture, and safety culture and regulator's specialty were discussed as Japanese issues. (T. Tanaka)

Nuclear power plant safety and reliability improvements derived from operational experience analysis

International Nuclear Information System (INIS)

Zebroski, E.L.; Rosen, S.L.

1983-01-01

The frequency and distribution of significant events at operating nuclear power plants can be used as one of several indices to obtain a preliminary indication of unit and/or utility performance in the development and implementation of improvements aimed at reducing the probability or consequences of troublesome events. Initial data of this type are presented along with qualifications on the validity of such indicators. Planned further steps to improve this as a performance indicator are noted

The state of improvement of security management setup in the Japan Atomic Power Company and improvement of facilities in its Tsuruga Nuclear Power Station

International Nuclear Information System (INIS)

1982-01-01

In connection with the series of accidents in the Tsuruga Nuclear Power Station of the Japan Atomic Power Company, the state of security management in JAPC and the safety of facilities in the Tsuruga Nuclear Power Station, which have resulted from improvement efforts, are described on the following items: security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (Mori, K.)

Means of evaluating and improving the effectiveness of training of nuclear power plant personnel

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

In 1996 the IAEA published a guidebook on Nuclear Power Plant Personnel Training and its Evaluation, which constitutes the recommendations of the IAEA with respect to development, implementation and evaluation of training programmes. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared to provide further details concerning the effectiveness of NPP personnel training. As the nuclear power industry continues to be challenged by increasing safety requirements, a high level of competition and decreasing budgets, it becomes more important than ever to have some methodology of ensuring that training contributes a value to the organization. The actual determination of training effectiveness is not an easy task because of the many variables associated with personnel performance. For example, for training to make a difference in job performance, line management should be involved prior to training delivery to identify what performance is desired, but not being achieved. Then, training is developed to meet desired performance, which is followed by practice and continued management reinforcement. Because of these other variables, it is very difficult to prove that training had a sole contribution to performance improvement, but rather one of many contributors needed for performance improvement. The difficulty to isolate training as a sole contributor has been documented in a number of research studies over the recent years. Due to these limitations, a base assumption must be made in order to use any methodology for training effectiveness evaluation. That assumption is that there are some basic principles for developing training and if training programmes are developed and maintained using these principles, then the training provided should be an effective tool to improve the line organization performance. By monitoring various types of training effectiveness indications

Means of evaluating and improving the effectiveness of training of nuclear power plant personnel

International Nuclear Information System (INIS)

2003-07-01

In 1996 the IAEA published a guidebook on Nuclear Power Plant Personnel Training and its Evaluation, which constitutes the recommendations of the IAEA with respect to development, implementation and evaluation of training programmes. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared to provide further details concerning the effectiveness of NPP personnel training. As the nuclear power industry continues to be challenged by increasing safety requirements, a high level of competition and decreasing budgets, it becomes more important than ever to have some methodology of ensuring that training contributes a value to the organization. The actual determination of training effectiveness is not an easy task because of the many variables associated with personnel performance. For example, for training to make a difference in job performance, line management should be involved prior to training delivery to identify what performance is desired, but not being achieved. Then, training is developed to meet desired performance, which is followed by practice and continued management reinforcement. Because of these other variables, it is very difficult to prove that training had a sole contribution to performance improvement, but rather one of many contributors needed for performance improvement. The difficulty to isolate training as a sole contributor has been documented in a number of research studies over the recent years. Due to these limitations, a base assumption must be made in order to use any methodology for training effectiveness evaluation. That assumption is that there are some basic principles for developing training and if training programmes are developed and maintained using these principles, then the training provided should be an effective tool to improve the line organization performance. By monitoring various types of training effectiveness indications

Improvement of Sodium Neutronic Nuclear Data for the Computation of Generation IV Reactors

International Nuclear Information System (INIS)

Archier, P.

2011-01-01

The safety criteria to be met for Generation IV sodium fast reactors (SFR) require reduced and mastered uncertainties on neutronic quantities of interest. Part of these uncertainties come from nuclear data and, in the particular case of SFR, from sodium nuclear data, which show significant differences between available international libraries (JEFF-3.1.1, ENDF/B-VII.0, JENDL-4.0). The objective of this work is to improve the knowledge on sodium nuclear data for a better calculation of SFR neutronic parameters and reliable associated uncertainties. After an overview of existing 23 Na data, the impact of the differences is quantified, particularly on sodium void reactivity effects, with both deterministic and stochastic neutronic codes. Results show that it is necessary to completely re-evaluate sodium nuclear data. Several developments have been made in the evaluation code Conrad, to integrate new nuclear reactions models and their associated parameters and to perform adjustments with integral measurements. Following these developments, the analysis of differential data and the experimental uncertainties propagation have been performed with Conrad. The resolved resonances range has been extended up to 2 MeV and the continuum range begins directly beyond this energy. A new 23 Na evaluation and the associated multigroup covariances matrices were generated for future uncertainties calculations. The last part of this work focuses on the sodium void integral data feedback, using methods of integral data assimilation to reduce the uncertainties on sodium cross sections. This work ends with uncertainty calculations for industrial-like SFR, which show an improved prediction of their neutronic parameters with the new evaluation. (author) [fr

Improved nuclear emergency management system reflecting lessons learned from the emergency response at Fukushima Daini Nuclear Power Station after the Great East Japan Earthquake

International Nuclear Information System (INIS)

Kawamura, Shinichi; Narabayashi, Tadashi

2016-01-01

Three nuclear reactors at Fukushima Daini Nuclear Power Station lost all their ultimate heat sinks owing to damage from the tsunami caused by the Great East Japan Earthquake on March 11, 2011. Water was injected into the reactors by alternate measures, damaged cooling systems were restored with promptly supplied substitute materials, and all the reactors were brought to a cold shutdown state within four days. Lessons learned from this experience were identified to improve emergency management, especially in the areas of strategic response planning, logistics, and functions supporting response activities continuing over a long period. It was found that continuous planning activities reflecting information from plant parameters and response action results were important, and that relevant functions in emergency response organizations should be integrated. Logistics were handled successfully but many difficulties were experienced. Therefore, their functions should be clearly established and improved by emergency response organizations. Supporting emergency responders in the aspects of their physical and mental conditions was important for sustaining continuous response. As a platform for improvement, the concept of the Incident Command System was applied for the first time to a nuclear emergency management system, with specific improvement ideas such as a phased approach in response planning and common operation pictures. (author)

Improving nuclear power plant safety through operator aids

International Nuclear Information System (INIS)

1987-12-01

In October 1986, the IAEA convened a one-week Technical Committee Meeting on Improving Nuclear Power Plant Safety Through Operator Aids. The term ''operator aid'' or more formally ''operator support system'' refers to a class of devices designed to be added to a nuclear power plant control station to assist an operator in performing his job and thereby decrease the probability of operator error. The addition of a carefully planned and designed operator aid should result in an increase in nuclear power plant safety and reliability. Operator aids encompass a wide range of devices from the very simple, such as color coding a display to distinguish it out of a group of similar displays, to the very complex, such as a computer-generated video display which concentrates a number of scattered indicator readings located around a control room into a concise display in front of the operator. This report provides guidelines and information to help make a decision as to whether an operator aid is needed, what kinds of operator aids are available and whether it should be purchased or developed by the utility. In addition, a discussion is presented on advanced operator aids to provide information on what may become available in the future. The broad scope of these guidelines makes it most suitable for use by a multi-disciplinary team. The document consists of two parts. The recommendations and results of the meeting discussions are given in the first part. The second part is the annex where the papers presented at the Technical Committee Meeting are printed. A separate abstract was prepared for each of the 10 papers. Refs, figs and tabs

Improvements in and relating to drums for storing fuel assemblies of nuclear reactors

International Nuclear Information System (INIS)

Artemiev, L.N.; Batjukov, V.I.; Fadeev, A.I.

1977-01-01

A specification is given for an improved design of drums used for storing nuclear reactor fuel assemblies. It is claimed that this new design reduces wear, increases reliability and enables the recharging operation to be speeded up. (UK)

Research needs and improvement of standards for nuclear power plant design

International Nuclear Information System (INIS)

Chen, C.; Moreadith, F.L.

1978-01-01

The need for research and improvement of code requirements, for both economy and safety reasons is discussed for the following topics relevant to nuclear power plant structural analysis: Earthquake definition; dynamic behavior of reinforced concrete structures under impact loads; design for postulated pipe rupture; code requirements for loading combinations for concrete structures, reinforcing steel splicing, reinforced concrete structural design for thermal effects. (Auth.)

New constraints on slip rates and locking depths of the San Andreas Fault System from Sentinel-1A InSAR and GAGE GPS observations

Science.gov (United States)

Ward, L. A.; Smith-Konter, B. R.; Higa, J. T.; Xu, X.; Tong, X.; Sandwell, D. T.

2017-12-01

After over a decade of operation, the EarthScope (GAGE) Facility has now accumulated a wealth of GPS and InSAR data, that when successfully integrated, make it possible to image the entire San Andreas Fault System (SAFS) with unprecedented spatial coverage and resolution. Resulting surface velocity and deformation time series products provide critical boundary conditions needed for improving our understanding of how faults are loaded across a broad range of temporal and spatial scales. Moreover, our understanding of how earthquake cycle deformation is influenced by fault zone strength and crust/mantle rheology is still developing. To further study these processes, we construct a new 4D earthquake cycle model of the SAFS representing the time-dependent 3D velocity field associated with interseismic strain accumulation, co-seismic slip, and postseismic viscoelastic relaxation. This high-resolution California statewide model, spanning the Cerro Prieto fault to the south to the Maacama fault to the north, is constructed on a 500 m spaced grid and comprises variable slip and locking depths along 42 major fault segments. Secular deep slip is prescribed from the base of the locked zone to the base of the elastic plate while episodic shallow slip is prescribed from the historical earthquake record and geologic recurrence intervals. Locking depths and slip rates for all 42 fault segments are constrained by the newest GAGE Facility geodetic observations; 3169 horizontal GPS velocity measurements, combined with over 53,000 line-of-sight (LOS) InSAR velocity observations from Sentinel-1A, are used in a weighted least-squares inversion. To assess slip rate and locking depth sensitivity of a heterogeneous rheology model, we also implement variations in crustal rigidity throughout the plate boundary, assuming a coarse representation of shear modulus variability ranging from 20-40 GPa throughout the (low rigidity) Salton Trough and Basin and Range and the (high rigidity) Central

Direct measurements of wall shear stress by buried wire gages in a shock-wave boundary-layer interaction region

Science.gov (United States)

Murthy, V. S.; Rose, W. C.

1977-01-01

Detailed measurements of wall shear stress (skin friction) were made with specially developed buried wire gages in the interaction regions of a Mach 2.9 turbulent boundary layer with externally generated shocks. Separation and reattachment points inferred by these measurements support the findings of earlier experiments which used a surface oil flow technique and pitot profile measurements. The measurements further indicate that the boundary layer tends to attain significantly higher skin-friction values downstream of the interaction region as compared to upstream. Comparisons between measured wall shear stress and published results of some theoretical calculation schemes show that the general, but not detailed, behavior is predicted well by such schemes.

Nuclear agriculture and biotechnology: integrated approaches for crop improvement

International Nuclear Information System (INIS)

Suprasanna, P.; Venugopalan, V.

2017-01-01

Use of radiation and radioisotopes in agriculture is one of the most important fields of peaceful applications of atomic energy for societal benefit. They are used to induce genetic variability in crop plants to develop improved mutant varieties, to manage insect pests, to monitor fate and persistence of pesticides, to study fertilizer use efficiency and plant micronutrient uptake and also to preserve agricultural produce. So far, BARC has developed and released 42 Trombay mutant varieties in oilseeds (groundnut, mustard, soybean, sunflower), pulses (pigeonpea, blackgram, greengram, cowpea), rice and jute for commercial cultivation across the nation. Mutant characterization has been benefitted by genomics approaches and availability of crop genome sequencing. In this regard, studies are underway to utilize mutant germplasm for molecular characterization and understanding trait modification. The nuclear technologies have benefited the farmers, traders and end-users and will continue to play a significant role in addressing food and nutritional security. In this presentation, an overview will be given on the activities of the NABTD in the field of nuclear agriculture and biotechnology

Risk management: A tool for improving nuclear power plant performance

International Nuclear Information System (INIS)

2001-04-01

This technical document on risk management as a tool for improving nuclear power plant (NPP) operations is part of an ongoing project on management of NPP operations in a competitive environment. The overall objective of this project is to assist the management of operating organizations and NPPs in identifying and implementing appropriate measures to remain competitive in a rapidly changing business environment. Other reports developed through this project have identified overall strategies and techniques that NPP operating organization managers can use to succeed in more competitive energy markets. For example, in IAEA-TECDOC-1123, Strategies for Competitive Nuclear Power Plants, one of the most important strategies identified was integrated risk management. This publication provides a recommended structure for risk management along with examples of how NPP operating organizations are using this tool to help them integrate safety, operational and economic related risks in a changing business environment

Improving the rationality of nuclear safety regulations

International Nuclear Information System (INIS)

Choi, Byung Sun; Choi, Y. G.; Mun, G. H.

2005-03-01

This study focuses on human nature and institutions around the risk management in Korean Nuclear Installations. Nuclear safety regulatory system in Korea has had a tendency to overvalue the technical or engineering areas. But just like other risk management system, the knowledge of social science is also required to design more valid safety regulatory system. As a result of analysis, this study suggest that performance regulation need to be introduced to current nuclear safety regulation system. In this advanced regulatory system, each nuclear generation unit have to be evaluated by performance of its own regulatory implementation and would be treated differently by the performance. Additionally, self-regulation could be very effective was to guarantee nuclear safety. Because KHNP could be judged to have an considerable capabilities to manage its own regulatory procedures. To make self-regulatory system established successfully, it is also important to arrange the appropriate incentive and compensate structures

The awareness of employees in safety culture through the improved nuclear safety culture evaluation method

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Ga; Sung, Chan Ho; Jung, Yeon Sub [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2012-10-15

After the Chernobyl nuclear accident in 1986, nuclear safety culture terminology was at first introduced emphasizing the importance of employees' attitude and organizational safety. The concept of safety culture was spread by INSAG 4 published in 1991. From that time, IAEA had provided the service of ASCOT for the safety culture assessment. However, many people still are thinking that safety culture is abstract and is not clear. It is why the systematic and reliable assessment methodology was not developed. Assessing safety culture is to identify what is the basic assumption for any organization to accept unconsciously. Therefore, it is very difficult to reach a meaningful conclusion by a superficial investigation alone. KHNP had been doing the safety culture assessment which was based on ASCOT methodology every 2 years. And this result had contributed to improving safety culture. But this result could not represent the level of organization's safety culture due to the limitation of method. So, KHNP has improved the safety culture method by benchmarking the over sea assessment techniques in 2011. The effectiveness of this improved methodology was validated through a pilot assessment. In this paper, the level of employees' safety culture awareness was analyzed by the improved method and reviewed what is necessary for the completeness and objectivity of the nuclear safety culture assessment methodology.

The awareness of employees in safety culture through the improved nuclear safety culture evaluation method

International Nuclear Information System (INIS)

Kim, Young Ga; Sung, Chan Ho; Jung, Yeon Sub

2012-01-01

After the Chernobyl nuclear accident in 1986, nuclear safety culture terminology was at first introduced emphasizing the importance of employees' attitude and organizational safety. The concept of safety culture was spread by INSAG 4 published in 1991. From that time, IAEA had provided the service of ASCOT for the safety culture assessment. However, many people still are thinking that safety culture is abstract and is not clear. It is why the systematic and reliable assessment methodology was not developed. Assessing safety culture is to identify what is the basic assumption for any organization to accept unconsciously. Therefore, it is very difficult to reach a meaningful conclusion by a superficial investigation alone. KHNP had been doing the safety culture assessment which was based on ASCOT methodology every 2 years. And this result had contributed to improving safety culture. But this result could not represent the level of organization's safety culture due to the limitation of method. So, KHNP has improved the safety culture method by benchmarking the over sea assessment techniques in 2011. The effectiveness of this improved methodology was validated through a pilot assessment. In this paper, the level of employees' safety culture awareness was analyzed by the improved method and reviewed what is necessary for the completeness and objectivity of the nuclear safety culture assessment methodology

Improving nuclear safety at international research reactors: The Integrated Research Reactor Safety Enhancement Program (IRRSEP)

International Nuclear Information System (INIS)

Huizenga, David; Newton, Douglas; Connery, Joyce

2002-01-01

Nuclear energy continues to play a major role in the world's energy economy. Research and test reactors are an important component of a nation's nuclear power infrastructure as they provide training, experiments and operating experience vital to developing and sustaining the industry. Indeed, nations with aspirations for nuclear power development usually begin their programs with a research reactor program. Research reactors also are vital to international science and technology development. It is important to keep them safe from both accident and sabotage, not only because of our obligation to prevent human and environmental consequence but also to prevent corresponding damage to science and industry. For example, an incident at a research reactor could cause a political and public backlash that would do irreparable harm to national nuclear programs. Following the accidents at Three Mile Island and Chernobyl, considerable efforts and resources were committed to improving the safety posture of the world's nuclear power plants. Unsafe operation of research reactors will have an amplifying effect throughout a country or region's entire nuclear programs due to political, economic and nuclear infrastructure consequences. (author)

The improvement of the fire protections system for nuclear cycle facilities. Formulation of a fire protection guideline for nuclear fuel cycle facilities

International Nuclear Information System (INIS)

2012-04-01

The private side Fire Protection Guideline was investigated with respect to the fire having taken place at the nuclear reactor site followed by the Chuetsu-Oki earthquake in Niigata Prefecture in 2007. To improve the fire protection system especially applicable to MOX fuel fabrication facilities, JNES (Japan Nuclear Energy Safety Organization) investigated private guidelines adopted in Japanese Light Water cooled Reactors, the standardized guidelines used in Nuclear Facilities in other countries including USA, and the standards in the chemical plants. The content of the guideline concerns the prevention of the fire breakout, the prevention of fire extension, the reduction of the fire effects, as well as the facility-characteristic protection countermeasures and the fire effect evaluations. (S. Ohno)

Study on the improvement of nuclear fuel cladding reliability

International Nuclear Information System (INIS)

Rheem, Karp Soon; Han, Jung Ho; Jeong, Yong Hwan; Lee, Deok Hyun

1987-12-01

In order to improve the nuclear fuel cladding reliability for high burn-up fuels, the corrosion resistance of laser beam surface treated and β-quenched zircaloys and the mechanical characteristics including fatigue, burst, and out-of-pile PCMI characteristics of heat treated zircaloys were investigated. In addition, the inadiation characteristics of Ko-Ri reactor fuel claddings was examined. It was found that the wasteside corrosion resistance of commercial zircaloys was improved remarkably by laser beam surface treatment. The out-of-pile transient cladding failures were investigated in terms of hoop stress versus time-to-failures by means of mandrel loading units at 25 deg C and 325 deg C. Fatigue characteristics of the β-quenched and as-received zircaloy cladding were investigated by using an internal oil pressurization method which can simulate the load-following operation cycle. The results were in good agreement with the existing data obtained by conventional methods for commercial zircaloys. Burst tests were performed with commercial and the β-quenched zircaloys in high pressure argon gas atmosphere as a function of burst temperature. The burst stress decreased linearly in the α phase region up to 600 deg C and hereafter the decrement of the burst stress decreased gradually with temperature in the β-phase region. For the first time, the burst characteristic of the irradiated zircaloy-4 cladding tubes released from Ko-Ri nuclear power unit 1 was investigated, and attempts were made to trace the cause of cladding failures by examining the failed structure and fret marks by debris. (Author)

Improved Monte Carlo Glauber predictions at present and future nuclear colliders

Science.gov (United States)

Loizides, Constantin; Kamin, Jason; d'Enterria, David

2018-05-01

We present the results of an improved Monte Carlo Glauber (MCG) model of relevance for collisions involving nuclei at center-of-mass energies of the BNL Relativistic Heavy Ion Collider (√{sNN}=0.2 TeV), CERN Large Hadron Collider (LHC) (√{sNN}=2.76 -8.8 TeV ), and proposed future hadron colliders (√{sNN}≈10 -63 TeV). The inelastic p p cross sections as a function of √{sNN} are obtained from a precise data-driven parametrization that exploits the many available measurements at LHC collision energies. We describe the nuclear density of a lead nucleus with two separated two-parameter Fermi distributions for protons and neutrons to account for their different densities close to the nuclear periphery. Furthermore, we model the nucleon degrees of freedom inside the nucleus through a lattice with a minimum nodal separation, combined with a "recentering and reweighting" procedure, that overcomes some limitations of previous MCG approaches. The nuclear overlap function, number of participant nucleons and binary nucleon-nucleon collisions, participant eccentricity and triangularity, overlap area, and average path length are presented in intervals of percentile centrality for lead-lead (PbPb) and proton-lead (p Pb ) collisions at all collision energies. We demonstrate for collisions at √{sNN}=5.02 TeV that the central values of the Glauber quantities change by up to 7% in a few bins of reaction centrality, due to the improvements implemented, though typically they remain within the previously assigned systematic uncertainties, while their new associated uncertainties are generally smaller (mostly below 5%) at all centralities than for earlier calculations. Tables for all quantities versus centrality at present and foreseen collision energies involving Pb nuclei, as well as for collisions of XeXe at √{sNN}=5.44 TeV , and AuAu and CuCu at √{sNN}=0.2 TeV , are provided. The source code for the improved Monte Carlo Glauber model is made publicly available.

Improved algorithm based on equivalent enthalpy drop method of pressurized water reactor nuclear steam turbine

International Nuclear Information System (INIS)

Wang Hu; Qi Guangcai; Li Shaohua; Li Changjian

2011-01-01

Because it is difficulty to accurately determine the extraction steam turbine enthalpy and the exhaust enthalpy, the calculated result from the conventional equivalent enthalpy drop method of PWR nuclear steam turbine is not accurate. This paper presents the improved algorithm on the equivalent enthalpy drop method of PWR nuclear steam turbine to solve this problem and takes the secondary circuit thermal system calculation of 1000 MW PWR as an example. The results show that, comparing with the design value, the error of actual thermal efficiency of the steam turbine cycle obtained by the improved algorithm is within the allowable range. Since the improved method is based on the isentropic expansion process, the extraction steam turbine enthalpy and the exhaust enthalpy can be determined accurately, which is more reasonable and accurate compared to the traditional equivalent enthalpy drop method. (authors)

Strategy for improving instrumentation and control in operating nuclear power plants

International Nuclear Information System (INIS)

Abad Bassols, L.; Nino Perote, R.

1996-01-01

There are three basic reasons why nuclear power plants need to systematically upgrade their instrumentation and control equipment: Obsolete instrumentation and lack spares Little capacity of flexibility for extension Possibility of attaining better systems integration and improving systems-operations interface This article shows how to approach these issues using the following strategies: Use of distributed control systems and PLCs for control, signalling, command, communications, etc, in both nuclear and conventional applications Upgrading of process instrumentation equipment, sensors, transmitters, etc Upgrading of alarm-signalling systems In each group of equipment items consideration should be given to: Aspects regarding manufacturers-suppliers Effects on design, adaptation and documentation of operating plants Effects on the training and handling skills of operation and maintenance staff Strategy for incorporating the new system into the Plant with minimum impact on operation (Author)

Improvement of fire protection measures for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Improvements of fire protection measures for nuclear power plants were performed as following items: Development of fire hazard analysis method. Application of developed Fire Dynamic Tool to actual plants (FDT{sup S}), With regard to fire tests for the fire data acquisition, cable fire test and High Energy Arcing Faults (HEAF) fire test were performed. Implementation of fire hazard analysis code and simulation were performed as following items: Fire analysis codes FDS, SYLVIA, and CFAST were implemented in order to analyze the fire progression phenomena. Trial simulation of HEAF accident of Onagawa NPP in Tohoku earthquake. (author)

Improvement of fire protection measures for nuclear power plants

International Nuclear Information System (INIS)

2012-01-01

Improvements of fire protection measures for nuclear power plants were performed as following items: Development of fire hazard analysis method. Application of developed Fire Dynamic tool to actual plants, With regard to fire tests for the fire data acquisition, cable fire test and oil fire test were performed. Implementation of fire hazard analysis code and simulation were performed as following items: Fire analysis codes FDS, SYLVIA, CFAST were implemented in order to analyze the fire progression phenomena, Trial simulation of fire hazard as Metal-Clad Switch Gear Fire of ONAGAWA NPP in Tohoku earthquake (HEAF accident). (author)

Role of recent research in improving check valve reliability at nuclear power plants

International Nuclear Information System (INIS)

Kalsi, M.S.; Horst, C.L.; Wang, J.K.; Sharma, V.

1990-01-01

Check valve failures at nuclear power plants in recent years have led to serious safety concerns, and caused extensive damage to other plant components which had a significant impact on plant availability. In order to understand the failure mechanism and improve the reliability of check valves, a systematic research effort was proposed by Kalsi Engineering, Inc. to U.S. Nuclear Regulatory Commission (NRC). The overall goal of the research was to develop models for predicting the performance and degradation of swing check valves in nuclear power plant systems so that appropriate preventive maintenance or design modifications can be performed to improve the reliability of check valves. Under Phase I of this research, a large matrix of tests was run with instrumented swing check valves to determine the stability of the disc under a variety of upstream flow disturbances, covering a wide range of disc stop positions and flow velocities in two different valve sizes. The goals of Phase II research were to develop predictive models which quantify the anticipated degradation of swing check valves that have flow disturbances closely upstream of the valve and are operating under flow velocities that do not result in full disc opening. This research allows the inspection/maintenance activities to be focussed on those check valves that are more likely to suffer premature degradation. The quantitative wear and fatigue prediction methodology can be used to develop a sound preventive maintenance program. The results of the research also show the improvements in check valve performance/reliability that can be achieved by certain modifications in the valve design

Basic information to improve public acceptance to nuclear energy in Brazil; Subsidios para a melhoria da aceitacao da energia nuclear no Brasil

Energy Technology Data Exchange (ETDEWEB)

Gibelli, Sonia M.O.; Lima e Silva, Pedro Paulo de; Xavier, Ana Maria [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

1997-12-31

In Brazil, the current production of nuclear energy is restricted to Angra I plant, a 657 MW pressurized water reactor, in operation since 1982. Among the eight units predicted in 1975 within the Brazil Germany nuclear agreement, only two have been effectively contracted, namely Angra 2 and 3. The nuclear alternative, likewise all other energy sources, is very much dependable on the assessment of their own benefits compared to the associated risks posed to the population and the environment. The main goal of this article is to provide information to enable the improvement of public acceptance of the use of nuclear energy in the country, by comparing risks associated with different sources as well as pointing out aspects related to risk perception by the public. (author) 18 refs., 5 figs.; e-mail: sonia at cnen.gov.br; lima-e-silva at pobox.com; axavier at cnen.gov.br

Improvements of radioactive waste management at WWER nuclear power plants

International Nuclear Information System (INIS)

2006-04-01

This report is part of a systematic IAEA effort to improve waste management practices at WWER plants and to make them consistent with the current requirements and standards for safe and reliable operation of nuclear power plants. The report reviews the wet and dry solid waste management practices at the various types of WWER nuclear power plants (NPP) and describes approaches and recent achievements in waste minimization. Waste minimization practices in use at western PWRs are reviewed and compared, and their applicability at WWER plants is evaluated. Radioactive waste volume reduction issues and waste management practices are reflected in many IAEA publications. However, aspects of waste minimization specific to individual WWER nuclear power plant designs and WWER waste management policies are not addressed extensively in those publications. This report covers the important aspects applicable to the improvement of waste management at WWER NPP, including both plant-level and country-level considerations. It is recognized that most WWER plants are already implementing many of these concepts and recommendations with varying degrees of success; others will benefit from the included considerations. The major issues addressed are: - Review of current waste management policies and practices related to WWERs and western PWRs, including the influence of the original design concepts and significant modifications, liquid waste discharge limits and dry solid waste clearance levels applied in individual countries, national policies and laws, and other relevant aspects affecting the nature and quantities of waste arisings; - Identification of strategies and methods for improving the radioactive waste management generated in normal operation and maintenance at WWERs. This report is a composite (combination) of the two separate initiatives mentioned above. The first draft report was prepared at the meeting 26-30 May 1997 by five consultants. The draft was improved during an

Towards the improvement of spin-isospin properties in nuclear energy density functionals

International Nuclear Information System (INIS)

Roca-Maza, X.; Colò, G.; Liang, H. Z.; Sagawa, H.; Meng, J.; Ring, P.; Zhao, P. W.

2016-01-01

We address the problem of improving existing nuclear Energy Density Functionals (EDFs) in the spin-isospin channel. For that, we propose two different ways. The first one is to carefully take into account in the fitting protocol some of the key ground state properties for an accurate description of the most studied spin-isospin resonances: the Gamow-Teller Resonance (GTR) [1]. The second consists in providing a strategy to build local covariant EDF keeping the main features from their non-local counterparts [2]. The RHF model based on a Lagrangian where heavy mesons carry the nuclear effective interaction have been shown to be successful in the description of spin-isospin resonances [3]. (paper)

Improved Technology To Prevent Nuclear Proliferation And Counter Nuclear Terrorism

Energy Technology Data Exchange (ETDEWEB)

Richardson, J; Yuldashev, B; Labov, S; Knapp, R

2006-06-12

As the world moves into the 21st century, the possibility of greater reliance on nuclear energy will impose additional technical requirements to prevent proliferation. In addition to proliferation resistant reactors, a careful examination of the various possible fuel cycles from cradle to grave will provide additional technical and nonproliferation challenges in the areas of conversion, enrichment, transportation, recycling and waste disposal. Radiation detection technology and information management have a prominent role in any future global regime for nonproliferation. As nuclear energy and hence nuclear materials become an increasingly global phenomenon, using local technologies and capabilities facilitate incorporation of enhanced monitoring and detection on the regional level. Radiation detection technologies are an important tool in the prevention of proliferation and countering radiological/nuclear terrorism. A variety of new developments have enabled enhanced performance in terms of energy resolution, spatial resolution, passive detection, predictive modeling and simulation, active interrogation, and ease of operation and deployment in the field. For example, various gamma ray imaging approaches are being explored to combine spatial resolution with background suppression in order to enhance sensitivity many-fold at reasonable standoff distances and acquisition times. New materials and approaches are being developed in order to provide adequate energy resolution in field use without the necessity for liquid nitrogen. Different detection algorithms enable fissile materials to be distinguished from other radioisotopes.

Improvement of nuclear third party liability system

International Nuclear Information System (INIS)

Kim, S. W.; Oh, B. J.; Yoo, S. O.; Kang, S. C.; Lee, J. I.

2001-01-01

A special regime for nuclear third party liability is necessary since the ordinary common law is not well suited to deal with the particular problems in the field of nuclear industry. The basic principles of this regime is i) strict liability (other than traditional fault liability), ii) channelling and the exclusive liability of operator, iii) compulsory financial security, iv) limits on liability in amount and in time v) intervention by the state, etc. In Korea, a revision was made to the Nuclear Damage Compensation Act on 16th January, 2001. The revision aimed at the reflection of the spirit of the new Vienna Convention on Nuclear Liability (1997) such as i) limit of liability to an amount of 300mil SDR, ii) increase of the level of financial protection (in the presidential decree, the 'Phasing-In' system would be introduced), iii) Extension of the definition 'nuclear damage', iv) extension of the scope of application to EEZ, v) deletion of 'natural calamity' from the causes of immunity, vi) extension of prescription period for personal injury to a length of 30 year

TSO assistance towards the improvement of nuclear safety in Lithuania: achievements and perspectives

International Nuclear Information System (INIS)

Butcher, P.; Bystedt, P.; Chouha; Weber, J.P.; Zilys, K.

2001-01-01

This paper explores the improvements that have taken place at INPP (Ignalina nuclear power plant) in both the engineering and operational aspects of nuclear safety, discussing as example some areas where there has been a large involvement of international experts. The development of the Lithuanian Nuclear Regulatory Authority VATESI, and also the technical support organisations for both the regulator and the NPP are discussed. In each of these sections the paper describes some of the successes and also the areas where there have been some problems. Many of the problems have been resolved but challenges remain for the future. The paper only deals with the assistance towards enhancing the safety of the NPP up to the time of its closure. Regulation of decommissioning is an important area for the future and is receiving urgent attention and active planning at the present time. (authors)

Strain Gage Load Calibration of the Wing Interface Fittings for the Adaptive Compliant Trailing Edge Flap Flight Test

Science.gov (United States)

Miller, Eric J.; Holguin, Andrew C.; Cruz, Josue; Lokos, William A.

2014-01-01

This is the presentation to follow conference paper of the same name. The adaptive compliant trailing edge (ACTE) flap experiment safety of flight requires that the flap to wing interface loads be sensed and monitored in real time to ensure that the wing structural load limits are not exceeded. This paper discusses the strain gage load calibration testing and load equation derivation methodology for the ACTE interface fittings. Both the left and right wing flap interfaces will be monitored and each contains four uniquely designed and instrumented flap interface fittings. The interface hardware design and instrumentation layout are discussed. Twenty one applied test load cases were developed using the predicted in-flight loads for the ACTE experiment.

Kozloduy nuclear power plant. Units 1-4. Status of safety improvements. Rev. 2

International Nuclear Information System (INIS)

1999-01-01

This paper presents the results of the safety improvements activities carried out by the Kozloduy Nuclear Power Plant (KNPP) within the period 1990-1998. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of russian design developed according to the safety standards in force in USSR in late sixties. Up to now 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short term program was implemented between from 1991 to 1997 owing to strong safety commitment of NEC and KNPP staff as well as broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. In parallel a special assessment process started in 1995 in order to evaluate the level of safety, achieved by Short Term Program, according to current safety standards and to define the measures, which should be implemented by the Utility to complete the process of improving the safety in future

Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, December 2015

International Nuclear Information System (INIS)

Cabellos, Oscar; De Saint Jean, Cyrille; Hursin, Mathieu; Pelloni, Sandro; Ivanov, Evgeny; Kodeli, Ivan; Leconte, Pierre; Palmiotti, Giuseppe; Salvatores, Massimo; Sobes, Vladimir; Yokoyama, Kenji

2015-12-01

The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the fifth formal Subgroup 39 meeting held at the Institute Curie, Paris, France, on 4 December 2015. It comprises a Summary Record of the meeting, and all the available presentations (slides) given by the participants: A - Sensitivity methods: - 1: Short update on deliverables (K. Yokoyama); - 2: Does one shot Bayesian is equivalent to successive update? Bayesian inference: some matrix linear algebra (C. De Saint Jean); - 3: Progress in Methodology (G. Palmiotti); - SG39-3: Use of PIA approach. Possible application to neutron propagation experiments (S. Pelloni); - 4: Update on sensitivity coefficient methods (E. Ivanov); - 5: Stress test for U-235 fission (H. Wu); - 6: Methods and approaches development at ORNL for providing feedback from integral benchmark experiments for improvement of nuclear data files (V. Sobes); B - Integral experiments: - 7a: Update on SEG analysis (G. Palmiotti); - 7b:Status of MANTRA (G. Palmiotti); - 7c: Possible new experiments at NRAD (G. Palmiotti); - 8: B-eff experiments (I. Kodeli); - 9: On going CEA activities related to dedicated integral experiments for nuclear date validation in the Fast energy range (P. Leconte); - 10: PROTEUS Experiments: an update (M. Hursin); - 11: Short updates on neutron propagation experiments, STEK, CIELO status (O. Cabellos)

Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, May 2015

International Nuclear Information System (INIS)

Wang, Wenming; Yokoyama, Kenji; Kim, Do Heon; Kodeli, Ivan-Alexander; Hursin, Mathieu; Pelloni, Sandro; Palmiotti, Giuseppe; Salvatores, Massimo; Touran, Nicholas; Cabellos De Francisco, Oscar; )

2015-05-01

The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the fourth Subgroup meeting, held at the NEA, Issy-les-Moulineaux, France, on 19-20 May 2015. It comprises a Summary Record of the meeting, two papers on deliverables and all the available presentations (slides) given by the participants: 1 - Status of Deliverables: '1. Methodology' (K. Yokoyama); 2 - Status of Deliverables: '2. Comments on covariance data' (K. Yokoyama); 3 - PROTEUS HCLWR Experiments (M. Hursin); 4 - Preliminary UQ Efforts for TWR Design (N. Touran); 5 - Potential use of beta-eff and other benchmark for adjustment (I. Kodeli); 6 - k_e_f_f uncertainties for a simple case of Am"2"4"1 using different codes and evaluated files (I. Kodeli); 7 - k_e_f_f uncertainties for a simple case of Am"2"4"1 using TSUNAMI (O. Cabellos); 8 - REWIND: Ranking Experiments by Weighting to Improve Nuclear Data (G. Palmiotti); 9 - Recent analysis on NUDUNA/MOCABA applications to reactor physics parameters (E. Castro); 10 - INL exploratory study for SEG (A. Hummel); 11 - The Development of Nuclear Data Adjustment Code at CNDC (H. Wu); 12 - SG39 Perspectives (M. Salvatores). A list of issues and actions conclude the document

Improvement of nuclear ship engineering simulation system. Hardware renewal and interface improvement of the integral type reactor

Energy Technology Data Exchange (ETDEWEB)

Takahashi, Hiroki; Kyoya, Masahiko; Shimazaki, Junya [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Kano, Tadashi [KCS, Co., Mito, Ibaraki (Japan); Takahashi, Teruo [Energis, Co., Kobe, Hyogo (Japan)

2001-10-01

JAERI had carried out the design study about a lightweight and compact integral type reactor (an advanced marine reactor) with passive safety equipment as a power source for the future nuclear ships, and completed an engineering design. We have developed the simulator for the integral type reactor to confirm the design and operation performance and to utilize the study of automation of the reactor operation. The simulator can be used also for future research and development of a compact reactor. However, the improvement in a performance of hardware and a human machine interface of software of the simulator were needed for future research and development. Therefore, renewal of hardware and improvement of software have been conducted. The operability of the integral-reactor simulator has been improved. Furthermore, this improvement with the hardware and software on the market brought about better versatility, maintainability, extendibility and transfer of the system. This report mainly focuses on contents of the enhancement in a human machine interface, and describes hardware renewal and the interface improvement of the integral type reactor simulator. (author)

Seismic coupling of nuclear explosions. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Larson, D B [ed.; Defense Advanced Research Projects Agency, Arlington, VA (United States)

1989-12-31

The new Giant Magnet Experimental Facility employing digital recording of explosion induced motion has been constructed and successfully tested. Particle velocity and piezoresistance gage responses can be measured simultaneously thus providing the capability for determining the multi-component stress-strain history in the test material. This capability provides the information necessary for validation of computer models used in simulation of nuclear underground testing, chemical explosion testing, dynamic structural response, earth penetration response, and etc. This report discusses fully coupled and cavity decoupled explosions of the same energy (0.622 kJ) were carried out as experiments to study wave propagation and attenuation in polymethylmethacrylate (PMMA). These experiments produced particle velocity time histories at strains from 2 {times} 10{sup {minus}3} to as low as 5.8 {times} 10{sup {minus}6}. Other experiments in PMMA, reported recently by Stout and Larson{sup 8} provide additional particle velocity data to strains of 10{sup {minus}1}.

New Anion-Exchange Resins for Improved Separations of Nuclear Materials

International Nuclear Information System (INIS)

Bartsch, Richard A.; Barr, Mary E.

2001-01-01

Improved separations of nuclear materials will have a significant impact upon a broad range of DOE activities. DOE-EM Focus Areas and Crosscutting Programs have identified improved methods for the extraction and recovery of radioactive metal ions from process, waste, and environmental waters as critical needs for the coming years. We propose to develop multifunctional anion-exchange resins that facilitate anion uptake by carefully controlling the structure of the anion receptor site. Our new ion-exchange resins interface the field of ion-specific chelating ligands with robust, commercial ion-exchange technology to provide materials which exhibit superior selectivity and kinetics of sorption and desorption. The following Focus Areas and Crosscutting Programs have described needs that would be favorably impacted by the new material: Efficient Separations and Processing - radionuclide removal from aqueous phases; Plutonium - Pu, Am or total alpha removal to meet regulatory requirement s before discharge to the environment; Plumes - U and Tc in groundwater, U, Pu, Am, and Tc in soils; Mixed Waste - radionuclide partitioning; High-Level Tank Waste - actinide and Tc removal from supernatants and/or sludges. The basic scientific issues which need to be addressed are actinide complex speciation along with modeling of metal complex/functional site interactions in order to determine optimal binding-site characteristics. Synthesis of multifunctionalized extractants and ion-exchange materials that implement key features of the optimized binding site, and testing of these materials, will provide feedback to the modeling and design activities. Resin materials which actively facilitate the uptake of actinide complexes from solution should display both improved selectivity and kinetic properties. The long-range implications of this research, however, go far beyond the nuclear complex. This new methodology of ''facilitated uptake'' could revolutionize ion-exchange technology

Application of nuclear techniques in improving agricultural productivity with particular reference to pasture management

International Nuclear Information System (INIS)

Majid Ajorlo; Ramdzani Abdullah

2009-01-01

Nuclear techniques are appropriate tools to settle problems for agriculture or natural resources which cannot be solved using conventional agricultural techniques. In this paper, the research activities carried out and the achievements so far obtained in the agricultural specialties -all by using nuclear techniques- with particular reference to pasture management are discussed. Insect pest control by Sterile Insect Techniques (SIT); soil and water management using neutron moisture probes; determining N-fixation capacity of legumes using N-15 isotope and nuclear methods; soil erosion measurement using of fallout radionuclide such as Cs-137; monitoring the movement of saline water in salt-affected land using isotopes of chlorine; livestock production and health by RIA and ELISA are some of achievements so far obtained in improving agricultural productivity. The ultimate goal of the nuclear technique investigation in agriculture is to use the resources efficiently in obtaining higher plant and livestock yields while increasing the quality and protecting them against insects, diseases and weeds. (Author)

Distinct GAGE and MAGE-A expression during early human development indicate specific roles in lineage differentiation

DEFF Research Database (Denmark)

Gjerstorff, Morten; Harkness, Linda; Kassem, Moustapha

2008-01-01

BACKGROUND: Expression of cancer/testis-associated proteins (CTAs) has traditionally been considered to be restricted to germ cells in normal tissues and to different types of malignancies. We have evaluated the potential role of CTAs in early human development. METHODS: Using immunohistochemistry...... and RT-PCR, we investigated the expression of CTAs in differentiated human embryonic stem cells (hESC) and in late embryos and early fetuses. RESULTS: We found that melanoma antigen A (MAGE-A) family members were expressed during differentiation of hESC to embryoid bodies and in teratomas, and overlapped...... with expression of the neuroectodermal markers beta-tubulin 3, Pax6 and nestin. A widespread expression of MAGE-A was also observed in neurons of the early developing central nervous system and peripheral nerves. G antigen (GAGE) expression was present in the early ectoderm of embryos, including cells...

Spin-off strategies for the improvement of the performance national nuclear R and D project

International Nuclear Information System (INIS)

Lee, T. J.; Kim, H. J.; Jung, H. S.; Yang, M. H.; Choi, Y. M.

1998-01-01

In the light of the strategic utilization of the national R and D projects, this paper is to induce the spin-off strategies to improve the national R and D effectiveness through analyzing the spin-off characteristics of nuclear technologies, the spin-off status of the advanced countries and the case study of Korean nuclear spin-offs. Spin-off process is viewed as a three-stage operation, such as preparation stage, implementation stage and maintenance stage. In order to find the correlation between the influencing factors and spin-off effectiveness, the Spearman's correlation coefficient was employed as a specific statistical technique. By integrating this correlation, spin-off process and spin-off strategies, this paper presents an efficient frame work to improve the spin-off effectiveness

Can the acceptance of nuclear reactors be raised by a simpler, more transparent safety concept employing improved containments?

International Nuclear Information System (INIS)

Krieg, R.

1993-01-01

Sociological and psychological findings are presented which describe problems society faces with risky technologies. It turns out that for a small but influential group of the society not only the risk, but also the transparency of the technology and the engineered safeguards are important. For this group an improvement of the transparency should raise the acceptance of the technology. However, for the majority of the public, broad discussions about a different more transparent safety concept could generate a feeling of insecurity, especially concerning existing nuclear power plants. In order to improve the transparency in engineered safeguards of nuclear reactors, four basic principles are introduced. Nuclear containments, which remain intact after failure of all emergency cooling systems resulting in a core meltdown accident with steam and hydrogen explosions, are in line with these principles. Such containments are under investigation in Germany right now. It is pointed out that the public should be informed prudently about this work to improve the containments, and the required transparency of the engineered safeguards should be underlined as a major goal. Vague descriptions, providing only superficially information about safer reactors, could easily cause misunderstandings. If one goes along this line a simpler and more transparent safety concept employing improved containments will have the potential to raise the acceptance of nuclear reactors. (orig.)

DOT1L inhibitor improves early development of porcine somatic cell nuclear transfer embryos

DEFF Research Database (Denmark)

Tao, Jia; Zhang, Yu; Zuo, Xiaoyuan

2017-01-01

Incomplete epigenetic reprogramming of the genome of donor cells causes poor early and full-term developmental efficiency of somatic cell nuclear transfer (SCNT) embryos. Previous research indicate that inhibition of the histone H3 K79 methyltransferase DOT1L, using a selective pharmacological...... inhibitor EPZ004777 (EPZ), significantly improved reprogramming efficiency during the generation of mouse induced pluripotent stem cells. However, the roles of DOT1L in porcine nuclear transfer-mediated cellular reprogramming are not yet known. Here we showed that DOT1L inhibition via 0.5 nM EPZ treatment...

Application of Modern Technologies for Nuclear Power Plant Productivity Improvements

International Nuclear Information System (INIS)

Joseph, A. Naser

2011-01-01

The nuclear power industry in several countries is concerned about the ability to maintain current high plant performance levels due to aging and obsolescence, knowledge drain, fewer plant staff, new requirements and commitments, unnecessary workloads and stress levels, and human errors. Current plant operations are labor-intensive due to the vast number of operational and support activities required by the commonly used technology in most plants. These concerns increase as plants extend their operating life. In addition, there is the desire by many plants to further improve performance while reducing human errors and increasingly focus on reducing operations and maintenance costs. New productivity improvement capabilities with measurable economic benefits are needed so that a successful business case can be made for their use. Improved and new instrumentation and control, human-system interface, information and communications technologies used properly can address concerns about cost-effectively maintaining current performance levels and enable shifts to even higher performance levels. This can be accomplished through the use of new technology implementations to improve productivity, reduce costs of systemic inefficiencies and avoid unexpected costs. Many of the same type of productivity improvements for operating plants will be applicable for new plants. As new plants are being built, it is important to include these productivity improvements or at least provide the ability to implement them easily later

Safety improvement technologies for nuclear power generation

International Nuclear Information System (INIS)

Nishida, Koji; Adachi, Hirokazu; Kinoshita, Hirofumi; Takeshi, Noriaki; Yoshikawa, Kazuhiro; Itou, Kanta; Kurihara, Takao; Hino, Tetsushi

2015-01-01

As the Hitachi Group's efforts in nuclear power generation, this paper explains the safety improvement technologies that are currently under development or promotion. As efforts for the decommissioning of Fukushima Daiichi Nuclear Power Station, the following items have been developed. (1) As for the spent fuel removal of Unit 4, the following items have mainly been conducted: removal of the debris piled up on the top surface of existing reactor building (R/B), removal of the debris deposited in spent fuel pool (SFP), and fuel transfer operation by means of remote underwater work. The removal of all spent fuels was completed in 2014. (2) The survey robots inside R/B, which are composed of a basement survey robot to check leaking spots at upper pressure suppression chamber and a floor running robot to check leaking spots in water, were verified with a field demonstration test at Unit 1. These robots were able to find the leaking spots at midair pipe expansion joint. (3) As the survey robot for reactor containment shells, robots of I-letter posture and horizontal U-letter posture were developed, and the survey on the upper part of first-floor grating inside the containment shells was performed. (4) As the facilities for contaminated water measures, sub-drain purification equipment, Advanced Liquid Processing System, etc. were developed and supplied, which are now showing good performance. On the other hand, an advanced boiling water reactor with high safety of the United Kingdom (UK ABWR) is under procedure of approval for introduction. In addition, a next-generation light-water reactor of transuranic element combustion type is under development. (A.O.)

Future nuclear systems technology

International Nuclear Information System (INIS)

Brooks, H.

1979-01-01

Five directions can be identified for evolution of nuclear systems, possibly a sixth. These are, first, and perhaps most important, toward a means of extending fissile resources through improvement of the efficiency of their use; second, improvements in nuclear safety; third, reduction in the environmental impacts of nuclear electric power generation, particularly water requirements; fourth, improvements in proliferation resistance of the nuclear fuel cycle; and fifth, improvements in economics. And added in a sixth, and somewhat more speculative direction, the use of nuclear power for purposes other than the direct generation of electricity

Concerning improvement and reform towards a more effective and realisable nuclear liability legal system in Japan

International Nuclear Information System (INIS)

Iizuka, H.

2006-01-01

Japan is the only country in the world that has ever experienced being attacked by atomic bombs. Japanese people have a special feeling towards nuclear power. Japan has opted for an unlimited liability system, which is regarded as a hospitable one to victims in Japan. Under the existing unlimited liability system in Japan, however, there is a problem that nuclear operators cannot necessarily foresee the probable limit of their risks to owe. In this paper, I want to present problems of the nuclear liability legal system, and proposals for improvement and reform towards more effective and realisable system in Japan. (author)

Flexible Riser Monitoring Using Hybrid Magnetic/Optical Strain Gage Techniques through RLS Adaptive Filtering

Directory of Open Access Journals (Sweden)

Daniel Pipa

2010-01-01

Full Text Available Flexible riser is a class of flexible pipes which is used to connect subsea pipelines to floating offshore installations, such as FPSOs (floating production/storage/off-loading unit and SS (semisubmersible platforms, in oil and gas production. Flexible risers are multilayered pipes typically comprising an inner flexible metal carcass surrounded by polymer layers and spiral wound steel ligaments, also referred to as armor wires. Since these armor wires are made of steel, their magnetic properties are sensitive to the stress they are subjected to. By measuring their magnetic properties in a nonintrusive manner, it is possible to compare the stress in the armor wires, thus allowing the identification of damaged ones. However, one encounters several sources of noise when measuring electromagnetic properties contactlessly, such as movement between specimen and probe, and magnetic noise. This paper describes the development of a new technique for automatic monitoring of armor layers of flexible risers. The proposed approach aims to minimize these current uncertainties by combining electromagnetic measurements with optical strain gage data through a recursive least squares (RLSs adaptive filter.

Improving automated load flexibility of nuclear power plants with ALFC

Energy Technology Data Exchange (ETDEWEB)

Kuhn, Andreas [AREVA GmbH, Karlstein (Germany). Plant Control/Training; Klaus, Peter [E.ON NPP Isar 2, Essenbach (Germany). Plant Operation/Production Engineering

2016-07-01

In several German and Swiss Nuclear Power Plants with Pressurized Water Reactor (PWR) the control of the reactor power was and will be improved in order to be able to support the energy transition with increasing volatile renewable energy in the grid by flexible load operation according to the need of the load dispatcher (power system stability). Especially regarding the mentioned German NPPs with a nominal electric power of approx. 1,500 MW, the general objectives are the main automated grid relevant operation modes. The new possibilities of digital I and C (as TELEPERM {sup registered} XS) enable the automation of the operating modes provided that manual support is no longer necessary. These possibilities were and will be implemented by AREVA within the ALFC-projects. Manifold adaption algorithms to the reactor physical variations during the nuclear load cycle enable a precise control of the axial power density distribution and of the reactivity management in the reactor core. Finally this is the basis for a highly automated load flexibility with the parallel respect and surveillance of the operational limits of a PWR.

Improving automated load flexibility of nuclear power plants with ALFC

Energy Technology Data Exchange (ETDEWEB)

Kuhn, Andreas [AREVA GmbH, Karlstein (Germany). Section Manager Training; Klaus, Peter [Preussenelektra NPP, Essenbach (Germany). Production Engineering

2017-03-15

In several German and Swiss Nuclear Power Plants with Pressurized Water Reactor (PWR) the control of the reactor power was and will be improved in order to be able to support the energy transition with increasing volatile renewable energy in the grid by flexible load operation according to the need of the load dispatcher (power system stability). Especially regarding the mentioned German NPPs with a nominal electric power of approx. 1500 MW, the general objectives are several automated grid relevant operation modes. The new possibilities of digital I and C (as TELEPERM {sup registered} XS) enable the automation of this operating modes provided that manual support is no longer necessary. These possibilities were and will be implemented by AREVA within the ALFC-projects. Manifold adaption algorithms to the reactor physical variations during the nuclear load cycle enable a precise control of the axial power density distribution and of the reactivity manage - ment in the reactor core. Finally this is the basis for a highly automated load flexibility with the parallel respect and surveillance of the operational limits of a PWR.

Iraq uses nuclear technology to improve crop productivity and adapt to climate change

International Nuclear Information System (INIS)

Gil, Laura

2016-01-01

A new drought-tolerant wheat variety developed with the support of the IAEA and the Food and Agriculture Organization of the United Nations (FAO) has increased yields fourfold in Iraq. This mutant variety now accounts for close to two thirds of all the wheat produced in the country. Iraq is increasingly making use of nuclear technology to improve its crop yields and cope with the consequences of a changing climate. Researchers in the country have developed new drought-tolerant plant varieties and improved water and soil management.

Improved design for vibration-proof platinum RTD in special position of nuclear power plant

International Nuclear Information System (INIS)

Liu Zhuo; Ma Jinna; Wu Bin

2014-01-01

In accordance with the actual situation for the vibration of violence in a special position of nuclear power plant, an improved design for platinum RTD was proposed. The structure design is verified to meet the measure requirement in the special position. (authors)

How the radiologic and nuclear medical communities can improve nuclear security.

Science.gov (United States)

Kahn, Laura H; von Hippel, Frank

2007-04-01

Highly enriched uranium (HEU) is used to manufacture technetium-99m, the most widely used medical radioisotope in the world. Highly enriched uranium is also used to make nuclear bombs; 50 kg of HEU is enough to make a Hiroshima-type bomb. It is generally agreed that this technology is within the reach of a terrorist group; the main obstacle is acquiring HEU. Currently, as a legacy of the US and Soviet Atoms for Peace Program, there are civilian users of HEU in 40 countries, and about 1,000 kg are still being shipped each year. Unfortunately, the major international manufacturers of technetium-99m have been refusing to convert their production facilities to use low-enriched uranium (LEU), which cannot be used to make a nuclear bomb. Only 1% to 2% of the HEU is consumed in the process of producing technetium-99m. The remainder is accumulating in radioactive waste storage facilities. The radiologic and nuclear medical communities could make a tremendous contribution to a safer world by supporting the replacement of HEU with LEU in the production of technetium-99m. Low-enriched uranium is just as cost effective as HEU for the manufacture of technetium-99m and does not contribute to the risk for nuclear terrorism.

A Method to Improve the Software Acceptance Criteria for Nuclear Power Plants

International Nuclear Information System (INIS)

Suh, Yong Suk; Park, Heui Youn; Son, Ki Sung; Lee, Ki Hyun; Kim, Hyeon Soo

2005-01-01

The license is a mandatory process required by a governmental authority and the certification is a voluntary process administrated by a professional community. A software certification is a result of an assessment that the certified software conforms to required criteria or standards. The certification is used as a committed promise to produce a high quality software, so software acquirers are requiring it from their suppliers. For example, US DoD (Department of Defense) requires an achievement of CMMI-SW (Capability Maturity Model Integration-Software) certification for participating in a major military software project. It is commonly said that the purpose of achieving a certification is to improve the product quality. In the nuclear area, a software certification has been rarely concerned with or required for the software used in a safety function of NPPs (Nuclear Power Plants). The safety critical software for NPPs is accepted by the nuclear regulators when the following three criteria are met: acceptable plans should be prepared to control the software development activities, the plans should be followed in an acceptable software life cycle, and the process should produce acceptable design outputs. The acceptance criteria are so abstractive that the nuclear regulators may assess the software development plans, activities, outputs based on their subjective engineering judgments. This is inevitable because a software has invisible or intangible characteristics. It is hard to assess the totality of a software prior to running it. These have caused the judgments to be biased. The regulators may want some objectiveness in assessing how much capability for software development the supplier possesses. In that case, the software certification can assist them for such an assessment. This paper proposes a method to improve the software acceptance criteria by applying the software certification to the criteria. This will assist the regulators to assess the supplier

arXiv Improved Monte Carlo Glauber predictions at present and future nuclear colliders

CERN Document Server

Loizides, Constantin; d'Enterria, David

2018-05-23

We present the results of an improved Monte Carlo Glauber (MCG) model of relevance for collisions involving nuclei at center-of-mass energies of BNL RHIC ($\\sqrt{s_{\\rm NN}}=0.2$ TeV), CERN LHC ($\\sqrt{s_{\\rm NN}}=2.76$-$8.8$ TeV), and proposed future hadron colliders ($\\sqrt{s_{\\rm NN}}\\approx 10$-$63$ TeV). The inelastic pp cross sections as a function of $\\sqrt{s_{\\rm NN}}$ are obtained from a precise data-driven parametrization that exploits the many available measurements at LHC collision energies. We describe the nuclear transverse profile with two separated 2-parameter Fermi distributions for protons and neutrons to account for their different densities close to the nuclear periphery. Furthermore, we model the nucleon degrees of freedom inside the nucleus through a lattice with a minimum nodal separation, combined with a "recentering and reweighting" procedure, that overcomes some limitations of previous MCG approaches. The nuclear overlap function, number of participant nucleons and binary nucleon-nuc...

Accelerometer and strain gage evaluation

International Nuclear Information System (INIS)

Ammerman, D.J.; Madsen, M.M.; Uncapher, W.L.; Stenberg, D.R.; Bronowski, D.R.

1991-01-01

This document describes the method developed by Sandia National Laboratories (SNL) to evaluate transducer used in the design certification testing of nuclear material shipping packages. This testing project was performed by SNL for the Office of Civilian Radioactive Waste Management (OCRWM). This evaluation is based on the results of tests conducted to measure ruggedness, failure frequency, repeatability, and manufacturers' calibration data under both field and laboratory conditions. The results of these tests are provided and discussed. The transducer were selected for testing by surveying cask contractors and testing facilities. Important insights relating to operational characteristics of accelerometer types were gained during field testing. 11 refs., 105 figs., 16 tabs

Improving the fidelity of electrically heated nuclear systems testing using simulated neutronic feedback

International Nuclear Information System (INIS)

Bragg-Sitton, Shannon M.; Godfroy, Thomas J.; Webster, Kenny

2010-01-01

Nonnuclear test platforms and methodologies can be employed to reduce the overall cost, risk and complexity of testing nuclear systems while allowing one to evaluate the operation of an integrated nuclear system within a reasonable timeframe, providing valuable input to the overall system design. In a nonnuclear test bed, electric heaters are used to simulate the heat from nuclear fuel. Standard electric test techniques allow one to fully assess thermal, heat transfer, and stress related attributes of a given system, but these approaches fail to demonstrate the dynamic response that would be present in an integrated, fueled reactor system. The integration of thermal hydraulic hardware tests with simulated neutronic response provides a bridge between electrically heated testing and testing with nuclear fuel elements installed. By implementing a neutronic response model to simulate the dynamic response that would be expected in a fueled reactor system, one can better understand system integration issues, characterize integrated system response times and response characteristics, and assess potential design improvements at a relatively small fiscal investment. This paper summarizes the results of initial system dynamic response testing for two electrically heated reactor concepts: a heat pipe-cooled reactor simulator with integrated heat exchanger and a gas-cooled reactor simulator with integrated Brayton power conversion system. Initial applications apply a simplified reactor kinetics model with either a single or an averaged measured state point. Preliminary results demonstrate the applicability of the dynamic test methodology to any reactor type, elucidating the variation in system response characteristics in different reactor concepts. These results suggest a need to further enhance the dynamic test approach by incorporating a more accurate model of the reactor dynamics and improved hardware instrumentation for better state estimation in application of the

Nuclear Forensics and Attribution for Improved Energy Security: The Use of Taggants in Nuclear Fuel

International Nuclear Information System (INIS)

Kristo, M J; Robel, M; Hutcheon, I D

2007-01-01

The Global Nuclear Energy Partnership (GNEP), recently announced by DOE Secretary Bodman, poses significant new challenges with regard to securing, safeguarding, monitoring and tracking nuclear materials. In order to reduce the risk of nuclear proliferation, new technologies must be developed to reduce the risk that nuclear material can be diverted from its intended use. Regardless of the specific nature of the fuel cycle, nuclear forensics and attribution will play key roles to ensure the effectiveness of nonproliferation controls and to deter the likelihood of illicit activities. As the leader of the DHS nuclear and radiological pre-detonation attribution program, LLNL is uniquely positioned to play a national leadership role in this effort. Ensuring that individuals or organizations engaged in illicit trafficking are rapidly identified and apprehended following theft or diversion of nuclear material provides a strong deterrent against unlawful activities. Key to establishing this deterrent is developing the ability to rapidly and accurately determine the identity, source and prior use history of any interdicted nuclear material. Taggants offer one potentially effective means for positively identifying lost or stolen nuclear fuels. Taggants are materials that can be encoded with a unique signature and introduced into nuclear fuel during fuel fabrication. During a nuclear forensics investigation, the taggant signature can be recovered and the nuclear material identified through comparison with information stored in an appropriate database. Unlike serial numbers or barcodes, microtaggants can provide positive identification with only partial recovery, providing extreme resistance to any attempt to delete or alter them

Nuclear safety in Slovak Republic. Status of safety improvements

International Nuclear Information System (INIS)

Toth, A.

1999-01-01

Status of the safety improvements at Bohunice V-1 units concerning WWER-440/V-230 design upgrading were as follows: supplementing of steam generator super-emergency feed water system; higher capacity of emergency core cooling system; supplementing of automatic links between primary and secondary circuit systems; higher level of secondary system automation. The goal of the modernization program for Bohunice V-1 units WWER-440/V-230 was to increase nuclear safety to the level of the proposals and IAEA recommendations and to reach probability goals of the reactor concerning active zone damage, leak of radioactive materials, failures of safety systems and damage shields. Upgrading program for Mochovce NPP - WWER-440/V-213 is concerned with improving the integrity of the reactor pressure vessel, steam generators 'leak before break' methods applied for the NPP, instrumentation and control of safety systems, diagnostic systems, replacement of in-core monitoring system, emergency analyses, pressurizers safety relief valves, hydrogen removal system, seismic evaluations, non-destructive testing, fire protection. Implementation of quality assurance has a special role in improvement of operational safety activities as well as safety management and safety culture, radiation protection, decommissioning and waste management and training. The Year 2000 problem is mentioned as well

Improvement of customer satisfaction evaluation for quality management system and accreditation in Nuclear Malaysia

International Nuclear Information System (INIS)

Fazila Said; Noriah Ali; Siti Mariam Ibrahim

2010-01-01

Malaysian Nuclear Agency (Nuclear Malaysia) possesses seven certification of Quality Management System, namely ISO 9001:2008, and two certification of Malaysia Laboratory Accreditation Scheme, namely ISO/IEC 17025:2005. General Requirement of Standard for those two certifications needs customer satisfaction evaluation to be conducted every year. Thus, the Innovation Management Centre (IMC) undertakes improvement action to harmonise and coordinate the formulation of questionnaires in Nuclear Malaysia based on data analysis for 2009. The newly developed questionnaire that applies to all processes and laboratories that have received or awaiting certification have value addition in terms of analytical methods that are more concise, precise, simple and focus on effective action plan to enhance customer satisfaction. Methods such as Importance-Performance Analysis (IPA), Customer Satisfaction Index (CSI) and Service Quality Dimension (SERVQUAL) will be used in this research. (author)

Demands for improvement in working surroundings for older workers in nuclear power plants

International Nuclear Information System (INIS)

Shizawa, Yasuhiro; Sakuda, Hiroshi; Ohashi, Tomoki

2003-01-01

Workers in three nuclear power plants belonging to Kansai Electric Power Co., Inc. were asked to complete a questionnaire. According to the accident reports, workers aged 50 or older had more accidents than those in 30s or 40s. Moreover, it is predicted that the average age of workers in Japan will increase during the first half of the 21st century. Therefore, investigations into working surroundings in which older workers can better perform their work would be useful. To this end, a questionnaire addressing issues related to working surroundings was conducted among workers in nuclear power plants and the demands for improvement of working surroundings for older workers are summarized. The demands of 'better lighting', 'making things less heavy', and installation of an elevator' were correlated with age, indicating that younger people have a tendency not to notice these issues. Thus, if the authority deciding on improvements in working surroundings is not an older worker, it is especially important that lighting, the weights of objects to be moved, and methods of moving between floors is taken into account. Findings specific to nuclear power plants were also reported. For example, employees who worked in the non-radiation controlled area demanded the installation of air conditioning and those who worked in the radiation controlled area demanded the establishment of a rest area. Further, we have developed a guidebook entitled 'a guidebook supporting workers' cooperation among all generations' to promote cooperation between older and younger workers. (author)

Improvements of the Regulatory Framework for Nuclear Installations in the Areas of Human and Organizational Factors and Safety Culture

International Nuclear Information System (INIS)

Tronea, M.; Ciurea, C.

2016-01-01

The paper presents the development of regulatory requirements in the area of human and organizational factors taking account of the lessons learned from major accidents in the nuclear industry and in particular of the factors that contributed to the Fukushima Daiichi accident and the improvement of the regulatory oversight of nuclear safety culture. New requirements have been elaborated by the National Commission for Nuclear Activities Control (CNCAN) on the nuclear safety policy of licencees for nuclear installations, on independent nuclear safety oversight, on safety conscious work environment and on the assessment of nuclear safety culture. The regulatory process for the oversight of nuclear safety culture within licencees’ organizations operating nuclear installations and the associated procedure and guidelines, based on the IAEA Safety Standards, have been developed in 2010-2011. CNCAN has used the 37 IAEA attributes for a strong safety culture, grouped into five areas corresponding to safety culture characteristics, as the basis for its regulatory guidelines providing support to the reviewers and inspectors, in their routine activities, for recognising and gathering information relevant to safety culture. The safety culture oversight process, procedure and guidelines are in process of being reviewed and revised to improve their effectiveness and to align with the current international practices, using lessons learned from the Fukushima Daiichi accident. Starting with July 2014, Romania has a National Strategy for Nuclear Safety and Security, which includes strategic objectives, associated directions for action and concrete actions for promoting nuclear safety culture in all the organizations in the nuclear sector. The progress with the implementation of this strategy with regard to nuclear safety culture is described in the paper. CNCAN started to define its own organizational culture model and identifying the elements that promote and support safety

Advanced control systems to improve nuclear power plant reliability and efficiency

International Nuclear Information System (INIS)

1997-07-01

The TECDOC is the result of a series of an advisory and consultants meetings held by the IAEA in 1995-1996 in Vienna (March 1995), in Erlangen Germany (December 1995), in Garching, Germany (June 1996) and in Vienna (November 1996). It was prepared with the participation and contributions of experts from Austria, Canada, Finland, France, Germany, the Republic of Korea, Norway, the Russian Federation, the United Kingdom and the United States of America. The publication not only describes advanced control systems for the improvement of nuclear power plant reliability and efficiency, but also provides a road map to guide interested readers to plan and execute an advanced instrumentation and control project. The subjects include: identification of needs and requirements, justification for safety and user acceptance, and the development of an engineering process. The report should be of interest to nuclear power plant staff, I and C system designers and integrators as well as regulators and researchers. Refs, figs, tabs

Advanced control systems to improve nuclear power plant reliability and efficiency

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

The TECDOC is the result of a series of an advisory and consultants meetings held by the IAEA in 1995-1996 in Vienna (March 1995), in Erlangen Germany (December 1995), in Garching, Germany (June 1996) and in Vienna (November 1996). It was prepared with the participation and contributions of experts from Austria, Canada, Finland, France, Germany, the Republic of Korea, Norway, the Russian Federation, the United Kingdom and the United States of America. The publication not only describes advanced control systems for the improvement of nuclear power plant reliability and efficiency, but also provides a road map to guide interested readers to plan and execute an advanced instrumentation and control project. The subjects include: identification of needs and requirements, justification for safety and user acceptance, and the development of an engineering process. The report should be of interest to nuclear power plant staff, I and C system designers and integrators as well as regulators and researchers. Refs, figs, tabs.

Improvement of nuclear power plants within the perspective of applications of lean manufacturing practices

Science.gov (United States)

Malek, A. K.; Muhammad, H. I.; Rosmaini, A.; Alaa, A. S.; Falah, A. M.

2017-09-01

Development and improvement process are essential to the companies and factories of various kinds and this necessity is related aspects of cost, time and risk that can be avoided, these aspects are available at the nuclear power stations essential demands cannot be ignored. The lean management technique is one of the recent trends in the management system. Where the lean management is stated as the system increases the customer value and reduces the wastage process in an industry or in a power plants. Therefore, there is an urgent necessity to ensure the development and improvement in nuclear power plants in the pre-established in process of being established and stage of the management and production. All of these stages according to the study are closely related to the necessity operationalize and apply lean manufacturing practices that these applications are ineffective and clear contribution to reduce costs and control of production processes and the process of reducing future risks that could be exposed to the station.

Construction Improvement for the Korean Nuclear Program

International Nuclear Information System (INIS)

Yang, T. E.

1992-01-01

Construction of the nine Nuclear plants requires an enormous financial investment. The decision to build a nuclear unit is based on both economic and resource requirements. Korea has few natural resources to use for power generation so the use of diversified fuel sources is a part of the planning process. Nuclear has historically had economic advantages over the fossil fueled plant, however, this advantage has been reduced. This is mainly due to increasing decommissioning and waste disposal costs plus the financial outlays associated with gaining public acceptance of new nuclear units. One of the principal means to recover the economic advantage of a nuclear plant is to shorten the time needed for construction. Every extra day of construction costs large sums of money in interest and escalation expenses alone. The challenge is to shorten the construction period to the minimum feasible time and thereby reduce the financing costs. The methods that have to be employed to achieve this goal require the total commitment from the management of all entities involved in the program. Through the application of advanced management and construction techniques a new era in the construction of nuclear plants in Korea will occur. This will include changes to the methods used for managing, planning, licensing, designing and constructing the new plants. The ability to meet the aggressive plan for the construction of new nuclear power plants in Korea rests in the hands of the managers of all the parties involved. These men set all the rules by which the new plants will be constructed. It is their responsibility to tackle the current problems and develop the solutions to enable the plan to be realized. The changes suggested within this paper are major, but the potential benefits will allow the Korean Nuclear Industry to advance into the twenty first Century as a leader. The number of fully trained specialists needed to make this happen will not appear overnight. They will have to be

Improving nuclear regulation. Compilation of Nea regulatory guidance booklets

International Nuclear Information System (INIS)

2009-01-01

A common theme throughout the series of NEA regulatory guidance reports, or 'green booklets', is the premise that the fundamental objective of all nuclear safety regulatory bodies is to ensure that nuclear facilities are operated at all times and later decommissioned in an acceptably safe manner. In meeting this objective the regulator must keep in mind that it is the operator that has responsibility for safely operating a nuclear facility; the role of the regulator is to oversee the operator's activities as related to assuming that responsibility. For the first time, the full series of these reports have been brought together in one edition. As such, it is intended to serve as a knowledge management tool both for current regulators and the younger generation of nuclear experts entering the regulatory field. While the audience for this publication is primarily nuclear regulators, the information and ideas may also be of interest to nuclear operators, other nuclear industry organisations and the general public. (author)

Analysis of residual transverse stresses in a thick UD glass/polyester pultruded profile using hole drilling with strain gage and digital image correlation

Science.gov (United States)

Yuksel, Onur; Baran, Ismet; Ersoy, Nuri; Akkerman, Remko

2018-05-01

Process induced stresses inherently exist in fiber reinforced polymer composites particularly in thick parts due to the presence of non-uniform cure, shrinkage and thermal expansion/contraction during manufacturing. In order to increase the reliability and the performance of the composite materials, process models are developed to predict the residual stress formation. The accuracy of the process models is dependent on the geometrical (micro to macro), material and process parameters as well as the numerical implementation. Therefore, in order to have reliable process modelling framework, there is a need for validation and if necessary calibration of the developed models. This study focuses on measurement of the transverse residual stresses in a relatively thick pultruded profile (20×20 mm) made of glass/polyester. Process-induced residual stresses in the middle of the profile are examined with different techniques which have never been applied for transverse residual stresses in thick unidirectional composites. Hole drilling method with strain gage and digital image correlation are employed. Strain values measured from measurements are used in a finite element model (FEM) to simulate the hole drilling process and predict the residual stress level. The measured released strain is found to be approximately 180 μm/m from the strain gage. The tensile residual stress at the core of the profile is estimated approximately as 7-10 MPa. Proposed methods and measured values in this study will enable validation and calibration of the process models based on the residual stresses.

Improving the international system for operating experience feedback. INSAG-23. A report by the International Nuclear Safety Group

International Nuclear Information System (INIS)

2008-01-01

The operational safety performance of nuclear facilities has, in general, improved notably over time throughout the world. This has been achieved, in part, through operating experience feedback (OEF) and the introduction of new technology. While the continued strong safety performance by operators is encouraging, safety significant events continue to recur in nuclear installations. This indicates that operators are not learning and applying the lessons that experience can teach us. This report focuses on systems that are operated by intergovernmental organizations with close contacts to national regulatory authorities. These systems provide an alternative network to the worldwide system employed by the operators of nuclear facilities known as the World Association of Nuclear Operators (WANO). The WANO system is restricted to its members, who have concluded that keeping the information exchanged confidential improves its usefulness. INSAG recognizes the merits of this approach, particularly in light of the primary responsibility of licensed operators for the safety of their facilities. Nevertheless, INSAG encourages WANO to share key safety lessons with national regulatory authorities and intergovernmental organization

Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, November 2013

International Nuclear Information System (INIS)

De Saint Jean, C.; Dupont, E.; ); Dyrda, J.; Hursin, M.; Pelloni, S.; Ishikawa, M.; Ivanov, E.; Ivanova, T.; Kim, D.H.; Ee, Y.O.; Kodeli, I.; Leal, L.; Leichtle, D.; Palmiotti, G.; Salvatores, M.; Pronyaev, V.; Simakov, S.; )

2013-11-01

The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the first formal Subgroup 39 meeting held at the NEA, Issy-les-Moulineaux, France, on 28-29 November 2013. It comprises a Summary Record of the meeting and all the available presentations (slides) given by the participants: A - Recent data adjustments performances and trends: 1 - Recommendations from ADJ2010 adjustment (M. Ishikawa); 2 - Feedback on CIELO isotopes from ENDF/B-VII.0 adjustment (G. Palmiotti); 3 - Sensitivity and uncertainty results on FLATTOP-Pu (I. Kodeli); 4 - SG33 benchmark: Comparative adjustment results (S. Pelloni) 5 - Integral benchmarks for data assimilation: selection of a consistent set and establishment of integral correlations (E. Ivanov); 6 - PROTEUS experimental data (M. Hursin); 7 - Additional information on High Conversion Light Water Reactor (HCLWR aka FDWR-II) experiments (14 January 2014); 8 - Data assimilation of benchmark experiments for homogenous thermal/epithermal uranium systems (J. Dyrda); B - Methodology issues: 1 - Adjustment methodology issues (G. Palmiotti); 2 - Marginalisation, methodology issues and nuclear data parameter adjustment (C. De Saint Jean); 3 - Nuclear data parameter adjustment (G. Palmiotti). A list of issues and actions conclude the document

Fuzzy logic control for improved pressurizer systems in nuclear power plants

International Nuclear Information System (INIS)

Brown, Chris; Gabbar, Hossam A.

2014-01-01

Highlights: • Improved performance of the pressurizer system in a CANDU nuclear power plant (NPP). • Inventory control for the pressurizer system in NPP. • Compare fuzzy logic with PID in pressurizer system in NPP. • Develop a fuzzy controller to regulate the pressurizer inventory control. • Compare control performance with current proportional controller used at NPP. - Abstract: The pressurizer system in a CANDU nuclear power plant is responsible for maintaining the pressure of the primary heat transport system to ensure the plant is operated within its safe operating envelope. The inventory control for the pressurizer system use a combination of level sensors, feed valves and bleed valves to ensure that there is adequate room in the pressurizer to accommodate any swell or shrinkage in the PHT system. The Darlington Nuclear Generating Station (DNGS) in Ontario, Canada currently uses a proportional controller for the bleed and feed valves to regulate the pressurizer inventory control which can result in large coolant level overshoot along with excessive settling times. The purpose of this paper is to develop a fuzzy controller to regulate the pressurizer inventory control and compare its performance to the current proportional controller used at DNGS. The simulation of the pressurizer inventory control system shows the fuzzy controller performs better than the proportional controller in terms of settling time and overshoot

Improving Industry-Relevant Nuclear-Knowledge Development through Special Partnerships

International Nuclear Information System (INIS)

Cilliers, A.

2016-01-01

Full text: South African Network for Nuclear Education Science and Technology (SAN NEST) has the objective to develop the nuclear education system in South Africa to a point where suitably qualified and experienced nuclear personnel employed by nuclear science and technology programmes in South Africa are predominantly produced by the South African education system. This is done to strengthen the nuclear science and technology education programmes to better meet future demands in terms of quality, capacity and relevance. To ensure sustainable relevance, it is important to develop special partnerships with industry. This paper describes unique partnerships that were developed with nuclear industry partners. The success of these partnerships has ensured more industry partners to embrace the model which has proven to develop relevant knowledge, support research and provide innovative solutions for industry. (author

Nuclear security. Improving correction of security deficiencies at DOE's weapons facilities

International Nuclear Information System (INIS)

Wells, James E.; Cannon, Doris E.; Fenzel, William F.; Lightner, Kenneth E. Jr.; Curtis, Lois J.; DuBois, Julia A.; Brown, Gail W.; Trujillo, Charles S.; Tumler, Pamela K.

1992-11-01

The US nuclear weapons research, development, and production are conducted at 10 DOE nuclear weapons facilities by contractors under the guidance and oversight of 9 DOE field offices. Because these facilities house special nuclear materials used in making nuclear weapons and nuclear weapons components, DOE administers a security program to protect (1) against theft, sabotage, espionage, terrorism, or other risks to national security and (2) the safety and health of DOE employees and the public. DOE spends almost $1 billion a year on this security program. DOE administers the security program through periodic inspections that evaluate and monitor the effectiveness of facilities' safeguards and security. Security inspections identify deficiencies, instances of noncompliance with safeguards and security requirements or poor performance of the systems being evaluated, that must be corrected to maintain adequate security. The contractors and DOE share responsibility for correcting deficiencies. Contractors, in correcting deficiencies, must comply with several DOE orders. The contractors' performances were not adequate in conducting four of the eight procedures considered necessary in meeting DOE's deficiency correction requirements. For 19 of the 20 deficiency cases we reviewed, contractors could not demonstrate that they had conducted three critical deficiency analyses (root cause, risk assessment, and cost-benefit) required by DOE. Additionally, the contractors did not always adequately verify that corrective actions taken were appropriate, effective, and complete. The contractors performed the remaining four procedures (reviewing deficiencies for duplication, entering deficiencies into a data base, tracking the status of deficiencies, and preparing and implementing a corrective action plan) adequately in all 20 cases. DOE's oversight of the corrective action process could be improved in three areas. The computerized systems used to track the status of security

Energy Research Advisory Board, Civilian Nuclear Power Panel: Subpanel 1 report, Light water reactor utilization and improvement: Volume 2

International Nuclear Information System (INIS)

1986-10-01

The Secretary of Energy requested that the Office of Nuclear Energy prepare a strategic national plan that outlines the Department's role in the future development of civilian nuclear power and that the Energy Research Advisory Board establish an ad hoc panel to review and comment on this plan. The Energy Research Advisory Board formed a panel for this review and three subpanels were formed. One subpanel was formed to address the institutional issues surrounding nuclear power, one on research and development for advanced nuclear power plants and a third subpanel on light water reactor utilization and improvement. The subpanel on light water reactors held two meetings at which representatives of the DOE, the NRC, EPRI, industry and academic groups made presentations. This is the report of the subpanel on light water reactor utilization and improvement. This report presents the subpanel's assessment of initiatives which the Department of Energy should undertake in the national interest, to develop and support light water reactor technologies

Vertical datum conversion process for the inland and coastal gage network located in the New England, Mid-Atlantic, and South Atlantic-Gulf hydrologic regions

Science.gov (United States)

Rydlund, Jr., Paul H.; Noll, Michael L.

2017-03-07

Datum conversions from the National Geodetic Vertical Datum of 1929 to the North American Vertical Datum of 1988 among inland and coastal gages throughout the hydrologic regions of New England, the Mid-Atlantic, and the South Atlantic-Gulf have implications among river and storm surge forecasting, general commerce, and water-control operations. The process of data conversions may involve the application of a recovered National Geodetic Vertical Datum of 1929–North American Vertical Datum of 1988 offset, a simplistic datum transformation using VDatum or VERTCON software, or a survey, depending on a gaging network datum evaluation, anticipated uncertainties for data use among the cooperative water community, and methods used to derive the conversion. Datum transformations from National Geodetic Vertical Datum of 1929 to North American Vertical Datum of 1988 using VERTCON purport errors of ± 0.13 foot at the 95 percent confidence level among modeled points, claiming more consistency along the east coast. Survey methods involving differential and trigonometric leveling, along with observations using Global Navigation Satellite System technology, afford a variety of approaches to establish or perpetuate a datum during a survey. Uncertainties among leveling approaches are generally quality category and ≥0.1 foot for Level II or III quality categories (defined by the U.S. Geological Survey) by observation and review of experienced practice. The conversion process is initiated with an evaluation of the inland and coastal gage network datum, beginning with altitude datum components and the history of those components queried through the U.S. Geological Survey Groundwater Site Inventory database. Subsequent edits to the Groundwater Site Inventory database may be required and a consensus reached among the U.S. Geological Survey Water Science Centers to identify the outstanding workload categorized as in-office datum transformations or offset applications versus out

Nuclear safety culture and nuclear safety supervision

International Nuclear Information System (INIS)

Chai Jianshe

2013-01-01

In this paper, the author reviews systematically and summarizes up the development process and stage characteristics of nuclear safety culture, analysis the connotation and characteristics of nuclear safety culture, sums up the achievements of our country's nuclear safety supervision, dissects the challenges and problems of nuclear safety supervision. This thesis focused on the relationship between nuclear safety culture and nuclear safety supervision, they are essential differences, but there is a close relationship. Nuclear safety supervision needs to introduce some concepts of nuclear safety culture, lays emphasis on humanistic care and improves its level and efficiency. Nuclear safety supervision authorities must strengthen nuclear safety culture training, conduct the development of nuclear safety culture, make sure that nuclear safety culture can play significant roles. (author)

Influence of the Testing Gage Length on the Strength, Young's Modulus and Weibull Modulus of Carbon Fibres and Glass Fibres

Directory of Open Access Journals (Sweden)

Luiz Claudio Pardini

2002-10-01

Full Text Available Carbon fibres and glass fibres are reinforcements for advanced composites and the fiber strength is the most influential factor on the strength of the composites. They are essentially brittle and fail with very little reduction in cross section. Composites made with these fibres are characterized by a high strength/density ratio and their properties are intrisically related to their microstructure, i.e., amount and orientation of the fibres, surface treatment, among other factors. Processing parameters have an important role in the fibre mechanical behaviour (strength and modulus. Cracks, voids and impurities in the case of glass fibres and fibrillar misalignments in the case of carbon fibres are created during processing. Such inhomogeneities give rise to an appreciable scatter in properties. The most used statistical tool that deals with this characteristic variability in properties is the Weibull distribution. The present work investigates the influence of the testing gage length on the strength, Young's modulus and Weibull modulus of carbon fibres and glass fibres. The Young's modulus is calculated by two methods: (i ASTM D 3379M, and (ii interaction between testing equipment/specimen The first method resulted in a Young modulus of 183 GPa for carbon fibre, and 76 GPa for glass fibre. The second method gave a Young modulus of 250 GPa for carbon fibre and 50 GPa for glass fibre. These differences revelead differences on how the interaction specimen/testing machine can interfere in the Young modulus calculations. Weibull modulus can be a tool to evaluate the fibre's homogeneity in terms of properties and it is a good quality control parameter during processing. In the range of specimen gage length tested the Weibull modulus for carbon fibre is ~ 3.30 and for glass fibres is ~ 5.65, which indicates that for the batch of fibres tested, the glass fibre is more uniform in properties.

Application of Advanced Technology to Improve Plant Performance in Nuclear Power Plants

International Nuclear Information System (INIS)

Hashemian, H.M.

2011-01-01

Advances in computer technologies, signal processing, analytical modeling, and the advent of wireless sensors have provided the nuclear industry with ample means to automate and optimize maintenance activities and improve safety, efficiency, and availability, while reducing costs and radiation exposure to maintenance personnel. This paper provides a review of these developments and presents examples of their use in the nuclear power industry and the financial and safety benefits that they have produced. As the current generation of nuclear power plants have passed their mid-life, increased monitoring of their health is critical to their safe operation. This is especially true now that license renewal of nuclear power plants has accelerated, allowing some plants to operate up to 60 years or more. Furthermore, many utilities are maximizing their power output through uprating projects and retrofits. This puts additional demand and more stress on the plant equipment such as the instrumentation and control (I and C) systems and the reactor internal components making them more vulnerable to the effects of aging, degradation, and failure. In the meantime, the nuclear power industry is working to reduce generation costs by adopting condition-based maintenance strategies and automation of testing activities. These developments have stimulated great interest in on-line monitoring (OLM) technologies and new diagnostic and prognostic methods to anticipate, identify, and resolve equipment and process problems and ensure plant safety, efficiency, and immunity to accidents. The foundation for much of the required technologies has already been established through 40 years of research and development (R and D) efforts performed by numerous organizations, scientists, and engineers around the world including the author. This paper provides examples of these technologies and demonstrates how the gap between some of the more important R and D efforts and end users have been filled

Improvement of information on the nuclear energy health effects, the aim of win Slovakia

International Nuclear Information System (INIS)

Petrasova, M.; Nikodemova, D.

1998-01-01

International organisation WIN Global and national organisation WIN Slovakia which as a section of Slovak Nuclear Society, offer unique opportunities for the improvement of radiation risk communication. WIN Global was established in 1993 and currently has about 600 members in 39 countries. WIN Slovakia was established in the end of 1997 and has 20 members. WIN Slovakia is the association of women working professionally in the fields of nuclear energy and application of radiation and willing to devote time to public information. Members of WIN Slovakia all have one thing in common: They want the general public to have a better understanding of nuclear and radiation matter. The members of WIN Slovakia would like and plane to make presentations, discuss and give information material on subjects as: energy and sustainable development; radiation, radioactivity, and health effects; medical applications, radiation protection; nuclear energy, uranium mining; nuclear power plants and their safety; radioactive waste; nuclear and environment; natural radiation, radon. In 1996-1997 a comparative risk perception study was carried out in Slovak Republic. Real data were collected through the administration of a questionnaires distributed among a group of 14-17 years old children (N 1 = 308) and teenagers (N 2 = 150). The list of 44 items covered a wide range of risks and hazards, including risks from technology (nuclear power plants, water-dams etc.) pollution (air-, water-, soil, waste management) nature (floods, fire, etc.), life style (smoking, drugs, alcohol abuse) and society (crime, conflicts, war, terror etc.). The questionnaire contains the questions about the sources of risk information. The topic of the study was the self assessment of the knowledge on particular risks too. The results were summarised

National Options for a Sustainable Nuclear Energy System: MCDM Evaluation Using an Improved Integrated Weighting Approach

Directory of Open Access Journals (Sweden)

Ruxing Gao

2017-12-01

Full Text Available While the prospects look bright for nuclear energy development in China, no consensus about an optimum transitional path towards sustainability of the nuclear fuel cycle has been achieved. Herein, we present a preliminary study of decision making for China’s future nuclear energy systems, combined with a dynamic analysis model. In terms of sustainability assessment based on environmental, economic, and social considerations, we compared and ranked the four candidate options of nuclear fuel cycles combined with an integrated evaluation analysis using the Multi-Criteria Decision Making (MCDM method. An improved integrated weighting method was first applied in the nuclear fuel cycle evaluation study. This method synthesizes diverse subjective/objective weighting methods to evaluate conflicting criteria among the competing decision makers at different levels of expertise and experience. The results suggest that the fuel cycle option of direct recycling of spent fuel through fast reactors is the most competitive candidate, while the fuel cycle option of direct disposal of all spent fuel without recycling is the least attractive for China, from a sustainability perspective. In summary, this study provided a well-informed decision-making tool to support the development of national nuclear energy strategies.

Improving performance of high risk organizations Spanish nuclear sector from the analysis of organizational culture factors

International Nuclear Information System (INIS)

La Salabarnada, E.; German, S.; Silla, I.; Navajas, J.

2012-01-01

This paper presents the research project funded by UNESA and conducted by the CISOT-CIEMAT that aims to contribute to improving the operating performance of the Spanish nuclear power plants. This paper aims to identify the factors and key organizational processes to improve efficiency, in order to advance knowledge about the influence of organizational culture on the safety of high reliability organizations.

Legal measures for improving public acceptance of nuclear plants

International Nuclear Information System (INIS)

Marti de Veses y Puig, J.J.

1983-01-01

The author of this paper considers that public acceptance of nuclear projects would be greatly enhanced by appropriate information on topics concerning safety of nuclear installations supplied through specialised institutions set up by the governments. In this context the author refers to the 1980 Spanish Act setting up the Nuclear Safety Council, one of whose tasks is to inform the public, and finally, the 1981 Act establishing a specific tax on electrical generation, including nuclear electricity. (NEA) [fr

Flight Test Results from the Rake Airflow Gage Experiment on the F-15B Airplane

Science.gov (United States)

Frederick, Michael A.; Ratnayake, Nalin A.

2011-01-01

The Rake Airflow Gage Experiment involves a flow-field survey rake that was flown on the Propulsion Flight Test Fixture at the NASA Dryden Flight Research Center using the Dryden F-15B research test bed airplane. The objective of this flight test was to ascertain the flow-field angularity, local Mach number profile, total pressure distortion, and dynamic pressure at the aerodynamic interface plane of the Channeled Centerbody Inlet Experiment. This new mixed-compression, supersonic inlet is planned for flight test in the near term. Knowledge of the flow-field characteristics at this location underneath the airplane is essential to flight test planning and computational modeling of the new inlet, anairplane, flying at a free-stream Mach number of 1.65 and a pressure altitude of 40,000 ft, would achieve the desired local Mach number for the future inlet flight test. Interface plane distortion levels of 2 percent and a local angle of attack of -2 deg were observed at this condition. Alternative flight conditions for future testing and an exploration of certain anomalous data also are provided.

Improvements and standardization of communication means for control room personnel in nuclear power plants

International Nuclear Information System (INIS)

Preuss, W.; Eggerdinger, C.; Sieber, R.

1982-01-01

This report describes the findings of an investigation into selected communication means for control room personnel in nuclear power stations. The study can be seen as a contribution to the systematic analysis of major problem areas which were identified in the general study 'Human factors in the nuclear power plant'. The subjects under investigation were the 'Shift book', 'Simulation book', and 'Technical and organisational changes and their records'. It was intended to analyse both the communication, processes and the associated written documentation in order to determine areas for potential improvement and possibilities for standardization. Information was obtained by interviewing shift members and their supervisors, by general observation, and by compilation and evaluation of the extensive dokumentation. Assessment criteria were developed on a scientific basis and in the course of the investigation, in particular from ergonomic findings, as well as from standards and regulations and comparison between the plants. General practical suggestions were developed for the improvement of the communication forms and the formal design of the documents and their contents. The transfer of the recommendations to practical use in the plants presupposes the consideration of plant-specific frames of reference. The report includes a compilation and listing of suggestions for improvement in topical subdivisions. (orig.) [de

The continuous improvement system of nuclear power plant of Laguna Verde; El sistema de mejora continua de la central nucleoelectrica Laguna Verde

Energy Technology Data Exchange (ETDEWEB)

Rivera C, A. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Km. 42.5 Cardel-Nautla, Veracruz (Mexico)], e-mail: arr99999@cfe.gob.mx

2009-10-15

This paper describes the continuous improvement system of nuclear power plant of Laguna Verde and the achievements in implementing the same and additionally two study cases are presents. In February 2009 is noteworthy because the World Association of Nuclear Operators we identified as a learning organization, qualification which shows that the continuous improvement system has matured, and this system will expose as I get to learn to capitalize on our own experiences and external experiences diffused by the nuclear industry. In 2007 the management of nuclear power plants integrates its improvement systems and calls it continuous improvement system and is presented in the same extensive report that won the National Quality Award. This system is made up of 5 subsystems operating individually and are also related 1) human performance; 2) referential comparison or benchmarking; 3) self-assessment; 4) corrective action and 5) external operating experience. Five subsystems that plan, generate, capture, manage, communicate and protect the knowledge generated during the processes execution of nuclear power plant of Laguna Verde, as well as from external sources. The target set in 2007 was to increase the intellectual capital to always give response to meeting the security requirements, but creating a higher value to quality, customer, environment protection and society. In brief each of them, highlighting the objective, expectations management, implementation and some benefits. At the end they will describe two study cases selected to illustrate these cases as the organization learns by their continuous improvement system. (Author)

Improvements around nuclear power plants for effective implementation of emergency countermeasures

International Nuclear Information System (INIS)

Srivasista, K.; Ravi, K.; Gupta, S.K.

2011-01-01

The 5 km sterilized zone (SZ) and 16 km emergency planning zone (EPZ) were set up for Indian nuclear power plants in 1960s. There is also a requirement that the growth of population in SZ shall be controlled. In the current scenario where population growth in SZ at some of the sites is much above the natural growth, the distinction between the two zones may disappear. It is clear that emergency preparedness plans shall be in place for these zones. In today's context if these numbers have to be revised, there is a need to give a fresh look to the basis and growth of population in these zones. In view of this, the issue of size and requirement of SZ and EPZ in Indian context are revisited. Technological advances and emerging improvements in some of the elements of emergency response were reviewed to determine their potential effects on decisions of emergency protective actions. Some such elements which affect implementation of emergency countermeasures effectively in SZ and EPZ around Indian nuclear power plants are discussed in this paper. (author)

Nuclear power plant life time improvement and management program in Korea

International Nuclear Information System (INIS)

Sung Yull Hong; Ill Seok Jeong; Taek Ho Song

1995-01-01

Korea Electric Power Research Institute (KEPRI) of Korea Electric Power Corporation (KEPCO) has performed a lifetime management of nuclear power plant program (LMNPP), ''Nuclear Power Plant Lifetime Management (PLIM) (I)'', since November 1993, which is a feasibility study of the Kori Unit 1 lifetime management including aging evaluation of the thirteen major components. The results of the PLIM(I) will provide information which is necessary for decision making of the Kori Unit 1 lifetime improvement. A plan of the work scope and schedule for the next phase, PLIM(II), will also be provided by this project. This paper introduced KEPRI's basic strategy of LMNPP, PLIM organization, current status, some interim results of the PLIM(I), and other related programs in Korea. So far, we have done field data survey, systems/structures screening, components prioritization, lifetime evaluation methodology study, and fracture mechanics tests of the Kori Unit 1 reactor pressure vessel surveillance coupons. Currently life assessment of the major components and PLIM economic evaluation of Kori Unit 1 are under way. (author)

Digital-image processing improves man-machine communication at a nuclear reactor

International Nuclear Information System (INIS)

Cook, S.A.; Harrington, T.P.; Toffer, H.

1982-01-01

The application of digital image processing to improve man-machine communication in a nuclear reactor control room is illustrated. At the Hanford N Reactor, operated by UNC Nuclear Industries for the United States Department of Energy, in Richland, Washington, digital image processing is applied to flow, temperature, and tube power data. Color displays are used to present the data in a clear and concise fashion. Specific examples are used to demonstrate the capabilities and benefits of digital image processing of reactor data. N Reactor flow and power maps for routine reactor operations and for perturbed reactor conditions are displayed. The advantages of difference mapping are demonstrated. Image processing techniques have also been applied to results of analytical reactor models; two examples are shown. The potential of combining experimental and analytical information with digital image processing to produce predictive and adaptive reactor core models is discussed. The applications demonstrate that digital image processing can provide new more effective ways for control room personnel to assess reactor status, to locate problems and explore corrective actions. 10 figures

Proceedings of the workshop on better nuclear plant maintenance: improving human and organisational performance

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-04-05

A significant proportion of nuclear plant events is attributable to failures that take place during maintenance and periodic testing. Human and organisational factors are frequently identified as making a major contribution to these events. Despite this recognition, licensee and regulatory oversight in the human and organisational area has tended to focus more on operational matters than maintenance. Owing to the importance of human and organisational performance on nuclear plant maintenance, the CSNI Special Experts' Group on Human and Organisational Factors (SEGHOF) hosted a workshop entitled 'Better nuclear plant maintenance: improving human and organisational performance'. The workshop provided an international forum for staff from nuclear plants, research bodies, and regulators to discuss human and organisational challenges to maintenance, and initiatives to support effective performance. Over 60 participants from about 20 countries participated. The workshop was divided into five sessions: 1) International guidance to improve maintenance performance; 2) Lessons learned through maintenance operating experience; 3) Licensee initiatives to support reliable maintenance; 4) Regulatory approaches to assuring effective licensee maintenance; and 5) Recent trends and their impact on maintenance. Sessions commenced with oral presentations of papers followed by break-out and plenary discussions. Session 4 on regulatory approaches included short presentations from ten regulatory bodies and was followed by discussion comparing these approaches. The main findings of the workshop concern: the retirements of experienced staff; the increasing use of contractors to perform maintenance activities; the use of skill-broadening in maintenance; the role of supervisors at the plant level; the organisational changes that are used to optimise the use of plant staff resources; the effective planning of maintenance tasks; the time allowed to complete maintenance tasks; the development

Opinion on the radio-ecological monitoring of waters around nuclear installations and on the management of old nuclear waste warehousing sites: 18 recommendations to improve information, transparency and dialogue with involved parties

International Nuclear Information System (INIS)

2008-01-01

After a presentation of the different actors (agencies, institutions, companies) involved in the activities of the various French nuclear installations (base nuclear installations and those concerning the national defence), this report describes the radio-ecological monitoring performed around these nuclear sites: water surveillance on these sites and within their environment, regulatory requirements on effluents and surveillance, information provided by operators and by institutional organisations, assessment of the radio-ecological status of nuclear sites and of potential environmental and health impacts. It describes regulatory obligation in terms of public information, information and communication actions, and gives an assessment of the High committee about public information quality. It discusses ways to improve this quality for a higher transparency, to reinforce the role of local information commissions (CLI), and improve site monitoring. All these aspects are grouped in 18 recommendations

Nuclear and related techniques for improving productivity of indigenous animals in harsh environments

International Nuclear Information System (INIS)

1986-01-01

The seminar provided a forum to review the various ways by which nuclear and related methods can be used to improve animal nutrition, reproduction and disease control under the different ecological conditions prevailing in Africa and the Middle East. The seminar was held concurrently with an FAO/IAEA Advisory Group Meeting. The purpose of this meeting was for invited scientists from various disciplines to evaluate those nuclear and related techniques currently used to quantify such functions as animal adaptation, digestion and utilization of poor quality feedstuffs, reproductive efficiency and resistance to disease and other forms of stress. This volume contains a selection of the papers presented during the seminar as well as the Recommendations of the Advisory Group Meeting. Separate abstracts were prepared for 15 papers of this volume

Welcome Address by H. Liu [4. International Conference on Effective Nuclear Regulatory Systems: Sustaining Improvements Globally, Vienna (Austria), 11-15 April 2016

International Nuclear Information System (INIS)

Liu, H.

2017-01-01

In his opening remarks, Mr. Liu Hua, the President of the conference, noted that the presence of so many attendees at the conference indicated a high level of interest in effective nuclear regulation. He added that effective regulatory systems are very important in maintaining and improving global nuclear safety, and that the first conference on this topic, held ten years ago, created a valuable platform for achieving that goal. In the intervening decade, through the conferences held in Moscow, Cape Town, Ottawa and Vienna, the importance of effective regulation has become more widely recognized and key elements, including independence, transparency, openness, competence and wider international cooperation, have been identified. Mr. Liu Hua pointed to specific actions proposed for governments, regulatory bodies and stakeholders, and highlighted that many of the actions had already achieved fruitful outcomes. He also noted that many lessons had been learned and many improvements had been made in the light of the Fukushima Daiichi accident: 1. To further improve government infrastructure; 2. To further improve nuclear safety standards; 3. To further develop regulation capacity building and human resource; 4. To further enhance knowledge and experience management and transition, 5. To further foster and strengthen nuclear safety culture; 6. To further improve and rebuild public confidence

National symposium: nuclear technique in industry, medicine, agriculture and environment protection. Abstracts of papers; Krajowe sympozjum: technika jadrowa w przemysle, medycynie, rolnictwie i ochronie srodowiska. Streszczenia referatow

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

The National Symposium `Nuclear Techniques in Industry, Medicine, Agriculture and Environment Protection` has been held in Rynia near Warsaw from 24 to 27 April 1995. Totally 94 lectures have been presented. The actual state of art in Polish investigations have been shown in all branches of applied nuclear sciences. The plenary session devoted to general topics has began the symposium. Further conference has been divided into 18 subject sessions. There were: (1) radiation technologies in environment protection; (2) radiation technologies in materials engineering; (3) radiation preservation in food; (4) radiation techniques for medical use; (5) radiotracers in industrial investigations; (6) radiotracers in water and sewage management and leak control; (7) tracers in hydrology; (8) radiotracers in materials testing; (9) instruments for environment protection, (10) radiometric industrial gages; (11) diagnostic and testing instruments; (12) application of nuclear techniques in materials testing; (13) applications of nuclear techniques in geology and hydrogeology; (14) radioanalytical methods; (15) radiation detectors; (16) radiation measurements; (17) data processing from radiometric experiments; (18) accelerators, isotopes manufacturing, INIS.

National symposium: nuclear technique in industry, medicine, agriculture and environment protection. Abstracts of papers; Krajowe sympozjum: technika jadrowa w przemysle, medycynie, rolnictwie i ochronie srodowiska. Streszczenia referatow

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-31

The National Symposium `Nuclear Techniques in Industry, Medicine, Agriculture and Environment Protection` has been held in Rynia near Warsaw from 24 to 27 April 1995. Totally 94 lectures have been presented. The actual state of art in Polish investigations have been shown in all branches of applied nuclear sciences. The plenary session devoted to general topics has began the symposium. Further conference has been divided into 18 subject sessions. There were: (1) radiation technologies in environment protection; (2) radiation technologies in materials engineering; (3) radiation preservation in food; (4) radiation techniques for medical use; (5) radiotracers in industrial investigations; (6) radiotracers in water and sewage management and leak control; (7) tracers in hydrology; (8) radiotracers in materials testing; (9) instruments for environment protection, (10) radiometric industrial gages; (11) diagnostic and testing instruments; (12) application of nuclear techniques in materials testing; (13) applications of nuclear techniques in geology and hydrogeology; (14) radioanalytical methods; (15) radiation detectors; (16) radiation measurements; (17) data processing from radiometric experiments; (18) accelerators, isotopes manufacturing, INIS.

Improvement and rationalization of nuclear energy laws and regulations

International Nuclear Information System (INIS)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chum; Kim, Hak Man; Oh, Ho Chul

2002-03-01

Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea

Improvement and rationalization of nuclear energy laws and regulations

Energy Technology Data Exchange (ETDEWEB)

Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul [Cheongju Univ., Cheongju (Korea, Republic of)

2001-03-15

Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea.

Improvement and rationalization of nuclear energy laws and regulations

Energy Technology Data Exchange (ETDEWEB)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chum; Kim, Hak Man; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

2002-03-15

Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea.

Development and Operation of the nuclear technology program for improving the public acceptance by providing the right information

Energy Technology Data Exchange (ETDEWEB)

Lee, Juwoon; Kang, Mincheol; Min, Sangky; Yi, Jongmin; Yi, Yunyoung

2013-11-15

This detailed assignment conducted to improve the communication efficiency through the operation of differentiated programs to accomplish 'Establishment of knowledge diffusion system for improvement of Nuclear understanding', which is the purpose of the general assignment. We developed the programs on each social opinion leader groups by providing the right information on nuclear(radiation) technology, and had a forum for providing the right information on each social groups. Also, Consisted the consultant group, which participates humanities and social sciences, civic group, science teachers, the press, national assembly workers. Technology PR was performed 4 times, which is 1 time more than the original plan of 4 times. In the theme of affection of radiation, we broadened the vision of various fields which enabled to approach in general for the PR program. We Induced a positive reaction from the participants in political areas which coexistent of uncertain expectation and difficult vision of nuclear and radiation, by sharing the development possibility in relation with potential values of radiation industry and other industries and delivering accurate information, not a fragmentary knowledge, but in general. We hope that this results will contribute to establishing the effective nuclear knowledge diffusion program system.

Development and Operation of the nuclear technology program for improving the public acceptance by providing the right information

International Nuclear Information System (INIS)

Lee, Juwoon; Kang, Mincheol; Min, Sangky; Yi, Jongmin; Yi, Yunyoung

2013-11-01

This detailed assignment conducted to improve the communication efficiency through the operation of differentiated programs to accomplish 'Establishment of knowledge diffusion system for improvement of Nuclear understanding', which is the purpose of the general assignment. We developed the programs on each social opinion leader groups by providing the right information on nuclear(radiation) technology, and had a forum for providing the right information on each social groups. Also, Consisted the consultant group, which participates humanities and social sciences, civic group, science teachers, the press, national assembly workers. Technology PR was performed 4 times, which is 1 time more than the original plan of 4 times. In the theme of affection of radiation, we broadened the vision of various fields which enabled to approach in general for the PR program. We Induced a positive reaction from the participants in political areas which coexistent of uncertain expectation and difficult vision of nuclear and radiation, by sharing the development possibility in relation with potential values of radiation industry and other industries and delivering accurate information, not a fragmentary knowledge, but in general. We hope that this results will contribute to establishing the effective nuclear knowledge diffusion program system

Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files. SG39 meeting, November 2014

International Nuclear Information System (INIS)

Aufiero, Manuele; Ivanov, Evgeny; Hoefer, Axel; Yokoyama, Kenji; Da Cruz, Dirceu Ferreira; KODELI, Ivan-Alexander; Hursin, Mathieu; Pelloni, Sandro; Palmiotti, Giuseppe; Salvatores, Massimo; Barnes, Andrew; Cabellos De Francisco, Oscar; ); Ivanova, Tatiana; )

2014-11-01

The aim of WPEC subgroup 39 'Methods and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files' is to provide criteria and practical approaches to use effectively the results of sensitivity analyses and cross section adjustments for feedback to evaluators and differential measurement experimentalists in order to improve the knowledge of neutron cross sections, uncertainties, and correlations to be used in a wide range of applications. This document is the proceedings of the third formal Subgroup meeting held at the NEA, Issy-les-Moulineaux, France, on 27-28 November 2014. It comprises a Summary Record of the meeting and all the available presentations (slides) given by the participants: A - Sensitivity methods: 1 - Perturbation/sensitivity calculations with Serpent (M. Aufiero); 2 - Comparison of deterministic and Monte Carlo sensitivity analysis of SNEAK-7A and FLATTOP-Pu Benchmarks (I. Kodeli); B - Integral experiments: 1 - PROTEUS experiments: selected experiments sensitivity profiles and availability, (M. Hursin, M. Salvatores - PROTEUS Experiments, HCLWR configurations); 2 - SINBAD Benchmark Database and FNS/JAEA Liquid Oxygen TOF Experiment Analysis (I. Kodeli); 3 - STEK experiment Opportunity for Validation of Fission Products Nuclear Data (D. Da Cruz); 4 - SEG (tailored adjoint flux shapes) (M. Savatores - comments) 5 - IPPE transmission experiments (Fe, 238 U) (T. Ivanova); 6 - RPI semi-integral (Fe, 238 U) (G. Palmiotti - comments); 7 - New experiments, e.g. in connection with the new NSC Expert Group on 'Improvement of Integral Experiments Data for Minor Actinide Management' (G. Palmiotti - Some comments from the Expert Group) 8 - Additional PSI adjustment studies accounting for nonlinearity (S. Pelloni); 9 - Adjustment methodology issues (G. Palmiotti); C - Am-241 and fission product issues: 1 - Am-241 validation for criticality-safety calculations (A. Barnes - Visio

Using operating experience and a cause coding tree to identify improvements for nuclear process control

International Nuclear Information System (INIS)

Paradies, M.W.; Busch, D.A.

1987-01-01

This paper outlines a systematic approach to identification of the root causes of incidents and the use of that information to improve nuclear plant process control. The paper describes how the system was developed, how the system is used, and how the system has been accepted

Improvements to the nuclear model code GNASH for cross section calculations at higher energies

International Nuclear Information System (INIS)

Young, P.G.; Chadwick, M.B.

1994-01-01

The nuclear model code GNASH, which in the past has been used predominantly for incident particle energies below 20 MeV, has been modified extensively for calculations at higher energies. The model extensions and improvements are described in this paper, and their significance is illustrated by comparing calculations with experimental data for incident energies up to 160 MeV

Availability Improvement Program for Louisiana Power and Light's Waterford 3 Nuclear Power Plant

International Nuclear Information System (INIS)

Simoneaux, G.E.

1985-01-01

The Middle South Utilities System (MSUS) began an Availability Improvement Program (AIP) in the late nineteen-seventies for the benefit of all the operating units making up the System. This paper describes the methodology that is being employed in implementing a formal Avalability Improvement Program for a new nuclear unit known as Waterford 3. The tasks needed to install and maintain the AIP at Waterford 3 are discussed in terms of Analytical Methodology, Avalability Data System, and Plant Imvolvement. In particular, the AIP will provide: Management reporting; External reporting; A self-sufficient core of trained avalability personnel; Procedures and methodologies to monitor plant availability and to analyze availability problems

Improving Farming With Nuclear Techniques

International Nuclear Information System (INIS)

Henriques, Sasha

2011-01-01

Soil erosion, land degradation, the excessive or inappropriate use of fertilisers in agriculture and poor water quality are threats to the environment and hamper development. IAEA projects apply nuclear technology to evaluate these risks and find ways to make better use of water and soil resources. Many countries have benefited from this programme, including Qatar, Chile, Kenya, Turkey, Vietnam and Bangladesh.

Use of collaboration software to improve nuclear power plant outage management

Energy Technology Data Exchange (ETDEWEB)

Germain, Shawn

2015-02-01

Nuclear Power Plant (NPP) refueling outages create some of the most challenging activities the utilities face in both tracking and coordinating thousands of activities in a short period of time. Other challenges, including nuclear safety concerns arising from atypical system configurations and resource allocation issues, can create delays and schedule overruns, driving up outage costs. Today the majority of the outage communication is done using processes that do not take advantage of advances in modern technologies that enable enhanced communication, collaboration and information sharing. Some of the common practices include: runners that deliver paper-based requests for approval, radios, telephones, desktop computers, daily schedule printouts, and static whiteboards that are used to display information. Many gains have been made to reduce the challenges facing outage coordinators; however; new opportunities can be realized by utilizing modern technological advancements in communication and information tools that can enhance the collective situational awareness of plant personnel leading to improved decision-making. Ongoing research as part of the Light Water Reactor Sustainability Program (LWRS) has been targeting NPP outage improvement. As part of this research, various applications of collaborative software have been demonstrated through pilot project utility partnerships. Collaboration software can be utilized as part of the larger concept of Computer-Supported Cooperative Work (CSCW). Collaborative software can be used for emergent issue resolution, Outage Control Center (OCC) displays, and schedule monitoring. Use of collaboration software enables outage staff and subject matter experts (SMEs) to view and update critical outage information from any location on site or off.

International effects on safety and performance improvement for increasing the share of nuclear power in supply of the world energy demand

International Nuclear Information System (INIS)

Rouhanifard, A.; Hosseini Toudeshki, S.

2008-01-01

Perhaps the biggest challenge in launching atomic energy projects will be common public perception that it is a dangerous energy source. In fact, there have only ever been two nuclear accidents - one was Chernobyl (Ukraine) and the other was Three Mile Island (US) where there was an encased explosion and no one was hurt. Undoubtedly, and for good reason, it has had a lasting negative effect on public opinion over the safety of nuclear energy. However, the technology behind nuclear energy has improved in recent years. People have to be aware that new nuclear is not old nuclear. Nuclear is a safe technology and plants are much safer now. In terms of air pollution, developing a nuclear power program can actually have a positive effect on the environment. So today, two thirds of the world's population live in an environment where nuclear power plants are an essential part of energy production and industrial infrastructure. World countries are moving steadily forward with plans for much expanded role of nuclear energy. Efficiency of nuclear generation has increased dramatically over thc last decades. Lessons learned from accidents, advances in nuclear technology and implementation of projects for design of future safer and more economical nuclear reactors, will lead to grow of installed global nuclear capacity from about 369 G We net at the beginning of 2005 to about 553 G We net by 2025. In this paper, we present the results of a study on international efforts to improve safety of nuclear power plants. We focus on the current state of technology and the technology which will be employed for future built reactors to strengthen the role of nuclear power plants for supply of electrical energy in next decades. Finally, based on our studies on past, present and future of the world nuclear technology, we mention the issues to be taken into consideration while preparing the program for development of nuclear power plants in Iran

Improvements in liquid metal cooled nuclear reactors

International Nuclear Information System (INIS)

Barnes, S.

1980-01-01

Improvements in the design of the thermally insulating material used to shield the concrete containment walls in liquid metal cooled nuclear reactors are described in detail. The insulating material is composed of two layers and is placed between the primary vessel (usually steel) and the steel lined concrete containment vault. The outer layer, which clads the inner wall surface of the vault, is generally impervious to liquid metal coolant whilst the inner layer is pervious to the coolant. In normal operation, both layers protect the concrete from heat radiated from the reactor. In the event of a breach of the containment vessel, the resulting leakage of liquid metal coolant permeates the inner layer of insulating material, provides a means of heat transfer by conduction and hence reduces the overall insulating properties of the two layers. The outer layer continues to protect the wall surface of the vault from substantial direct contact with the liquid metal. Thus the two apparently conflicting requirements of good thermal insulation during normal operation and of heat transfer during loss of coolant accidents are satisfied by this novel design. Suggestions are given for possible materials for use as the insulating layers. (U.K.)

Improving activity transport models for water-cooled nuclear power reactors

Energy Technology Data Exchange (ETDEWEB)

Burrill, K.A

2001-08-01

Eight current models for describing radioactivity transport and radiation field growth around water-cooled nuclear power reactors have been reviewed and assessed. A frequent failing of the models is the arbitrary nature of the determination of the important processes. Nearly all modelers agree that the kinetics of deposition and release of both dissolved and particulate material must be described. Plant data must be used to guide the selection and development of suitable improved models, with a minimum of empirically-based rate constraints being used. Limiting case modelling based on experimental data is suggested as a way to simplify current models and remove their subjectivity. Improved models must consider the recent change to 'coordinated water chemistry' that appears to produce normal solubility behaviour for dissolved iron throughout the fuel cycle in PWRs, but retrograde solubility remains for dissolved nickel. Profiles are suggested for dissolved iron and nickel concentrations around the heat transport system in CANDU reactors, which operate nominally at constant chemistry, i.e., pH{sub T} constant with time, and which use carbon steel isothermal piping. These diagrams are modified for a CANDU reactor with stainless steel piping, in order to show the changes expected. The significance of these profiles for transport in PWRs is discussed for further model improvement. (author)

Footprints of phineas gage: Historical beginnings on the origins of brain and behavior and the birth of cerebral localizationism

Directory of Open Access Journals (Sweden)

Bhaskara P Shelley

2016-01-01

Full Text Available The intellectual revolution led by ancient Greek philosophers and physicians witnessed the extraordinary evolution of the birth of neuroscience from speculations of cardiocentrism (Aristotelism and encephalocentrism (Galenism. Later further development of neurosciences was hallmarked by the development of anatomic theories of phrenology by the German physician Franz Joseph Gall in 1796. Although phrenology was a pseudoscience, it was Gall who laid the foundations for the subsequent biologically based doctrine of brain behavior localization. The amazing story of Phineas Gage is a classic case in the nineteenth-century neurosciences literature that played a pivotal role in the concept of cerebral localizationism, a theory that moved beyond phrenology. This iconic case marked the historical beginnings of brain origins of human behavior and elucidated a link between brain trauma, prefrontal brain damage and personality change.

Optimization and improvement of the technical specifications for Santa Maria de Garona and Cofrentes nuclear power plants

International Nuclear Information System (INIS)

Norte Gomez, M.D.; Alcantud, F.; Hoyo, C. del

1993-01-01

Technical Specifications (TS) form one of the basic documents necessary for licensing nuclear power plants and are required by the Government in accordance with Article 26 of the Regulation for Nuclear and Radioactive Facilities. They contain specific plant characteristics and operating limits to provide adequate protection for the safety and health of operators and the general public. For operator actuation, TS include all the surveillance requirements and limiting operating conditions (operation at full power, startup, hot and cold shutdown, and refueling outage) of safety-related systems. They also include the conventional support systems which are necessary to keep the plant in a safe operating conditioner to bring it to safe shutdown in the event of incidents or hypothetical accidents. Because of the large volume of information contained in the TS, the NRC and American utility owners began to simplify and improve the initial standard TS, which has given way to the development of a TS Optimization Program in the USA under the auspices of the NRC. Empresarios Agrupados has been contracted by the BWR Spanish Owners' Group (GPE-BWR) to develop optimized TS for the Santa Maria de Garona and Cofrentes Nuclear Power Plants. The optimized and improved TS are simplified versions of the current ones and facilitate the work of plant operators. They help to prevent risks, and reduce the number of potential transients caused by the large number of tests required by current TS. Plant operational safety is enhanced and higher effective operation is achieved. The GPE-BWR has submitted the first part of the optimized TS with their corresponding Bases to the Spanish Nuclear Council (CSN), for comment and subsequent approval. Once the TS are approved by the Spanish Nuclear Council, the operators of the Santa Maria de Garona and Cofrentes Nuclear Power Plants will be given a training and adaptation course prior to their implementation. (author)

Nuclear performance and reliability

International Nuclear Information System (INIS)

Rothwell, G.

1993-01-01

If fewer forced outages are a sign of improved safety, nuclear power plants have become safer and more productive. There has been a significant improvement in nuclear power plant performance, due largely to a decline in the forced outage rate and a dramatic drop in the average number of forced outages per fuel cycle. If fewer forced outages are a sign of improved safety, nuclear power plants have become safer and more productive over time. To encourage further increases in performance, regulatory incentive schemes should reward reactor operators for improved reliability and safety, as well as for improved performance

Improving quality and the assurance of quality in the design and construction of nuclear power plants: a report to Congress

International Nuclear Information System (INIS)

Altman, W.; Ankrum, T.; Brach, W.

1984-05-01

A study was conducted of existing and alternative programs for improving quality and the assurance of quality in the design and construction of commercial nuclear power plants. A primary focus of the study was to determine the underlying causes of major quality-related problems in the construction of some nuclear power plants and the untimely detection and correction of these problems. The study concluded that the root cause for major quality-related problems was the failure or inability of some utility managements to effectively implement a management system that ensured adequate control over all aspects of the project. These management shortcoming arose in part from inexperience on the part of some project teams in the construction of nuclear power plants. NRC's past licensing and inspection practices did not adequately screen construction permit applicants for overall capability to manage or provide effective management oversight over the construction project. The study recommends a number of improvements in industry and NRC programs. For industry, the study recommends self-imposed rising standards of excellence, treatment of quality assurance as a management tool, not a substitute for management, improved trend analysis and identification of root causes of quality problems, and a program of comprehensive third party audits of present and future construction projects. To improve NRC programs, the study recommends a heavier emphasis on team inspections and resident inspectors, an enhanced review of new applicant's capabilities to construct commercial nuclear power plants, more attention to management issues, improved diagnostic and trending capabilities, improved quality and quality assurance for operating reactors, and development of guidance to facilitate the prioritization of quality assurance measures commensurate with the importance of plant structures, systems, and components to the achievement of safety

Improved Nuclear Reactor and Shield Mass Model for Space Applications

Science.gov (United States)

Robb, Kevin

2004-01-01

New technologies are being developed to explore the distant reaches of the solar system. Beyond Mars, solar energy is inadequate to power advanced scientific instruments. One technology that can meet the energy requirements is the space nuclear reactor. The nuclear reactor is used as a heat source for which a heat-to-electricity conversion system is needed. Examples of such conversion systems are the Brayton, Rankine, and Stirling cycles. Since launch cost is proportional to the amount of mass to lift, mass is always a concern in designing spacecraft. Estimations of system masses are an important part in determining the feasibility of a design. I worked under Michael Barrett in the Thermal Energy Conversion Branch of the Power & Electric Propulsion Division. An in-house Closed Cycle Engine Program (CCEP) is used for the design and performance analysis of closed-Brayton-cycle energy conversion systems for space applications. This program also calculates the system mass including the heat source. CCEP uses the subroutine RSMASS, which has been updated to RSMASS-D, to estimate the mass of the reactor. RSMASS was developed in 1986 at Sandia National Laboratories to quickly estimate the mass of multi-megawatt nuclear reactors for space applications. In response to an emphasis for lower power reactors, RSMASS-D was developed in 1997 and is based off of the SP-100 liquid metal cooled reactor. The subroutine calculates the mass of reactor components such as the safety systems, instrumentation and control, radiation shield, structure, reflector, and core. The major improvements in RSMASS-D are that it uses higher fidelity calculations, is easier to use, and automatically optimizes the systems mass. RSMASS-D is accurate within 15% of actual data while RSMASS is only accurate within 50%. My goal this summer was to learn FORTRAN 77 programming language and update the CCEP program with the RSMASS-D model.

Nuclear disarmament and peaceful nuclear technology

International Nuclear Information System (INIS)

Taylor, T.B.

1989-01-01

According to the author, it remains to be seen whether nuclear disarmament can reduce the risks of nuclear war sufficiently for the residual risks to be acceptable to a majority of the world's population, while at the same time vigorous growth in the world's dependence on nuclear energy for peaceful purposes continues. This paper discusses how use of nuclear materials from dismantled weapons as fuel for peaceful purposes may help progress to be made towards that goal, by stimulating considerable improvements in the effectiveness of arrangements for preventing diversion of the materials from peaceful to military purposes, while at the same time eliminating large numbers of nuclear weapons

Nuclear Forensics' role in analyzing nuclear trafficking activities

International Nuclear Information System (INIS)

Hrnecek, E.; Mayer, K.; Schubert, A.; Wallenius, M.

2010-01-01

Nuclear forensics aims at identifying origin and intended use of nuclear material using information inherent to the nuclear material.The information gathered in nuclear forensics include isotopic composition, elemental composition, impurities and age of the material, macroscopic appearance and microstructure. The information so collected helps to solve criminal cases and put the individuals involved in nuclear trafficking in jails. The information also helps to improve safeguards and physical protection measures at place of theft or diversion to prevent future thefts or diversions.

Input/Output of ab-initio nuclear structure calculations for improved performance and portability

International Nuclear Information System (INIS)

Laghave, Nikhil

2010-01-01

Many modern scientific applications rely on highly computation intensive calculations. However, most applications do not concentrate as much on the role that input/output operations can play for improved performance and portability. Parallelizing input/output operations of large files can significantly improve the performance of parallel applications where sequential I/O is a bottleneck. A proper choice of I/O library also offers a scope for making input/output operations portable across different architectures. Thus, use of parallel I/O libraries for organizing I/O of large data files offers great scope in improving performance and portability of applications. In particular, sequential I/O has been identified as a bottleneck for the highly scalable MFDn (Many Fermion Dynamics for nuclear structure) code performing ab-initio nuclear structure calculations. We develop interfaces and parallel I/O procedures to use a well-known parallel I/O library in MFDn. As a result, we gain efficient I/O of large datasets along with their portability and ease of use in the down-stream processing. Even situations where the amount of data to be written is not huge, proper use of input/output operations can boost the performance of scientific applications. Application checkpointing offers enormous performance improvement and flexibility by doing a negligible amount of I/O to disk. Checkpointing saves and resumes application state in such a manner that in most cases the application is unaware that there has been an interruption to its execution. This helps in saving large amount of work that has been previously done and continue application execution. This small amount of I/O provides substantial time saving by offering restart/resume capability to applications. The need for checkpointing in optimization code NEWUOA has been identified and checkpoint/restart capability has been implemented in NEWUOA by using simple file I/O.

Surface Coatings as Xenon Diffusion Barriers for Improved Detection of Clandestine Nuclear Explosions

OpenAIRE

Bläckberg, Lisa

2014-01-01

This thesis investigates surface coatings as xenon diffusion barriers on plastic scintillators. The motivation for the work is improved radioxenon detection systems, used within the verification regime of the Comprehensive Nuclear-Test-Ban Treaty (CTBT). One type of radioxenon detection systems used in this context is the Swedish SAUNA system. This system uses a cylindrical plastic scintillator cell to measure the beta decay from radioxenon isotopes. The detector cell also acts as a container...

Evaluation of the residual stress field in a steam generator end tube after hydraulic expansion

International Nuclear Information System (INIS)

Thiel, F.; Kang, S.; Chabrerie, J.

1994-01-01

This paper presents a finite element elastoplastic model of a nuclear steam generator end tube, used to evaluate the residual stress field existing after hydraulic expansion of the tube into the tubesheet of the heat exchanger. This model has been tested against an experimental hydraulic expansion, carried out on full scale end tubes. The operation was monitored thanks to strain gages localized on the outer surface of the tubes, subjected to elastoplastic deformations. After a presentation of the expansion test and the description of the numerical model, the authors compare the stress fields issues from the gages and from the model. The comparison shows a good agreement. These results allow them to calculate the stress field resulting from normal operating conditions, while taking into account a correct initial state of stress. Therefore the authors can improve the understanding of the behavior of a steam generator end tube, with respect to stress corrosion cracking and crack growth

Nuclear power development

International Nuclear Information System (INIS)

Nealey, S.

1990-01-01

The objective of this study is to examine factors and prospects for a resumption in growth of nuclear power in the United States over the next decade. The focus of analysis on the likelihood that current efforts in the United States to develop improved and safer nuclear power reactors will provide a sound technical basis for improved acceptance of nuclear power, and contribute to a social/political climate more conducive to a resumption of nuclear power growth. The acceptability of nuclear power and advanced reactors to five social/political sectors in the U.S. is examined. Three sectors highly relevant to the prospects for a restart of nuclear power plant construction are the financial sector involved in financing nuclear power plant construction, the federal nuclear regulatory sector, and the national political sector. For this analysis, the general public are divided into two groups: those who are knowledgeable about and involved in nuclear power issues, the involved public, and the much larger body of the general public that is relatively uninvolved in the controversy over nuclear power

Nuclear data for nuclear reactor analyses

International Nuclear Information System (INIS)

Pearlstein, S.

1984-01-01

A discussion of nuclear data is presented emphasizing to what extent data are known and to what accuracy. The principal data of interest is that for neutron cross-sections. The changing status of data, evaluated nuclear data files and data validation and improvement are described. Although the discussion relates to nuclear data for reactor analysis may of the results also apply to fusion, accelerator, shielding, biomedical, space and defense studies. (U.K.)

Improved predictions of nuclear data: A continued challenge in astrophysics

International Nuclear Information System (INIS)

Goriely, S.

2001-01-01

Although important effort has been devoted in the last decades to measure reaction cross sections and decay half-lives of interest in astrophysics, most of the nuclear astrophysics applications still require the use of theoretical predictions to estimate experimentally unknown rates. The nuclear ingredients to the reaction or weak interaction models should preferentially be estimated from microscopic or semi-microscopic global predictions based on sound and reliable nuclear models which, in turn, can compete with more phenomenological highly-parametrized models in the reproduction of experimental data. The latest developments made in deriving the nuclear inputs of relevance in astrophysics applications are reviewed. It mainly concerns nuclear structure properties (atomic masses, deformations, radii, etc...), nuclear level densities, nucleon and α-optical potentials, γ-ray and Gamow-Teller strength functions

Crop improvement for salinity and drought tolerance using nuclear and related techniques (abstract)

International Nuclear Information System (INIS)

Serraj, R.; Lagoda, P.J.

2005-01-01

complex interactions among the traits involved in tolerance to both drought and salinity, pyramiding using marker-assisted breeding, induced mutation and other biotechnologies, combined with a multidisciplinary approach and the participation of farmers, is likely to provide the best strategy to accelerate the progress towards the development of adapted tolerant crop germplasm. The joint FAO/IAEA division is investing considerable effort in evaluating opportunities for using nuclear and related technologies to improve tolerance to abiotic stresses such as drought and salinity. The division has a long-standing experience in developing and coordinating collaborative research programs (CRP) on abiotic stresses, involving NARs in developing countries, international IARCs and expert scientists. Similarly, several technical cooperation projects (TCP) were carried out on crop improvement for tolerance to drought and salinity, at national, regional and interregional levels. The Soil and Biotechnology laboratories at Seibersdorf also have the experience and facilities for developing, testing and applying new isotope and nuclear-related techniques for the improvement of crop productivity and stress tolerance. An important project is currently being implemented by the joint FAO/IAEA division for the identification and development of crop germplasm with superior resource use efficiency and nutritional value and adapted to harsh environments. Two CRPs have been recently launched under this project dealing respectively with (i) the identification and pyramiding of mutated genes, and novel approaches for improving crop tolerance to salinity and drought, and (II) the selection for greater agronomic water-use efficiency in wheat and rice using carbon isotope discrimination under drought and saline environments. This paper will review the recent progress made at the joint FAO/IAEA division in deciphering the complexity of drought and salinity problems and developing drought and salt

Improved predictions of nuclear reaction rates for astrophysics applications with the TALYS reaction code

International Nuclear Information System (INIS)

Goriely, S.; Hilaire, S.; Koning, A.J.

2008-01-01

Nuclear reaction rates for astrophysics applications are traditionally determined on the basis of Hauser-Feshbach reaction codes, like MOST. These codes use simplified schemes to calculate the capture reaction cross section on a given target nucleus, not only in its ground state but also on the different thermally populated states of the stellar plasma at a given temperature. Such schemes include a number of approximations that have never been tested, such as an approximate width fluctuation correction, the neglect of delayed particle emission during the electromagnetic decay cascade or the absence of the pre-equilibrium contribution at increasing incident energies. New developments have been brought to the reaction code TALYS to estimate the Maxwellian-averaged reaction rates of astrophysics relevance. These new developments give us the possibility to calculate with an improved accuracy the reaction cross sections and the corresponding astrophysics rates. The TALYS predictions for the thermonuclear rates of astrophysics relevance are presented and compared with those obtained with the MOST code on the basis of the same nuclear ingredients for nuclear structure properties, optical model potential, nuclear level densities and γ-ray strength. It is shown that, in particular, the pre-equilibrium process significantly influences the astrophysics rates of exotic neutron-rich nuclei. The reciprocity theorem traditionally used in astrophysics to determine photo-rates is also shown no to be valid for exotic nuclei. The predictions obtained with different nuclear inputs are also analyzed to provide an estimate of the theoretical uncertainties still affecting the reaction rate prediction far away from the experimentally known regions. (authors)

Research on the improvement of nuclear safety -Improvement of level 1 PSA computer code package-

International Nuclear Information System (INIS)

Park, Chang Kyoo; Kim, Tae Woon; Kim, Kil Yoo; Han, Sang Hoon; Jung, Won Dae; Jang, Seung Chul; Yang, Joon Un; Choi, Yung; Sung, Tae Yong; Son, Yung Suk; Park, Won Suk; Jung, Kwang Sub; Kang Dae Il; Park, Jin Heui; Hwang, Mi Jung; Hah, Jae Joo

1995-07-01

This year is the third year of the Government-sponsored mid- and long-term nuclear power technology development project. The scope of this sub project titled on 'The improvement of level-1 PSA computer codes' is divided into three main activities : (1) Methodology development on the underdeveloped fields such as risk assessment technology for plant shutdown and low power situations, (2) Computer code package development for level-1 PSA, (3) Applications of new technologies to reactor safety assessment. At first, in this area of shutdown risk assessment technology development, plant outage experiences of domestic plants are reviewed and plant operating states (POS) are decided. A sample core damage frequency is estimated for over draining event in RCS low water inventory i.e. mid-loop operation. Human reliability analysis and thermal hydraulic support analysis are identified to be needed to reduce uncertainty. Two design improvement alternatives are evaluated using PSA technique for mid-loop operation situation: one is use of containment spray system as backup of shutdown cooling system and the other is installation of two independent level indication system. Procedure change is identified more preferable option to hardware modification in the core damage frequency point of view. Next, level-1 PSA code KIRAP is converted to PC-windows environment. For the improvement of efficiency in performing PSA, the fast cutest generation algorithm and an analytical technique for handling logical loop in fault tree modeling are developed. 48 figs, 15 tabs, 59 refs. (Author)

Research on the improvement of nuclear safety -Improvement of level 1 PSA computer code package-

Energy Technology Data Exchange (ETDEWEB)

Park, Chang Kyoo; Kim, Tae Woon; Kim, Kil Yoo; Han, Sang Hoon; Jung, Won Dae; Jang, Seung Chul; Yang, Joon Un; Choi, Yung; Sung, Tae Yong; Son, Yung Suk; Park, Won Suk; Jung, Kwang Sub; Kang Dae Il; Park, Jin Heui; Hwang, Mi Jung; Hah, Jae Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-07-01

This year is the third year of the Government-sponsored mid- and long-term nuclear power technology development project. The scope of this sub project titled on `The improvement of level-1 PSA computer codes` is divided into three main activities : (1) Methodology development on the underdeveloped fields such as risk assessment technology for plant shutdown and low power situations, (2) Computer code package development for level-1 PSA, (3) Applications of new technologies to reactor safety assessment. At first, in this area of shutdown risk assessment technology development, plant outage experiences of domestic plants are reviewed and plant operating states (POS) are decided. A sample core damage frequency is estimated for over draining event in RCS low water inventory i.e. mid-loop operation. Human reliability analysis and thermal hydraulic support analysis are identified to be needed to reduce uncertainty. Two design improvement alternatives are evaluated using PSA technique for mid-loop operation situation: one is use of containment spray system as backup of shutdown cooling system and the other is installation of two independent level indication system. Procedure change is identified more preferable option to hardware modification in the core damage frequency point of view. Next, level-1 PSA code KIRAP is converted to PC-windows environment. For the improvement of efficiency in performing PSA, the fast cutest generation algorithm and an analytical technique for handling logical loop in fault tree modeling are developed. 48 figs, 15 tabs, 59 refs. (Author).

Design requirements for new nuclear reactor facilities in Canada (focus on important improvements from RD-337 version 1 of 2008)

International Nuclear Information System (INIS)

Shim, S.; Harwood, C.; Ohn, M-Y; Liu, Y.C.; Young, T.

2014-01-01

The Canadian Nuclear Safety Commission (CNSC) has established the regulatory framework that includes the documentation of the requirements and guidance for each of CNSC's 14 Safety and Control Areas, one important area being the design of nuclear power plants (NPPs). For the design area, the CNSC published RD-337 version 1 Design of New Nuclear Power Plants in 2008. As such regulatory documents are reviewed on a regular basis, this document was recently updated as RD-337 version 2, and its guidance document GD-337, Guidance for the Design of New Nuclear Power Plants was developed to provide guidance on how to meet the requirements. REGDOC-2.5.2 Design of Reactor Facilities: Nuclear Power Plants that combines RD-337 version 2 and GD-337 version 1 was presented to the Commission on March 27, 2014 after two rounds of consultation with stakeholders, and was subsequently published in May 28, 2014. Although REGDOC-2.5.2 maintains the structure and the contents nearly the same as RD-337 version 1, it introduces several important improvements to: Include GD-337 guidance for further clarity to applicants, licensees and vendors on how to meet the requirements. This guidance provides the review criteria considered in CNSC staff's review in a transparent way; Ensure alignment with international standards including recent IAEA SSR 2/1, Safety of Nuclear Power Plants: Design; Implement CNSC Fukushima Task Force Report findings that pertain to the design of reactor facilities for severe accidents; and, Make necessary improvements such as addition of requirements for cyber security. This paper describes the overall regulatory framework related to CNSC's design requirements and guidance for NPPs, and focus on the important improvements included in REGDOC-2.5.2 and their reasoning. (author)

Design requirements for new nuclear reactor facilities in Canada (focus on important improvements from RD-337 version 1 of 2008)

Energy Technology Data Exchange (ETDEWEB)

Shim, S.; Harwood, C.; Ohn, M-Y; Liu, Y.C.; Young, T. [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

2014-07-01

The Canadian Nuclear Safety Commission (CNSC) has established the regulatory framework that includes the documentation of the requirements and guidance for each of CNSC's 14 Safety and Control Areas, one important area being the design of nuclear power plants (NPPs). For the design area, the CNSC published RD-337 version 1 Design of New Nuclear Power Plants in 2008. As such regulatory documents are reviewed on a regular basis, this document was recently updated as RD-337 version 2, and its guidance document GD-337, Guidance for the Design of New Nuclear Power Plants was developed to provide guidance on how to meet the requirements. REGDOC-2.5.2 Design of Reactor Facilities: Nuclear Power Plants that combines RD-337 version 2 and GD-337 version 1 was presented to the Commission on March 27, 2014 after two rounds of consultation with stakeholders, and was subsequently published in May 28, 2014. Although REGDOC-2.5.2 maintains the structure and the contents nearly the same as RD-337 version 1, it introduces several important improvements to: Include GD-337 guidance for further clarity to applicants, licensees and vendors on how to meet the requirements. This guidance provides the review criteria considered in CNSC staff's review in a transparent way; Ensure alignment with international standards including recent IAEA SSR 2/1, Safety of Nuclear Power Plants: Design; Implement CNSC Fukushima Task Force Report findings that pertain to the design of reactor facilities for severe accidents; and, Make necessary improvements such as addition of requirements for cyber security. This paper describes the overall regulatory framework related to CNSC's design requirements and guidance for NPPs, and focus on the important improvements included in REGDOC-2.5.2 and their reasoning. (author)

Use of Covariances in a Consistent Data Assimilation for Improvement of Basic Nuclear Parameters in Nuclear Reactor Applications: From Meters to Femtometers

International Nuclear Information System (INIS)

Herman, Mike; Hoblit, Sam; Gustavo, Nobre; Palumbo, Annalia; Pigni, M.T.; Palmiotti, G.; Hiruta, H.; Salvatores

2013-01-01

Extensive sensitivity and uncertainty studies and the availability of new covariance data have allowed preliminary quantification of the impact of current nuclear data uncertainties on the design parameters of the Generation-IV systems (both fast neutron and thermal neutron systems). Similar quantifications can be done for the parameters that characterize the associated innovative fuel cycle to insure sustainability, waste minimization and drastic reduction of the proliferation risks. In parallel, there has been a growing and very significant trend to develop a new generation of reactor simulation tools that rely more and more on first principles. It is safe to say that the next generation of innovative nuclear systems will be assessed with a completely new set of tools, more science based, in sharp contrast with what has been done in the past. However, the studies mentioned above point out that the present uncertainties in nuclear data should be significantly reduced in order to fully benefit from advances in modeling and simulation. Only a parallel effort in advanced simulation and nuclear data improvement will be able to provide designers with more general and well validated calculational tools to meet new design target accuracies. One further consideration related to the development of new advanced simulation tools is that there should be a more explicit link with the more fundamental physics parameters underlying the models used to describe cross sections that would avoid the use of processed, application-oriented, data (like multigroup cross sections). Finally, current methodologies for reducing uncertainties coming from nuclear data, which rely on the use of integral experiment information to perform statistical multigroup (i.e., energy spectrum weighted) cross section data assimilation should evolve to embrace new frontiers in advanced simulation. One of the drawbacks of the classical methodologies is related to the energy group structure and the type of

Hepatocyte nuclear factor 4A improves hepatic differentiation of immortalized adult human hepatocytes and improves liver function and survival.

Science.gov (United States)

Hang, Hua-Lian; Liu, Xin-Yu; Wang, Hai-Tian; Xu, Ning; Bian, Jian-Min; Zhang, Jian-Jun; Xia, Lei; Xia, Qiang

2017-11-15

Immortalized human hepatocytes (IHH) could provide an unlimited supply of hepatocytes, but insufficient differentiation and phenotypic instability restrict their clinical application. This study aimed to determine the role of hepatocyte nuclear factor 4A (HNF4A) in hepatic differentiation of IHH, and whether encapsulation of IHH overexpressing HNF4A could improve liver function and survival in rats with acute liver failure (ALF). Primary human hepatocytes were transduced with lentivirus-mediated catalytic subunit of human telomerase reverse transcriptase (hTERT) to establish IHH. Cells were analyzed for telomerase activity, proliferative capacity, hepatocyte markers, and tumorigenicity (c-myc) expression. Hepatocyte markers, hepatocellular functions, and morphology were studied in the HNF4A-overexpressing IHH. Hepatocyte markers and karyotype analysis were completed in the primary hepatocytes using shRNA knockdown of HNF4A. Nuclear translocation of β-catenin was assessed. Rat models of ALF were treated with encapsulated IHH or HNF4A-overexpressing IHH. A HNF4A-positive IHH line was established, which was non-tumorigenic and conserved properties of primary hepatocytes. HNF4A overexpression significantly enhanced mRNA levels of genes related to hepatic differentiation in IHH. Urea levels were increased by the overexpression of HNF4A, as measured 24h after ammonium chloride addition, similar to that of primary hepatocytes. Chromosomal abnormalities were observed in primary hepatocytes transfected with HNF4A shRNA. HNF4α overexpression could significantly promote β-catenin activation. Transplantation of HNF4A overexpressing IHH resulted in better liver function and survival of rats with ALF compared with IHH. HNF4A improved hepatic differentiation of IHH. Transplantation of HNF4A-overexpressing IHH could improve the liver function and survival in a rat model of ALF. Copyright © 2017 Elsevier Inc. All rights reserved.

Quality procedure management for improved nuclear safety

International Nuclear Information System (INIS)

Forzano, P.; Castagna, P.

1995-01-01

Emergency Operating Procedures and Accident Management Procedures are the next step in the computerization of NPP control rooms. Different improvements are presently conceivable for this operator aid tool, and research activities are in development. Undergoing activities regard especially formal aspects of knowledge representation, Human-Machine interface and procedure life cycle management. These aspects have been investigated deeply by Ansaldo, and partially incorporated in the DIAM prototype. Nuclear Power Plant Procedures can be seen from essentially two viewpoints: the process and the information management. From the first point of view, it is important to supply the knowledge apt to solve problems connected with the control of the process, from the second one the focus of attention is on the knowledge representation, its structure, elicitation and maintenance, and formal quality assurance. These two aspects of procedure representation can be considered and solved separately. In particular, methodological, formal and management issues require long and tedious activities, that in most cases constitute a great barrier for procedures development and upgrade. To solve these problems, Ansaldo is developing DIAM, a wide integrated tool for procedure management to support in procedure writing, updating, usage, and documentation. One of the most challenging features of DIAM is AUTO-LAY, a CASE sub-tool that, in a complete automatical way, structures parts or complete flow diagram. This is the feature that is partial present in some other CASE products, that, anyway, do not allow complex graph handling and isomorphism between video and paper representation. AUTO-LAY has the unique prerogative to draw graphs of any complexity to section them in pages, and to automatically compose a document. This has been recognized in the literature as the most important a second-generation CASE improvement. (Author) 9 Figs., 5 Refs

Improvement of quality with Nuclear Power Training Center (NTC) operator training

International Nuclear Information System (INIS)

Matsumoto, Y.

2005-01-01

Nuclear Power Training Center (NTC) was established in 1972 for PWR operator training. As the result of introduction of quality assurance management into NTC operator training, it became possible to confirm each step of systematic approach to training (SAT) process and then feedback process became clearer. Simulation models were modified based on domestic or overseas accidents cases and so training was improved using simulators closer to actual plants. Also a new multipurpose simulator with modified reactor coolant system (RCS) visual display device (RVD) and parameter-event-log (PEL) device was introduced in 2003 to provide more information so as to upgrade knowledge level of operators. (T. Tanaka)

Improved predictions of nuclear reaction rates with the TALYS reaction code for astrophysical applications

International Nuclear Information System (INIS)

Goriely, S.; Hilaire, S.; Koning, A.J

2008-01-01

Context. Nuclear reaction rates of astrophysical applications are traditionally determined on the basis of Hauser-Feshbach reaction codes. These codes adopt a number of approximations that have never been tested, such as a simplified width fluctuation correction, the neglect of delayed or multiple-particle emission during the electromagnetic decay cascade, or the absence of the pre-equilibrium contribution at increasing incident energies. Aims. The reaction code TALYS has been recently updated to estimate the Maxwellian-averaged reaction rates that are of astrophysical relevance. These new developments enable the reaction rates to be calculated with increased accuracy and reliability and the approximations of previous codes to be investigated. Methods. The TALYS predictions for the thermonuclear rates of relevance to astrophysics are detailed and compared with those derived by widely-used codes for the same nuclear ingredients. Results. It is shown that TALYS predictions may differ significantly from those of previous codes, in particular for nuclei for which no or little nuclear data is available. The pre-equilibrium process is shown to influence the astrophysics rates of exotic neutron-rich nuclei significantly. For the first time, the Maxwellian- averaged (n, 2n) reaction rate is calculated for all nuclei and its competition with the radiative capture rate is discussed. Conclusions. The TALYS code provides a new tool to estimate all nuclear reaction rates of relevance to astrophysics with improved accuracy and reliability. (authors)

New reactor technology: safety improvements in nuclear power systems.

Science.gov (United States)

Corradini, M L

2007-11-01

Almost 450 nuclear power plants are currently operating throughout the world and supplying about 17% of the world's electricity. These plants perform safely, reliably, and have no free-release of byproducts to the environment. Given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power can only satisfy the need for electricity and other energy-intensive products if it can demonstrate (1) enhanced safety and system reliability, (2) minimal environmental impact via sustainable system designs, and (3) competitive economics. The U.S. Department of Energy with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market by 2030 or earlier, and that can offer significant advances toward these challenging goals; in particular, six candidate reactor system designs have been identified. These future nuclear power systems will require advances in materials, reactor physics, as well as thermal-hydraulics to realize their full potential. However, all of these designs must demonstrate enhanced safety above and beyond current light water reactor systems if the next generation of nuclear power plants is to grow in number far beyond the current population. This paper reviews the advanced Generation-IV reactor systems and the key safety phenomena that must be considered to guarantee that enhanced safety can be assured in future nuclear reactor systems.

Effects of rainstorms and runoff on consequences of nuclear reactor accidents

International Nuclear Information System (INIS)

Ritchie, L.T.; Brown, W.D.; Wayland, J.R.

1976-10-01

A preliminary model describing the effects of washout and runoff on the consequences of a nuclear reactor accident is presented. The most important new feature of this stratified model relative to the model in WASH-1400 is the spatial structure of rainstorms and runoff consisting of four levels of rain activity that are normalized by rain gage data. The predicted concentrations of radioactivity and resultant health consequences of the stratified model are compared with those of the model in WASH-1400 for simplified rainstorms with fixed meteorological conditions, an actual rainstorm, and a stratified sample run consisting of 91 separate reactor accidents. In the case of individual storms, runoff and the spatial structure of the rain in the new model can result in health consequences that are significantly different from those of the WASH-1400 model. The differences between the predictions of the two models are small for the stratified sample run

Significant improvement of mouse cloning technique by treatment with trichostatin A after somatic nuclear transfer

International Nuclear Information System (INIS)

Kishigami, Satoshi; Mizutani, Eiji; Ohta, Hiroshi; Hikichi, Takafusa; Thuan, Nguyen Van; Wakayama, Sayaka; Bui, Hong-Thuy; Wakayama, Teruhiko

2006-01-01

The low success rate of animal cloning by somatic cell nuclear transfer (SCNT) is believed to be associated with epigenetic errors including abnormal DNA hypermethylation. Recently, we elucidated by using round spermatids that, after nuclear transfer, treatment of zygotes with trichostatin A (TSA), an inhibitor of histone deacetylase, can remarkably reduce abnormal DNA hypermethylation depending on the origins of transferred nuclei and their genomic regions [S. Kishigami, N. Van Thuan, T. Hikichi, H. Ohta, S. Wakayama. E. Mizutani, T. Wakayama, Epigenetic abnormalities of the mouse paternal zygotic genome associated with microinsemination of round spermatids, Dev. Biol. (2005) in press]. Here, we found that 5-50 nM TSA-treatment for 10 h following oocyte activation resulted in more efficient in vitro development of somatic cloned embryos to the blastocyst stage from 2- to 5-fold depending on the donor cells including tail tip cells, spleen cells, neural stem cells, and cumulus cells. This TSA-treatment also led to more than 5-fold increase in success rate of mouse cloning from cumulus cells without obvious abnormality but failed to improve ES cloning success. Further, we succeeded in establishment of nuclear transfer-embryonic stem (NT-ES) cells from TSA-treated cloned blastocyst at a rate three times higher than those from untreated cloned blastocysts. Thus, our data indicate that TSA-treatment after SCNT in mice can dramatically improve the practical application of current cloning techniques

Operational analysis and improvement of a spent nuclear fuel handling and treatment facility using discrete event simulation

International Nuclear Information System (INIS)

Garcia, H.E.

2000-01-01

Spent nuclear fuel handling and treatment often require facilities with a high level of operational complexity. Simulation models can reveal undesirable characteristics and production problems before they become readily apparent during system operations. The value of this approach is illustrated here through an operational study, using discrete event modeling techniques, to analyze the Fuel Conditioning Facility at Argonne National Laboratory and to identify enhanced nuclear waste treatment configurations. The modeling approach and results of what-if studies are discussed. An example on how to improve productivity is presented.

Improvement of the nuclear plant analyzer for Korean Standard Nuclear Power Plants

International Nuclear Information System (INIS)

Choi, Sung Soo; Han, Byoung Sub; Suh, Jae Seung; Son, Dae Seong

2005-04-01

Accurate analysis of the operating characteristics of Nuclear Power Plants provides valuable information for both norman and abnormal operation. The information can be used for the enhancement of plant performance and safety. Usually, such analysis is performed using computer codes used for plant design or simulators. However, their usages are limited because special expertise is required to use the computer codes and simulators are not portable. Therefore, it deemed necessary to develop an NPA which minimizes those limitations and can be used for the analysis and simulation of Nuclear Power Plants. The purpose of this study is to develop a real-time best-estimate NPA for the Korean Nuclear Power Plants(KSNP). The NPA is an interactive, high fidelity engineering simulator. NPA combines the process model simulating the plant behavior with the latest computer technology such as Graphical User Interface(GUI) and simulation executive for enhanced user interface. The process model includes models for a three-dimensional reactor core, the NSSS, secondary system including turbine and feedtrain, safety auxiliary systems, and various control systems. Through the verification and validation of the NPA, it was demonstrated that the NPA can realistically simulate the plant behaviors during transient and accident conditions

Reducing nuclear danger through intergovernmental technical exchanges on nuclear materials safety management

International Nuclear Information System (INIS)

Jardine, L.J.; Peddicord, K.L.; Witmer, F.E.; Krumpe, P.F.; Lazarev, L.; Moshkov, M.

1997-01-01

The United States and Russia are dismantling nuclear weapons and generating hundreds of tons of excess plutonium and high enriched uranium fissile nuclear materials that require disposition. The U.S. Department of Energy and Russian Minatom organizations.are planning and implementing safe, secure storage and disposition operations for these materials in numerous facilities. This provides a new opportunity for technical exchanges between Russian and Western scientists that can establish an improved and sustained common safety culture for handling these materials. An initiative that develops and uses personal relationships and joint projects among Russian and Western participants involved in fissile nuclear materials safety management contributes to improving nuclear materials nonproliferation and to making a safer world. Technical exchanges and workshops are being used to systematically identify opportunities in the nuclear fissile materials facilities to improve and ensure the safety of workers, the public, and the environment

A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Beyer, M; Carl, H; Nowak, K [Technischer Ueberwachungsverein Rheinland, Koeln (Germany). Inst. for Nuclear Engineering and Radiation Protection; Schumann, P; Seidel, A; Weiss, F P; Zschau, J

1998-10-01

As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

International Nuclear Information System (INIS)

Beyer, M.; Carl, H.; Nowak, K.; Schumann, P.; Seidel, A.; Weiss, F.P.; Zschau, J.

1998-01-01

As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

Improved single particle potential for transport model simulations of nuclear reactions induced by rare isotope beams

International Nuclear Information System (INIS)

Xu Chang; Li Baoan

2010-01-01

Taking into account more accurately the isospin dependence of nucleon-nucleon interactions in the in-medium many-body force term of the Gogny effective interaction, new expressions for the single-nucleon potential and the symmetry energy are derived. Effects of both the spin (isospin) and the density dependence of nuclear effective interactions on the symmetry potential and the symmetry energy are examined. It is shown that they both play a crucial role in determining the symmetry potential and the symmetry energy at suprasaturation densities. The improved single-nucleon potential will be useful for more accurate simulation of nuclear reactions induced by rare-isotope beams within transport models.

Histone deacetylase inhibitor significantly improved the cloning efficiency of porcine somatic cell nuclear transfer embryos.

Science.gov (United States)

Huang, Yongye; Tang, Xiaochun; Xie, Wanhua; Zhou, Yan; Li, Dong; Yao, Chaogang; Zhou, Yang; Zhu, Jianguo; Lai, Liangxue; Ouyang, Hongsheng; Pang, Daxin

2011-12-01

Valproic acid (VPA), a histone deacetylase inbibitor, has been shown to generate inducible pluripotent stem (iPS) cells from mouse and human fibroblasts with a significant higher efficiency. Because successful cloning by somatic cell nuclear transfer (SCNT) undergoes a full reprogramming process in which the epigenetic state of a differentiated donor nuclear is converted into an embryonic totipotent state, we speculated that VPA would be useful in promoting cloning efficiency. Therefore, in the present study, we examined whether VPA can promote the developmental competence of SCNT embryos by improving the reprogramming state of donor nucleus. Here we report that 1 mM VPA for 14 to 16 h following activation significantly increased the rate of blastocyst formation of porcine SCNT embryos constructed from Landrace fetal fibroblast cells compared to the control (31.8 vs. 11.4%). However, we found that the acetylation level of Histone H3 lysine 14 and Histone H4 lysine 5 and expression level of Oct4, Sox2, and Klf4 was not significantly changed between VPA-treated and -untreated groups at the blastocyst stage. The SCNT embryos were transferred to 38 surrogates, and the cloning efficiency in the treated group was significantly improved compared with the control group. Taken together, we have demonstrated that VPA can improve both in vitro and in vivo development competence of porcine SCNT embryos.

Nuclear Safety Review 2013

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-15

The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis.

Nuclear Safety Review 2013

International Nuclear Information System (INIS)

2013-07-01

The Nuclear Safety Review 2013 focuses on the dominant nuclear safety trends, issues and challenges in 2012. The Executive Overview provides crosscutting and worldwide nuclear safety information along with a summary of the major sections covered in this report. Sections A-E of this report cover improving radiation, transport and waste safety; strengthening safety in nuclear installations; improving regulatory infrastructure and effectiveness; enhancing emergency preparedness and response (EPR); and civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards (CSS), and activities relevant to the IAEA Safety Standards. The world nuclear community has made noteworthy progress in strengthening nuclear safety in 2012, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as ''the Action Plan''). For example, an overwhelming majority of Member States with operating nuclear power plants (NPPs) have undertaken and essentially completed comprehensive safety reassessments ('stress tests') with the aim of evaluating the design and safety aspects of plant robustness to protect against extreme events, including: defence in depth, safety margins, cliff edge effects, multiple failures, and the prolonged loss of support systems. As a result, many have introduced additional safety measures including mitigation of station blackout. Moreover, the IAEA's peer review services and safety standards have been reviewed and strengthened where needed. Capacity building programmes have been built or improved, and EPR programmes have also been reviewed and improved. Furthermore, in 2012, the IAEA continued to share lessons learned from the Fukushima Daiichi accident with the nuclear community including through three international experts' meetings (IEMs) on reactor and spent fuel safety, communication in the event of a nuclear or radiological emergency, and protection against extreme earthquakes and tsunamis