Rewriting the Salem Witchcraft Trials in Contemporary Popular Literature

Directory of Open Access Journals (Sweden)

Marta María Gutiérrez Rodríguez

2016-10-01

Full Text Available The Salem Witchcraft Trials (1692 have received a lot of attention from history and literature, although there are very few critical analysis of how this historical event has entered the literary field. Many works of historical fiction – considered the most suitable literary genre to talk about an historical event - have used it in their storylines; however, popular genres such as romance, crime fiction, fantasy and science fiction have also shown an interest in this witch hunt. The main reason for this interest can be found in the lack of final conclusions as regards what really happened in Salem. The main objective of this paper is to show how what happened in Salem has entered contemporary popular fiction with the aim of showing the interest that it still arises and to vindicate the production of more critical works about the literary construction of one of the events that most dramatically has affected the configuration of the American mind.

Salem 98: A post-plume phase, federal participation exercise

International Nuclear Information System (INIS)

1999-01-01

Salem 98 was the largest nuclear power plant post-plume phase exercise since the 1993 FRMAC-93 exercise at the Fort Calhoun Nuclear Power Plant in Nebraska. Salem 98 was a 3 Day exercise, held on May 5--7, 1998, involving participation by the States of New Jersey and Delaware and associated State and county agencies. Public Service Electric and Gas was the host utility and Salem County the host county. Federal participation included the Nuclear Regulatory Commission, Federal Emergency Management Agency, Department of Energy, Environmental Protection Agency, US department of Agriculture and Department of Health and Human Services. In addition, the American Nuclear Insurers participated, adding a dimension to the exercise not experienced often enough. This was a stand-alone post-plume phase exercise, which took place 2 months after the evaluated plume phase exercise held on March 3, 1998, also including participation by various Federal agencies. This exercise demonstrated the positive working relationship among utility, State, county, and Federal responders in response to a postulated major nuclear power plant emergency with significant offsite consequences

Salem 98: A post-plume phase, federal participation exercise

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-01-01

Salem 98 was the largest nuclear power plant post-plume phase exercise since the 1993 FRMAC-93 exercise at the Fort Calhoun Nuclear Power Plant in Nebraska. Salem 98 was a 3 Day exercise, held on May 5--7, 1998, involving participation by the States of New Jersey and Delaware and associated State and county agencies. Public Service Electric and Gas was the host utility and Salem County the host county. Federal participation included the Nuclear Regulatory Commission, Federal Emergency Management Agency, Department of Energy, Environmental Protection Agency, US department of Agriculture and Department of Health and Human Services. In addition, the American Nuclear Insurers participated, adding a dimension to the exercise not experienced often enough. This was a stand-alone post-plume phase exercise, which took place 2 months after the evaluated plume phase exercise held on March 3, 1998, also including participation by various Federal agencies. This exercise demonstrated the positive working relationship among utility, State, county, and Federal responders in response to a postulated major nuclear power plant emergency with significant offsite consequences.

33 CFR 165.116 - Safety and Security Zones; Salem and Boston Harbors, Massachusetts.

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones; Salem..., DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PORTS AND WATERWAYS SAFETY REGULATED NAVIGATION AREAS AND LIMITED... § 165.116 Safety and Security Zones; Salem and Boston Harbors, Massachusetts. (a) Location. The...

Multi-Century Record of Anthropogenic Impacts on an Urbanized Mesotidal Estuary: Salem Sound, MA

Science.gov (United States)

Salem, MA, located north of Boston, has a rich, well-documented history dating back to settlement in 1626 CE, but the associated anthropogenic impacts on Salem Sound are poorly constrained. This project utilized dated sediment cores from the sound to assess the proxy record of an...

Pathogen Transport and Fate Modeling in the Upper Salem River Watershed Using SWAT Model

Science.gov (United States)

SWAT (Soil and Water Assessment Tool) is a dynamic watershed model that is applied to simulate the impact of land management practices on water quality over a continuous period. The Upper Salem River, located in Salem County New Jersey, is listed by the New Jersey Department of ...

Environmental assessment, proposed generating station for Darlington

International Nuclear Information System (INIS)

1975-04-01

This document indicates the intention of Ontario Hydro to seek approval from the Provincial Government for its plan to construct and operate a 3400 MWe nuclear generating station at the Darlington site, west of Bowmanville. This preliminary proposal also contains the environmental assessment. The environmental section of this proposal describes and assesses the existing environment and the environmental influences which would occur due to the construction and operation of a nuclear generating station, consisting of four 850 MW units, at the Darlington site. This proposed station is similar to the Bruce GS A station presently under construction. (author)

The Specter of Salem in American Culture.

Science.gov (United States)

Adams, Gretchen A.

2003-01-01

Focuses on the impact of the Salem (Massachusetts) witchcraft trials on U.S. society over the centuries, particularly in relation to the trials as a metaphor for persecution and witch-hunting. Explores different events in history, such as the anti-communism evident in the 1950's and abolitionism during the U.S. Civil War. (CMK)

Aspectos discursivos em As Bruxas de Salem: peça e filme

OpenAIRE

Pinheiro, Eder Sergio

2009-01-01

Esta pesquisa, cujo título é Aspectos Discursivos em As Bruxas de Salem: eça e Filme, propõe discutir a transposição da linguagem escrita, neste caso, as rubricas da peça de teatro para a linguagem fílmica, devido a problemática das duas linguagens se diferenciarem, convergirem-se e cruzarem-se ao mesmo tempo. Deste modo, dois fragmentos foram escolhidos para análise, sendo eles: um trecho da peça escrita As Bruxas de Salem (1953) e outro do filme (1976), ambos os trechos são correspondent...

Genetic architecture and bottleneck analyses of Salem Black goat breed based on microsatellite markers

Directory of Open Access Journals (Sweden)

A. K. Thiruvenkadan

2014-09-01

Full Text Available Aim: The present study was undertaken in Salem Black goat population for genetic analysis at molecular level to exploit the breed for planning sustainable improvement, conservation and utilization, which subsequently can improve the livelihood of its stakeholders. Materials and Methods: Genomic DNA was isolated from blood samples of 50 unrelated Salem Black goats with typical phenotypic features in several villages in the breeding tract and the genetic characterization and bottleneck analysis in Salem Black goat was done using 25 microsatellite markers as recommended by the Food and Agricultural Organization, Rome, Italy. The basic measures of genetic variation were computed using bioinformatic software. To evaluate the Salem Black goats for mutation drift equilibrium, three tests were performed under three different mutation models, viz., infinite allele model (IAM, stepwise mutation model (SMM and two-phase model (TPM and the observed gene diversity (He and expected equilibrium gene diversity (Heq were estimated under different models of microsatellite evolution. Results: The study revealed that the observed number of alleles ranged from 4 (ETH10, ILSTS008 to 17 (BM64444 with a total of 213 alleles and mean of 10.14±0.83 alleles across loci. The overall observed heterozygosity, expected heterozygosity, inbreeding estimate and polymorphism information content values were 0.631±0.041, 0.820±0.024, 0.233±0.044 and 0.786±0.023 respectively indicating high genetic diversity. The average observed gene diversities (He pooled over different markers was 0.829±0.024 and the average expected gene diversities under IAM, TPM and SMM models were 0.769±0.026, 0.808±0.024 and 0.837±0.020 respectively. The number of loci found to exhibit gene diversity excess under IAM, TPM and SMM models were 18, 17 and 12 respectively. Conclusion: All the three statistical tests, viz., sign test, standardized differences test and Wilcoxon sign rank test, revealed

SaLEM (v1.0) - the Soil and Landscape Evolution Model (SaLEM) for simulation of regolith depth in periglacial environments

Science.gov (United States)

Bock, Michael; Conrad, Olaf; Günther, Andreas; Gehrt, Ernst; Baritz, Rainer; Böhner, Jürgen

2018-04-01

We propose the implementation of the Soil and Landscape Evolution Model (SaLEM) for the spatiotemporal investigation of soil parent material evolution following a lithologically differentiated approach. Relevant parts of the established Geomorphic/Orogenic Landscape Evolution Model (GOLEM) have been adapted for an operational Geographical Information System (GIS) tool within the open-source software framework System for Automated Geoscientific Analyses (SAGA), thus taking advantage of SAGA's capabilities for geomorphometric analyses. The model is driven by palaeoclimatic data (temperature, precipitation) representative of periglacial areas in northern Germany over the last 50 000 years. The initial conditions have been determined for a test site by a digital terrain model and a geological model. Weathering, erosion and transport functions are calibrated using extrinsic (climatic) and intrinsic (lithologic) parameter data. First results indicate that our differentiated SaLEM approach shows some evidence for the spatiotemporal prediction of important soil parental material properties (particularly its depth). Future research will focus on the validation of the results against field data, and the influence of discrete events (mass movements, floods) on soil parent material formation has to be evaluated.

PATHOGEN TRANSPORT AND FATE MODELING IN THE UPPER SALEM RIVER WATERSHED USING SWAT MODEL - PEER-REVIEWED JOURNAL ARTICLE

Science.gov (United States)

Simulation of the fate and transport of pathogen contamination was conducted with SWAT for the Upper Salem River Watershed, located in Salem County, New Jersey. This watershed is 37 km2 and land uses are predominantly agricultural. The watershed drains to a 32 km str...

Point Lepreau generating station

International Nuclear Information System (INIS)

Ganong, G.H.D.; Strang, A.E.; Gunter, G.E.; Thompson, T.S.

Point Lepreau-1 reactor is a 600 MWe generating station expected to be in service by October 1979. New Brunswick is suffering a 'catch up' phenomenon in load growth and needs to decrease dependence on foreign oil. The site is on salt water and extensive study has gone into corrosion control. Project management, financing and scheduling have unique aspects. (E.C.B.)

SaLEM (v1.0 – the Soil and Landscape Evolution Model (SaLEM for simulation of regolith depth in periglacial environments

Directory of Open Access Journals (Sweden)

M. Bock

2018-04-01

Full Text Available We propose the implementation of the Soil and Landscape Evolution Model (SaLEM for the spatiotemporal investigation of soil parent material evolution following a lithologically differentiated approach. Relevant parts of the established Geomorphic/Orogenic Landscape Evolution Model (GOLEM have been adapted for an operational Geographical Information System (GIS tool within the open-source software framework System for Automated Geoscientific Analyses (SAGA, thus taking advantage of SAGA's capabilities for geomorphometric analyses. The model is driven by palaeoclimatic data (temperature, precipitation representative of periglacial areas in northern Germany over the last 50 000 years. The initial conditions have been determined for a test site by a digital terrain model and a geological model. Weathering, erosion and transport functions are calibrated using extrinsic (climatic and intrinsic (lithologic parameter data. First results indicate that our differentiated SaLEM approach shows some evidence for the spatiotemporal prediction of important soil parental material properties (particularly its depth. Future research will focus on the validation of the results against field data, and the influence of discrete events (mass movements, floods on soil parent material formation has to be evaluated.

Trends in the capital costs of CANDU generating stations

International Nuclear Information System (INIS)

Yu, A.M.

1982-09-01

This paper consolidates the actual cost experience gained by Atomic Energy of Canada Limited, Ontario Hydro, and other Canadian electric utlities in the planning, design and construction of CANDU-PHWR (CANada Deuterium Uranium-Pressurized Heavy Water Reactor) generating stations over the past 30 years. For each of the major CANDU-PHWR generating stations in operation and under construction in Canada, an analysis is made to trace the evolution of the capital cost estimates. Major technical, economic and other parameters that affect the cost trends of CANDU-PHWR generating stations are identified and their impacts assessed. An analysis of the real cost of CANDU generating stations is made by eliminating interest during construction and escalation, and the effects of planned deferment of in-service dates. An historical trend in the increase in the real cost of CANDU power plants is established. Based on the cost experience gained in the design and construction of CANDU-PHWR units in Canada, as well as on the assessment of parameters that influence the costs of such projects, the future costs of CANDU-PHWRs are presented

Next Generation Hydrogen Station Composite Data Products: Retail Stations, Data through Quarter 4 of 2016

Energy Technology Data Exchange (ETDEWEB)

Sprik, Sam [National Renewable Energy Lab. (NREL), Golden, CO (United States); Kurtz, Jennifer [National Renewable Energy Lab. (NREL), Golden, CO (United States); Ainscough, Chris [National Renewable Energy Lab. (NREL), Golden, CO (United States); Saur, Genevieve [National Renewable Energy Lab. (NREL), Golden, CO (United States); Peters, Michael [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2017-05-31

This publication includes 86 composite data products (CDPs) produced for next generation hydrogen stations, with data through the fourth quarter of 2016. These CDPs include data from retail stations only.

Next Generation Hydrogen Station Composite Data Products: Retail Stations, Data through Quarter 2 of 2017

Energy Technology Data Exchange (ETDEWEB)

Sprik, Samuel [National Renewable Energy Lab. (NREL), Golden, CO (United States); Kurtz, Jennifer M [National Renewable Energy Lab. (NREL), Golden, CO (United States); Ainscough, Christopher D. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Saur, Genevieve [National Renewable Energy Lab. (NREL), Golden, CO (United States); Peters, Michael C. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2017-12-05

This publication includes 92 composite data products (CDPs) produced for next generation hydrogen stations, with data through the second quarter of 2017. These CDPs include data from retail stations only.

Report on Darlington nuclear generating station

International Nuclear Information System (INIS)

1985-12-01

The Select Committee on Energy was appointed on July 10, 1985 by the Legislative Assembly of the Province of Ontario in order to inquire into and report on Ontario Hydro affairs within ten months. Two sessions were planned the first of which was a review of the Darlington Nuclear Generating Station. Darlington is a large, 4 unit nuclear-powered electricity generating station currently under construction on the shore of Lake Ontario in the town of Newcastle. At the time the Committee met, construction had been underway for over four years. The first two units are scheduled to become operational in 1988 and 1989 with the second two scheduled to become operational in 1991 and 1992. The total estimated cost of the station is $10.895 billion of which $3.66 billion has been spent and $3.385 billion has been committed. Though the nuclear industry has been a major area of investment in Ontario over the past decade, the demand for electrical power from nuclear stations has been significantly decreased. This report focusses on the need for Darlington and public policy issues involved in planning and completing it. The Committee proposed the following recommendations: 1) The relationship between the Government of Ontario and Ontario Hydro and their individual responsibilities should be clarified. 2) An independent review of the Ontario Hydro demand/supply options should be carried out. 3) No further significant contracts for Darlington units 3 and 4 should be let for materials not required for construction during the next 6 months while the Committee studies demand and supply options

Dispersion of chlorine at seven southern California coastal generating stations

International Nuclear Information System (INIS)

Grove, R.S.

1983-01-01

The objectives of this study were to (1) determine chlorine concentrations and exposure time gradients of chlorine through seven coastal generating stations and (2) assess the dispersion characteristics of chlorine in the receiving waters. Remarkable variability in chlorine injection concentrations, condenser outlet concentrations, outfall concentrations, and dissipation rates between generating stations and, to a lesser extent, between surveys at the same generating station was found in this chlorine monitoring study. Other than quite consistent low injection and correspondingly low outfall concentrations at San Onofre (a generating station that had one of the more rigorous chlorine control and minimization programs in effect at the time), no recognizable patterns of chlorination could be discerned in the data. Over half of the outfall chlorine surveys had chlorine concentrations below 0.08 mg/L, which is the accepted level of detection for the titrator being used in the surveys. The post-outfall dilution calculations further showed that the chlorine that does enter the receiving water is initially diluted with entrained ambient water at a ratio of 5.2:19.0

Control rod trip failures; Salem 1, the cause, response, and potential fixes

International Nuclear Information System (INIS)

Hall, R.E.; Boccio, J.L.; Luckas, W.J.

1984-01-01

This chapter presents a systems and reliability analysis of recent nuclear reactor control rod failure-to-trip (or scram) events that have been experienced in the US commercial nuclear industry. The operational factors of hardware, procedures, and human error are considered in the analysis of transients without scram. The 1980 Browns Ferry 3 scram system failure is analyzed to contrast the two 1983 Salem 1 events. The details of the Salem control rod failure to trip are investigated and used to calculate the reactor protection system unavailabilities. The internal reactor trip breaker logic is reviewed as related to the Westinghouse DB-50 breaker application. The impact of test and maintenance on system challenges is discussed. It is concluded that although the failure to trip or scram represents a single class of initiators, the actual events of each transient are operationally unique and require individual human responses

Review of freeboard: Grand Rapids Generating Station

Energy Technology Data Exchange (ETDEWEB)

Groeneveld, J.L.; Harding, W.B.; Bonin, D.V.; Fuchs, D.M. [Acres Manitoba Ltd., Winnipeg, MB (Canada); Warner, B.J. [Manitoba Hydro, Winnipeg, MB (Canada)

2001-10-01

Constructed during the period 1960-1965, the Grand Rapids Generating Station is a 472 MW hydroelectric station located approximately 400 kilometres northwest of Winnipeg, Manitoba, on the Saskatchewan River. An intake structure, four penstocks, a four-unit plus house unit powerhouse, wing walls, extensive dyke structures and a four-bay spillway are the components of the generating station. A little over ten years ago, the Manitoba Hydro Dam Safety Program was initiated. The program included a detailed dam safety review of the Grand rapids Generating Station. A potential deficiency in the freeboard allowance for several of the earthen dykes was revealed by the review process. The dam safety guidelines sponsored by the Canadian Dam Association were not met. The occurrence of a 1:1000 year wind event from the critical direction when the reservoir was at or near its full supply level was compounded by the analysis. The establishment of a wind and wave monitoring program was included in the deficiency studies commissioned. The objective was to confirm the empirical estimates concerning wave height, the development and usage of a two dimensional numerical wave model, and additional freeboard analyses to refine estimates of the recurrence interval of the current level of protection. A statistical Monte Carlo analysis was performed in the case of the estimates of the recurrence interval to determine the joint probabilities of seasonal variations in wind direction, wind speed, and reservoir level. The estimate of the actual risk of overtopping was therefore refined, and the details pertaining to the methodology and the conclusions of the analysis are all included in the paper. 15 refs., 4 tabs., 9 figs.

A novel lignin-based surfactant system for the Salem Unit

International Nuclear Information System (INIS)

DeBons, F.E.; Whittington, L.E.

1991-01-01

Texaco conducted a successful surfactant/polymer flood in a 60-acre [24 ha] portion of the Salem Benoist reservoir in Salem, Illinois, in 1981. This pilot used a brine-tolerant petroleum sulfonate surfactant system blended in injection brine followed by a xanthan mobility control polymer in fresher water. The oil recovery over the seven year life of the flood was 487,050 bbl [77 435 m 3 ]. This represents 45% of the oil remaining in the total thickness of 73% of that from the more permeable lower interval where most of the surfactant flowed. Since this successful project, Texaco has continued to improve enhanced oil recovery surfactant systems. We have developed novel, brine tolerant surfactants based on the renewable resources lignin and tallow amine. This paper describes the laboratory work leading to a surfactant system which has been recommended for field testing. The laboratory work includes blending, interfacial tension measurements, and core floods in Berea and reservoir cores. The type of lignin based surfactant system described in this report has applicability in all fields where conventional petroleum-based surfactants have been used. Their much lower cost means that they can be used economically at lower crude oil prices

Electricity pricing model in thermal generating stations under deregulation

International Nuclear Information System (INIS)

Reji, P.; Ashok, S.; Moideenkutty, K.M.

2007-01-01

In regulated public utilities with competitive power markets, deregulation has replaced the monopoly. Under the deregulated power market, the electricity price primarily depends on market mechanism and power demand. In this market, generators generally follow marginal pricing. Each generator fixes the electricity price based on their pricing strategy and it leads to more price volatility. This paper proposed a model to determine the electricity price considering all operational constraints of the plant and economic variables that influenced the price, for a thermal generating station under deregulation. The purpose of the model was to assist existing stations, investors in the power sector, regulatory authorities, transmission utilities, and new power generators in decision-making. The model could accommodate price volatility in the market and was based on performance incentive/penalty considering plant load factor, availability of the plant and peak/ off peak demand. The model was applied as a case study to a typical thermal utility in India to determine the electricity price. It was concluded that the case study of a thermal generating station in a deregulated environment showed that the electricity price mainly depended on the gross calorific value (GCV) of fuel, mode of operation, price of the fuel, and operating charges. 11 refs., 2 tabs., 1 fig

A "clean cigarette" for a clean nation: a case study of Salem Pianissimo in Japan.

Science.gov (United States)

Assunta, M; Chapman, S

2004-12-01

To illustrate, through internal industry documents, how RJ Reynolds exploited the concerns of the Japanese society about cleanliness to market the concept of cleaner, implicitly healthier cigarettes in Japan. Systematic keyword and opportunistic website searches of formerly private internal industry documents. Industry documents show that RJ Reynolds developed marketing plans based upon their cultural assumptions of Japanese people as fastidious about hygiene and manners, and with relatively high penchants to try new products. RJ Reynolds found there was also a growing concern for health, the environment, and smokers were conscious about annoying others. Deodorised consumer products were one of Japan's biggest trends. These characteristics presented RJ Reynolds with a profitable formula for marketing Salem Pianissimo, a clean cigarette with less smell and smoke. Salem Pianissimo, a 100 mm cigarette claiming to contain 1 mg tar and 0.1 mg nicotine, targeted women since menthol cigarettes were popular among 18-24 year old female smokers, although Japan's law prohibited those below 20 years to smoke and the tobacco industry had a voluntary code disallowing advertising to women and youth. RJ Reynolds successfully launched its clean cigarette, Salem Pianissimo, in Japan aiming to exploit perceived cultural characteristics such as a penchant for cleanliness, an eagerness to try new products, and social harmony.

ALGORITHM TO CHOOSE ENERGY GENERATION MULTIPLE ROLE STATION

Directory of Open Access Journals (Sweden)

Alexandru STĂNESCU

2014-05-01

Full Text Available This paper proposes an algorithm that is based on a complex analysis method that is used for choosing the configuration of a power station. The station generates electric energy and hydrogen, and serves a "green" highway. The elements that need to be considered are: energy efficiency, location, availability of primary energy sources in the area, investment cost, workforce, environmental impact, compatibility with existing systems, meantime between failure.

The Misema generating station by CREC : the journey

International Nuclear Information System (INIS)

2003-01-01

The Canadian Renewable Energy Corporation (CREC) was created in 2000 in response to the government's commitment to renewable energy. This publication presents a series of photographs illustrating the development of the Misema run-of-the river hydro generating station, including its 300 m long power tunnel from the intake to the powerhouse. The Misema project was the first in Ontario to run an underground tunnel to protect the river bank and reduce visual impact. It was also the first to have an underground power house that could withstand the 1 in 1,000 year flood. Connection to the grid is via a private 44,000 volt line. The station is fully automated to meet Ontario's power demand. Engineering and environmental approval for the project began in 2001, with construction starting in May 2001. The generating facility uses natural river flow to generate electricity, and is expected to play an important role in strengthening the electricity grid at its periphery and offer reliable power to thousands of customers. Small hydro also has minimal impact on the environment. CREC intends to make the site accessible to recreational canoeists, fishermen, geologists and tourists. The generating station was nearly completely constructed by local tradesmen and contractors, creating about 30,000 man-hours for the Englehart area. The Misema facility is contributing to Ontario's deregulated power market and has provided much needed electricity while reducing Ontario's greenhouse gas emissions. The facility was built to the highest international standards. figs

Physical degradation assessment of generator station cables

International Nuclear Information System (INIS)

Stonkus, D.J.

1988-01-01

Preliminary studies of fossil-fired and nuclear generator station cables indicate that the low voltage PVC insulated cables are in relatively good condition. The insulation is flexible and in the case of nuclear cables can withstand a design basis event after nearly 15 years of service. Cables insulated with styrene butadiene rubber have been found embrittled and cables insulated with SBR should be closely inspected in any plant assurance program. Thermal analysis using oxidative induction technique shows promise to indicate cable insulation degradation. Long term reliability assurance and plant life extension studies are being actively pursued at Ontario Hydro. A major study is currently underway to extend the life of the oldest operating fossil-fuel station, the 8-unit, 2400 MW Lakeview TGS in operation since the 1960s. Plant life assurance programs have been initiated at the 2000 MW Lambton TGS in operation since 1969, and for the oldest operating nuclear plant, Pickering NGS A in operation since the early 1970s. As cables are considered one of the critical components in a generator station due to the extreme difficulty and cost of cable replacement, test programs have been initiated to evaluate the physical degradation of the cables and relate the results to electrical diagnostic tests and to chemical changes. The decommissioning of two small nuclear stations, the 20 MW Nuclear Power Demonstration (NPD) and the 200 MW Douglas Point NGS, which were placed in service in 1962 and 1967 respectively, will provide an opportunity to perform destructive electrical and physical evaluation on field aged cables

Phytotoxicology section investigation in the vicinity of the Bruce Nuclear Power Development, the Pickering Nuclear Generating Station and the Darlington Nuclear Generating Station, in October, 1989

International Nuclear Information System (INIS)

1991-02-01

The Phytotoxicology Section, Air Resources Branch is a participant in the Pickering and Bruce Nuclear Contingency Plans. The Phytotoxicology Emergency Response Team is responsible for collecting vegetation samples in the event of a nuclear emergency at any of the nuclear generating stations in the province. As part of its responsibility the Phytotoxicology Section collects samples around the nuclear generating stations for comparison purposes in the event of an emergency. Because of the limited frequency of sampling, the data from the surveys are not intended to be used as part of a regulatory monitoring program. These data represent an effort by the MOE to begin to establish a data base of tritium concentrations in vegetation. The Phytotoxicology Section has carried out seven surveys in the vicinity of Ontario Hydro nuclear generating stations since 1981. Surveys were conducted for tritium in snow in the vicinity of Bruce Nuclear Power Development (BNPD), February, 1981; tritium in cell-free water of white ash in the vicinity of BNPD, September, 1981; tritium in snow in the vicinity of BNPD, March, 1982; tritium in tree sap in the vicinity of BNPD, April, 1982; tritium in tree sap in the vicinity of BNPD, April, 1984, tritium in the cell-free water of white ash in the vicinity of BNPD, September, 1985; and, tritium in cell-free water of grass in the vicinity of Pickering Nuclear Generation Station (PNGS), October 1986. In all cases a pattern of decreasing tritium levels with increasing distance from the stations was observed. In October, 1989, assessment surveys were conducted around Bruce Nuclear Power Development, the Pickering Nuclear Generating Station and the new Darlington Nuclear Generating Station (DNGS). The purpose of these surveys was to provide baseline data for tritium in cell-free water of grass at all three locations at the same time of year. As none of the reactor units at DNGS had been brought on line at the time of the survey, this data was to be

Dose management programmes at Kaiga Generating Station

International Nuclear Information System (INIS)

Vijayan, P.; Prabhakaran, V.; Managavi, Sadashiv B.; Danannavar, Veerendra; Biju, P.; Manoj Kumar, M.; Shrikrishna, U.V.

2001-01-01

Kaiga Generating Station (KGS) has two units of pressurized heavy water reactors of 220 MWe each capacity. KGS-2 started power generation since 1999 and KGS-1 since 2000. Several programmes such as assessment of radioactive condition, training on radiological safety aspects, job planning in radioactive areas, etc. are conducted periodically to implement an effective dose control programmes in KGS. These efforts are briefly discussed in this report. Facilities and techniques to implement ALARA programs are also highlighted in this report. (author)

75 FR 20033 - Winston-Salem Southbound Railway Company-Corporate Family Transaction Exemption-High Point...

Science.gov (United States)

2010-04-16

... DEPARTMENT OF TRANSPORTATION Surface Transportation Board [STB Finance Docket No. 35338] Winston-Salem Southbound Railway Company--Corporate Family Transaction Exemption--High Point, Thomasville... under 49 CFR 1180.2(d)(3) for a transaction within a corporate family. Applicants state that HPTD will...

Beyond the Criminal Arena: The Justice Studies Program at Winston-Salem State University

Science.gov (United States)

Harvey, Lynn K.; Mitchell, Alvin D.

2006-01-01

The justice studies program at Winston-Salem State University (WSSU) is designed to produce a new breed of justice practitioners whose understanding of justice and its administration is broadened to include the political, social, economic, and cultural conditions within which issues of crime and punishment are pursued and addressed. While it…

Radioactive release data from Canadian nuclear generating stations 1872-1987

International Nuclear Information System (INIS)

1989-03-01

All nuclear generating stations emit small quantities of radioactive effluent both into the atmosphere and in the form of liquid effluent, into the adjoining water body, be it river, lake or sea. The purpose of this document is to report on the magnitude of these emissions for each nuclear generating station in Canada and to indicate how these emissions compare with the relevant limitations imposed by the Atomic Energy Control Board as part of its regulatory and licensing program. This report incorporates histograms indicating the annual releases of tritium in air, noble gases, iodine-131, airborne particulates, tritium in water and waterborne gross beta activity for each nuclear generating station. In addition, for Pickering NGS 'A', annual released of carbon-14 are depicted for the years 1986 and 1987. In each case the emission data are compared to the Derived Emission Limit (DEL) in order that the data may be placed in perspective. At present, only Pickering NGS 'A' is required to monitor and report carbon-14 emissions. Environmental monitoring for C-14 is conducted around the Bruce site to determine the environmental impact of its emission and whether effluent monitoring will be necessary in future years. Three nuclear generating stations have been permanently taken out of service during the last few years (Gentilly NGS-1, Douglas Point NGS and NPD NGS). Some small emissions from these sites do still occur, however, due to decontamination and decommissioning operations. (11 tabs., 26 figs.)

Performance assessment of Point Lepreau Generating Station

International Nuclear Information System (INIS)

Alikhan, S.

1991-01-01

The Point Lepreau Generating Station, a 680 MWe CANDU unit, is located about 40 km southwest of the city of Saint John, New Brunswick, Canada. It was declared in-service on 1 February, 1983 and, since then, has demonstrated an average cross capacity factor of over 93% up to the end of 1990. This paper compared the performance of the station with other sister CANDU units and the Light Water Reactors world-wide using the following ten performance indicators, as applicable: - gross capacity factor; - fuel burn-up; - heavy water upkeep; - unplanned reactor trips while critical; - forced outage rate; - fuel handling performance; - derived emission of radioactive effluents to environment; - personnel radiation dose; - industrial safety; - low-level solid radioactive wastes. The paper examines various areas of station activities including management and organization, operations and maintenance, technical support, fuel handling and health physics in order to highlight some of the 'good practices' which are believed to have made a significant contribution towards achieving the demonstrated performance of Point Lepreau G.S. In addition, several areas of potential improvement are discussed in order to maintain and enhance, where practicable, the safety, reliability and economic performance of the station. In this context, a careful review of the operating experiences, both in-house and at other stations, and a judicious application of lessons learned plays a significant role. (author)

Performance assessment of Point Lepreau Generating Station

Energy Technology Data Exchange (ETDEWEB)

Alikhan, S [Point Lepreau Generating Station, Lepreau, NB (Canada)

1991-04-01

The Point Lepreau Generating Station, a 680 MWe CANDU unit, is located about 40 km southwest of the city of Saint John, New Brunswick, Canada. It was declared in-service on 1 February, 1983 and, since then, has demonstrated an average cross capacity factor of over 93% up to the end of 1990. This paper compared the performance of the station with other sister CANDU units and the Light Water Reactors world-wide using the following ten performance indicators, as applicable: - gross capacity factor; - fuel burn-up; - heavy water upkeep; - unplanned reactor trips while critical; - forced outage rate; - fuel handling performance; - derived emission of radioactive effluents to environment; - personnel radiation dose; - industrial safety; - low-level solid radioactive wastes. The paper examines various areas of station activities including management and organization, operations and maintenance, technical support, fuel handling and health physics in order to highlight some of the 'good practices' which are believed to have made a significant contribution towards achieving the demonstrated performance of Point Lepreau G.S. In addition, several areas of potential improvement are discussed in order to maintain and enhance, where practicable, the safety, reliability and economic performance of the station. In this context, a careful review of the operating experiences, both in-house and at other stations, and a judicious application of lessons learned plays a significant role. (author)

Acquisition of wood fuel at the Joseph C. McNeil Generating Station

Energy Technology Data Exchange (ETDEWEB)

Kropelin, W. [Burlington Electric Dept., VT (United States)

1993-12-31

The Joseph C. McNeil Generating Station is the world`s largest single boiler, municipally-owned, wood-fired electrical generating plant. The 50 megawatt McNeil Station is located in Burlington, Vermont and is owned by several Vermont public and private electric utilities. The operator and majority owner is the City of Burlington Electric Department (BED). Wood fuel procurement for the McNeil Station has been conducted in an environmentally sensitive way. Harvesting is carried out in conformance with a comprehensive wood chip harvesting policy and monitored by professional foresters. Unpredictable levels of Station operation require rigid adherence to a wood storage plan that minimizes the risk of over heating and spontaneous combustion of stockpiled fuel.

Refurbishment of Point Lepreau Generating Station

International Nuclear Information System (INIS)

Thompson, P.D.; Jaitly, R.; Ichiyen, N.; Petrilli, M.A.

2004-01-01

NB Power is planning to conduct an 18-month maintenance outage of the Point Lepreau Generating Station (PLGS) beginning in April 2008. The major activity would be the replacement of all 380 Fuel Channel and Calandria Tube Assemblies and the connecting feeder pipes. This activity is referred to as Retube. NB Power would also take advantage of this outage to conduct a number of repairs, replacements, inspections and upgrades (such as rewinding or replacing the generator, replacement of shutdown system trip computers, replacement of certain valves and expansion joints, inspection of systems not normally accessible, etc). These collective activities are referred to as Refurbishment. This would allow the station to operate for an additional 25 to 30 years. The scope of the project was determined from the outcome of a two-year study involving a detailed condition assessment of the station that examined issues relating to ageing and obsolescence. The majority of the plant components were found to be capable of supporting extended operation without needing replacement or changes. In addition to the condition assessment, a detailed review of Safety and Licensing issues associated with extended operation was performed. This included a review of known regulatory and safety issues, comparison of the station against current codes and standards, and comparison of the station against safety related modifications made to more recent CANDU 6 units. Benefit cost analyses (BCA) were performed to assist the utility in determining which changes were appropriate to include in the project scope. As a Probabilistic Safety Assessment (PSA) for PLGS did not exist at the time, a risk baseline for the station had to be determined for use in the BCA. Extensive dialogue with the Canadian Nuclear Safety Commission staff was also undertaken during this phase. A comprehensive Licensing Framework was produced upon which the CNSC provided feedback to NB Power. This feedback was important in terms of

Multi-Unit Aspects of the Pickering Generating Station

Energy Technology Data Exchange (ETDEWEB)

Morison, W. G. [Atomic Energy of Canada Ltd, Sheridan Park, ON (Canada)

1968-04-15

The Pickering nuclear generating station is located on the north shore of Lake Ontario, about 20 miles east of the city of Toronto, Canada. The station has been planned and laid out on an eight-unit station, four units of which have now been authorized for construction. Each of these four units consists of a single heavy-water moderated and cooled CANDU-type reactor and auxiliaries coupled to a single tandem compound turbine generator with a net output of approximately 500 MW(e). The units are identical and are scheduled to come into operation at intervals of one year from 1970 to 1973. The station has been planned with central facilities for: administration maintenance laboratories, stores, change rooms, decontamination and waste management services. A common control centre, cooling water intake and discharge system, and spent fuel storage bay for four units has been arranged. A feature of the multi-unit station is a common containment system. Cost savings in building a number of identical units on the same site result from a single exclusion area, shared engineering costs, equipment purchase contracts for four identical components, and efficient use of construction plant. Operating cost savings are anticipated in the use of a common operating and maintenance staff and spare parts inventory. The plant has been arranged to minimize problems of operating, commissioning and constructing units at the same time on the same site. The layout and construction sequence have been arranged so that the first unit can be commissioned and operated with little or no interference from the construction forces working on succeeding units. During the construction phase barriers will be erected in the common control centre between operating control equipment and that being installed. Operations and construction personnel will enter the plant by separate routes and work in areas separated by physical barriers. (author)

The competitive economics of a middle aged multi unit nuclear generating station

International Nuclear Information System (INIS)

Talbot, K.H.

1994-01-01

In 1992 Ontario Hydro's 15 year old 4 x 850 MWe Candu, Bruce A Nuclear Generating Station was predicted to need considerable capital investment to replace pressure tubes, steam generators and other prematurely ageing equipment in order to restore the station to high performance. Over the subsequent two years the station has undergone 2 major economic assessment studies which have confirmed the economic viability of continued operation of the plant. Declining demand for electricity in Ontario combined with a excess of generating capacity and a need to stabilise electricity rates have however forced significant operational cost reductions and reduced capital availability for rehabilitation work, it's medium and long term future remains in question. This presentation offers a practical illustration of the need to maintain steady high performance from nuclear generating plant via the appropriate life management techniques. The avoidance of mid life infusion of capital is considered as essential if nuclear generation is to successfully survive major changes in economic conditions. 2 tabs., 7 figs

Naturalization of landscaped parkland at Ontario Hydro's Nanticoke generating station

International Nuclear Information System (INIS)

McKenna, G.R.

1998-01-01

The implementation of a program for the naturalization of Nanticoke Park, a 30 hectare area located on the property of Ontario Hydro's Nanticoke Generating Station was discussed. The station, which is located in southern Ontario very near to noted wildlife areas, is the largest coal-fired generating station in North America. Naturalization of Nanticoke Park began with passive naturalization of interior areas. An active naturalization program involving four to five hectare size areas annually was begun in 1997, to be completed over a five -year period. This presentation described the site preparation, planting methods, post-planting tending methods, survival assessment of planted areas, and scientific research initiatives including mulch trials with zebra mussel shells to increase soil moisture. The lessons learned from the two year experiment in determining the optimum planting strategy and methods were described. 7 refs., 1 tab

Electrical system design and reliability at Ontario Hydro nuclear generating stations

Energy Technology Data Exchange (ETDEWEB)

Royce, C. J. [Ontario Hydro, 700 University Avenue, Toronto, Ontario M5G 1X6 (Canada)

1986-02-15

This paper provides an overview of design practice and the predicted and actual reliability of electrical station service Systems at Ontario Nuclear Generating Stations. Operational experience and licensing changes have indicated the desirability of improving reliability in certain instances. For example, the requirement to start large emergency coolant injection pumps resulted in the turbine generator units in a multi-unit station being used as a back-up power supply. Results of reliability analyses are discussed. To mitigate the effects of common mode events Ontario Hydro adopted a 'two group' approach to the design of safety related Systems. This 'two group' approach is reviewed and a single fully environmentally qualified standby power supply is proposed for future use. (author)

Wolf Creek Generating Station containment model

International Nuclear Information System (INIS)

Nguyen, D.H.; Neises, G.J.; Howard, M.L.

1995-01-01

This paper presents a CONTEMPT-LT/28 containment model that has been developed by Wolf Creek Nuclear Operating Corporation (WCNOC) to predict containment pressure and temperature behavior during the postulated events at Wolf Creek Generating Station (WCGS). The model has been validated using data provided in the WCGS Updated Safety Analysis Report (USAR). CONTEMPT-LT/28 model has been used extensively at WCGS to support plant operations, and recently, to support its 4.5% thermal power uprate project

Simulation of the energy - environment economic system power generation costs in power-stations

International Nuclear Information System (INIS)

Weible, H.

1978-09-01

The costs of power generation are an important point in the electricity industry. The present report tries to supply a model representation for these problems. The costs of power generation for base load, average and peak load power stations are examined on the basis of fossil energy sources, nuclear power and water power. The methods of calculation where dynamic investment calculation processes are used, are given in the shape of formulae. From the point of view of long term prediction, power generation cost sensitivity studies are added to the technical, economic and energy-political uncertainties. The sensitivity of models for calculations is examined by deterministic and stochastic processes. In the base load and average region, power generation based on nuclear power and water power is economically more favourable than that from fossilfired power stations. Even including subsidies, this cost advantage is not in doubt. In the peak load region, pumped storage power stations are more economic than fossilfired power stations. (orig.) [de

Automation of steam generator services at public service electric & gas

Energy Technology Data Exchange (ETDEWEB)

Cruickshank, H.; Wray, J.; Scull, D. [Public Service Electric & Gas, Hancock`s Bridge, NJ (United States)

1995-03-01

Public Service Electric & Gas takes an aggressive approach to pursuing new exposure reduction techniques. Evaluation of historic outage exposure shows that over the last eight refueling outages, primary steam generator work has averaged sixty-six (66) person-rem, or, approximately tewenty-five percent (25%) of the general outage exposure at Salem Station. This maintenance evolution represents the largest percentage of exposure for any single activity. Because of this, primary steam generator work represents an excellent opportunity for the development of significant exposure reduction techniques. A study of primary steam generator maintenance activities demonstrated that seventy-five percent (75%) of radiation exposure was due to work activities of the primary steam generator platform, and that development of automated methods for performing these activities was worth pursuing. Existing robotics systems were examined and it was found that a new approach would have to be developed. This resulted in a joint research and development project between Westinghouse and Public Service Electric & Gas to develop an automated system of accomplishing the Health Physics functions on the primary steam generator platform. R.O.M.M.R.S. (Remotely Operated Managed Maintenance Robotics System) was the result of this venture.

77 FR 66484 - PSEG Nuclear LLC; Hope Creek Generating Station and Salem Generating Station, Units 1 and 2...

Science.gov (United States)

2012-11-05

... Power Plant Personnel,'' endorses the Nuclear Energy Institute (NEI) report, NEI 06-11, Revision 1... exclusion, set forth in 10 CFR 51.22(c)(25). Pursuant to 10 CFR 51.22(b), no environmental impact statement... Commission (NRC or the Commission) now or hereafter in effect. The facilities consist of one boiling-water...

75 FR 9956 - PSEG Nuclear LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1...

Science.gov (United States)

2010-03-04

... letter number LR-N09- 0248 and the second enclosure is an environmental impact statement. Based on a... November 3, and November 20, 2009, submittals, with the exception of the environmental impact statement... M. S. Fertel, Nuclear Energy Institute, ADAMS Accession No. ML091410309). The licensee's request for...

Musculoskeletal disorders and mental health-related issues as occupational hazards among dental practitioners in Salem city: A cross-sectional study

Directory of Open Access Journals (Sweden)

Vanita D Revankar

2017-01-01

Full Text Available Background: Like in any other profession, dental surgeons are also afflicted by many occupational health hazards such as Musculoskeletal disorders (MSD and mental health related issues. Aims: To assess the distribution of MSD and mental health related issues amidst dentists in Salem City according to age, sex and number of working hours per week. Objectives: A survey was organized to check the rate of occurrence of these occupational health hazards among dental practitioners in Salem city. Materials and Methods: The study was conducted among one hundred and fifty dentists practicing in Salem City in the form of questionnaire. Dentists were asked about any occupational disease that they suffered related to a musculo–skeletal pain and its location whether in the back, upper limbs or lower limbs. In addition to this,dentists were asked about mental stress that they had experienced. Results: MSD showed higher rate of prevalence compared to mental health related issues. Conclusion: The application of preventive measures is necessary, in view of the high rate of these disorders in the society of dental practitioners.

Socio-economic impacts of nuclear generating stations: summary report on the NRC post-licensing studies

International Nuclear Information System (INIS)

Chalmers, J.; Pijawka, D.; Branch, K.; Bergmann, P.; Flynn, J.; Flynn, C.

1982-07-01

Information is presented concerning the conceptual framework for the assessment of socioeconomic impacts; methodology for the post-licensing case studies; socioeconomic changes due to the construction and operation of nuclear generating stations; public response to the construction and operation of nuclear generating stations; socioeconomic consequences of the accident at Three Mile Island; the significance of socioeconomic change due to the construction and operation of nuclear generating stations; findings of the post-licensing studies relative to the nuclear station impact literature; and implications of the findings for projective assessments and planning studies

Nuclear generating station and heavy water plant cost estimates for strategy studies

International Nuclear Information System (INIS)

Archinoff, G.H.

1979-07-01

Nuclear generating station capital, operating and maintenance costs are basic input data for strategy analyses of alternate nuclear fuel cycles. This report presents estimates of these costs for natural uranium CANDU stations, CANDU stations operating on advanced fuel cycles, and liquid metal fast breeder reactors. Cost estimates for heavy water plants are also presented. The results show that station capital costs for advanced fuel cycles are not expected to be significantly greater than those for natural uranium stations. LMFBR capital costs are expected to be 25-30 percent greater than for CANDU's. (auth)

Next Generation Hydrogen Station Composite Data Products: All Stations (Retail and Non-Retail Combined), Data through Quarter 2 of 2017

Energy Technology Data Exchange (ETDEWEB)

Sprik, Samuel [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Kurtz, Jennifer M [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Ainscough, Christopher D [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Saur, Genevieve [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Peters, Michael C [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

2017-12-05

This publication includes 95 composite data products (CDPs) produced for next generation hydrogen stations with data through the second quarter of 2017. These CDPs include data for all stations in NREL's evaluation (retail and non-retail combined).

Next Generation Hydrogen Station Composite Data Products: All Stations (Retail and Non-Retail Combined), Data through Quarter 4 of 2016

Energy Technology Data Exchange (ETDEWEB)

Sprik, Sam [National Renewable Energy Lab. (NREL), Golden, CO (United States); Kurtz, Jennifer [National Renewable Energy Lab. (NREL), Golden, CO (United States); Ainscough, Chris [National Renewable Energy Lab. (NREL), Golden, CO (United States); Saur, Genevieve [National Renewable Energy Lab. (NREL), Golden, CO (United States); Peters, Michael [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2017-05-31

This publication includes 90 composite data products (CDPs) produced for next generation hydrogen stations with data through the fourth quarter of 2016. These CDPs include data for all stations in NREL's evaluation (retail and non-retail combined).

Next Generation Hydrogen Station Composite Data Products: All Stations (Retail and Non-Retail Combined), Data through Quarter 3 of 2016

Energy Technology Data Exchange (ETDEWEB)

Sprik, Sam [National Renewable Energy Lab. (NREL), Golden, CO (United States); Kurtz, Jennifer [National Renewable Energy Lab. (NREL), Golden, CO (United States); Ainscough, Chris [National Renewable Energy Lab. (NREL), Golden, CO (United States); Saur, Genevieve [National Renewable Energy Lab. (NREL), Golden, CO (United States); Peters, Michael [National Renewable Energy Lab. (NREL), Golden, CO (United States); Jeffers, Matthew [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2017-03-06

This publication includes 87 composite data products (CDPs) produced for next generation hydrogen stations with data through the third quarter of 2016. These CDPs include data for all stations in NREL's evaluation (retail and non-retail combined).

Insulation co-ordination aspects for power stations with generator circuit-breakers

International Nuclear Information System (INIS)

Sanders, M.; Koeppl, G.; Kreuzer, J.

1995-01-01

The generator circuit-breaker (gen. c.b.) located between the generator and the step-up transformer, is now being applied world-wide. It has become a recognized electrical component of power stations which is largely due to economical advantages and increased power station availability. Technical protection considerations for power stations have always been the reason for discussion and the object of improvement. With the use of a gen. c.b., some points of view need to be considered anew. Not only the protection system in case of fault conditions will be influenced, but also the insulation co-ordination philosophy. Below the results of some calculations concerning expected overvoltages are presented. These calculations are based on a transformer rated 264/15.5kV, 220 MVA. But the results are transferable to other power plants. Some measurements carried out on a transformer of the same rating complement the calculations. The findings may contribute to an improvement in insulation co-ordination and protection of the electrical system generator--step-up transformer

Ontario Hydro Pickering Generating Station fuel handling system performance

International Nuclear Information System (INIS)

Underhill, H.J.

1986-01-01

The report briefly describes the Pickering Nuclear Generating Station (PNGS) on-power fuel handling system and refuelling cycle. Lifetime performance parameters of the fuelling system are presented, including station incapability charged to the fuel handling system, cost of operating and maintenance, dose expenditure, events causing system unavailability, maintenance and refuelling strategy. It is concluded that the 'CANDU' on-power fuelling system, by consistently contributing less than 1% to the PNGS incapability, has been credited with a 6 to 20% increase in reactor capacity factor, compared to off-power fuelling schemes. (author)

Electricity Generation Through the Koeberg Nuclear Power Station of Eskom in South Africa

International Nuclear Information System (INIS)

Dladla, G.; Joubert, J.

2015-01-01

The poster provides information on the process of nuclear energy generation in a nuclear power plant in order to produce electricity. Nuclear energy currently provides approximately 11% of the world’s electricity needs, with Koeberg Nuclear Power Station situated in the Western Cape providing 4.4% of South Africa’s electricity needs. As Africa’s first nuclear power station, Koeberg has an installed capacity of 1910 MW of power. Koeberg’ s total net output is 1860 MW. While there are significant differences, there are many similarities between nuclear power plants and other electrical generating facilities. Uranium is used for fuel in nuclear power plants to make electricity. With the exception of solar, wind, and hydroelectric plants, all others including nuclear plants convert water to steam that spins the propeller-like blades of a turbine that spins the shaft of a generator. Inside the generator coils of wire and magnetic fields interact to create electricity. The energy needed to boil water into steam is produced in one of two ways: by burning coal, oil, or gas (fossil fuels) in a furnace or by splitting certain atoms of uranium in a nuclear energy plant. The uranium fuel generates heat through a controlled fission process fission, which is described in this poster presentation. The Koeberg Nuclear Power Station is a Pressurised water reactor (PWR). The operating method and the components of the Koeberg Power Station are also described. The nuclear waste generated at a nuclear power station is described under three headings— low-level waste, intermediate-level waste and used or spent fuel, which can be solid, liquid or gaseous. (author)

Tritium in groundwater investigation at the Pickering Nuclear Generating Station

International Nuclear Information System (INIS)

DeWilde, J.; Yu, L.; Wootton, R.; Belanger, D.; Hansen, K.; McGurk, E.; Teare, A.

2001-01-01

Ontario Power Generation Inc. (OPG) investigated tritium in groundwater at the Pickering Nuclear Generating Station (PNGS). The objectives of the study were to evaluate and define the extent of radionuclides, primarily tritium, in groundwater, investigate the causes or sources of contamination, determine impacts on the natural environment, and provide recommendations to prevent future discharges. This paper provides an overview of the investigations conducted in 1999 and 2000 to identity the extent of the tritium beneath the site and the potential sources of tritium released to the groundwater. The investigation and findings are summarized with a focus on unique aspects of the investigation, on lessons learned and benefits. Some of the investigative techniques discussed include process assessments, video inspections, hydrostatic and tracer tests, Helium 3 analysis for tritium age dating, deuterium and tritium in soil analysis. The investigative techniques have widespread applications to other nuclear generating stations. (author)

Prevalence of early childhood caries and its risk factors in 18-72 month old children in Salem, Tamil Nadu.

Science.gov (United States)

Stephen, Arokiaraj; Krishnan, Ramesh; Ramesh, Maya; Kumar, Vasaviah Suresh

2015-01-01

Early childhood caries (ECC) is one of the most common dental diseases among the preschoolers, leading to suboptimal health. A study was planned to evaluate the prevalence of ECC in preschool children in the age group between 18 and 72 months and its relationship with parent's education and socioeconomic status of the family. This cross-sectional study was conducted among 2771 children selected randomly, in the age group 18-72 months and attending playschools and primary schools in urban, semi-urban, and rural areas of Salem, Tamil Nadu. A modified Winter et al. questionnaire and a proforma were used for collecting information on each child. The completed questionnaire and proformas were statistically analyzed and evaluated. The statistical analysis was done using Student's t-test and analysis of variance (ANOVA) to obtain mean values. The prevalence of ECC in Salem was 16% with a mean dfs of 5.23 ± 1. Prevalence was high among the children of low socioeconomic status group and the children of working mothers, with a mean dfs of 10.47. The prevalence of ECC was 16% in Salem, Tamil Nadu. ECC was seen more in children of working mothers, lower parental education, and lower socioeconomic groups.

DESIGNING AND OPPORTUNITY FUEL WITH BIOMASS AND TIRE-DERIVED FUEL FOR COFIRING AT WILLOW ISLAND GENERATING STATION AND COFIRING SAWDUST WITH COAL AT ALBRIGHT GENERATING STATION

Energy Technology Data Exchange (ETDEWEB)

K. Payette; D. Tillman

2004-06-01

During the period July 1, 2000-March 31, 2004, Allegheny Energy Supply Co., LLC (Allegheny) conducted an extensive demonstration of woody biomass cofiring at its Willow Island and Albright Generating Stations. This demonstration, cofunded by USDOE and Allegheny, and supported by the Biomass Interest Group (BIG) of EPRI, evaluated the impacts of sawdust cofiring in both cyclone boilers and tangentially-fired pulverized coal boilers. The cofiring in the cyclone boiler--Willow Island Generating Station Unit No.2--evaluated the impacts of sawdust alone, and sawdust blended with tire-derived fuel. The biomass was blended with the coal on its way to the combustion system. The cofiring in the pulverized coal boiler--Albright Generating Station--evaluated the impact of cofiring on emissions of oxides of nitrogen (NO{sub x}) when the sawdust was injected separately into the furnace. The demonstration of woody biomass cofiring involved design, construction, and testing at each site. The results addressed impacts associated with operational issues--capacity, efficiency, and operability--as well as formation and control of airborne emissions such as NO{sub x}, sulfur dioxide (SO{sub 2}2), opacity, and mercury. The results of this extensive program are detailed in this report.

Abundance and diversity of Odonata in temporary water bodies of Coimbatore and Salem districts in Tamil Nadu

Directory of Open Access Journals (Sweden)

R. Arulprakash

2010-07-01

Full Text Available Odonata diversity was assessed in 13 temporary water bodies of Coimbatore and Salem districts in Tamil Nadu. Assessment revealed the presence of 21 species of Odonata (14 species of Anisoptera and seven species of Zygoptera belonging to 17 genera under four families. Libellulidae (Anisoptera was represented by the maximum number of species and individuals. Pantala flavescens (Libellulidae was the most abundant among 21 species. Among the temporary water bodies, the maximum number of individuals as well as species was recorded from Utkulam tank (Coimbatore district. Odonata diversity was higher in Kamalapuram tanks 1 and 2 (Salem district and lower in Ukkadam tank (Coimbatore District. Diplacodes trivialis (Rambur, Orthetrum sabina (Drury and Pantala flavescens (Fabricius were identified as temporary water body specialists because of their presence in all the 13 temporary water bodies sampled.

Valve maintainability in CANDU-PHW nuclear generating stations

International Nuclear Information System (INIS)

Pothier, N.E.; Crago, W.A.

1977-09-01

Design, application, layout and administrative factors which affect valve maintainability in CANDU-PHW power reactors are identified and discussed. Some of these are illustrated by examples based on prototype reactor operation experience. Valve maintainability improvements resulting from laboratory development and maintainability analysis, have been incorporated in commercial CANDU-PHW nuclear generating stations. These, also, are discussed and illustrated. (author)

Determination of reliability criteria for standby diesel generators at a nuclear power station

International Nuclear Information System (INIS)

Evans, M.G.K.

1987-01-01

The requirement for standby diesel generators at nuclear power stations is developed and a probabilistic approach used to define the reliability parameters. The present criteria used when ordering a diesel generator are compared with the testing required by the regulatory body and the most likely requirement following an accident. The impact of this on the diesels at a particular station and the root cause of failures are discussed. (orig.)

Analysis of steam generator tube sections removed from Gentilly-2 nuclear generating station

International Nuclear Information System (INIS)

Semmler, J.; Lockley, A.J.; Doyon, D.

2010-01-01

deposition rate in the steam generators from 2001 to 2009 were estimated and compared to the estimated values from 1983 (station commissioning) to 2001. This paper presents a summary of steam generator tube characterization results and describes how the data on the oxide deposition rate were correlated to the changes in station operating practices. These data demonstrate the benefits that resulted from recent changes to station chemistry and operational practices. (author)

76 FR 24064 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice...

Science.gov (United States)

2011-04-29

... Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice of Issuance of Renewed... Company (licensee), the operator of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS... Plants: Supplement 43, Regarding Palo Verde Nuclear Generating Station,'' issued January 2011, discusses...

Navajo Generating Station and Air Visibility Regulations: Alternatives and Impacts

Energy Technology Data Exchange (ETDEWEB)

Hurlbut, D. J.; Haase, S.; Brinkman, G.; Funk, K.; Gelman, R.; Lantz, E.; Larney, C.; Peterson, D.; Worley, C.; Liebsch, E.

2012-01-01

Pursuant to the Clean Air Act, the U.S. Environmental Protection Agency (EPA) announced in 2009 its intent to issue rules for controlling emissions from Navajo Generating Station that could affect visibility at the Grand Canyon and at several other national parks and wilderness areas. The final rule will conform to what EPA determines is the best available retrofit technology (BART) for the control of haze-causing air pollutants, especially nitrogen oxides. While EPA is ultimately responsible for setting Navajo Generating Station's BART standards in its final rule, it will be the U.S. Department of the Interior's responsibility to manage compliance and the related impacts. This study aims to assist both Interior and EPA by providing an objective assessment of issues relating to the power sector.

75 FR 52045 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental...

Science.gov (United States)

2010-08-24

... Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental Assessment and Finding of No.... NPF-74, issued to Arizona Public Service Company (APS, the licensee), for operation of Palo Verde... Statement for the Palo Verde Nuclear Generating Station, NUREG-0841, dated February 1982. Agencies and...

A study of wet deposition of atmospheric tritium releases at the Ontario Power Generation, Pickering Nuclear Generating Station

International Nuclear Information System (INIS)

Crooks, G.; DeWilde, J.; Yu, L.

2001-01-01

The Ontario Power Generation,Pickering Nuclear Generating Station (PNGS) has been investigating deposition of atmospheric releases of tritium on their site. This study has included numerical dispersion modelling studies conducted over the past three years, as well as an ongoing field monitoring study. The following paper will present results of the field monitoring study and make comparisons to the numerical modelling. The results of this study could be of potential use to nuclear stations in quantifying tritium deposition in near field regions where building wake effects dominate pollutant dispersion

Groundwater resource exploration in Salem district, Tamil Nadu using GIS and remote sensing

Science.gov (United States)

Maheswaran, G.; Selvarani, A. Geetha; Elangovan, K.

2016-03-01

Since last decade, the value per barrel of potable groundwater has outpaced the value of a barrel of oil in many areas of the world. Hence, proper assessment of groundwater potential and management practices are the needs of the day. Establishing relationship between remote sensing data and hydrologic phenomenon can maximize the efficiency of water resources development projects. Present study focuses on groundwater potential assessment in Salem district, Tamil Nadu to investigate groundwater resource potential. At the same, all thematic layers important from ground water occurrence and movement point of view were digitized and integrated in the GIS environment. The weights of different parameters/themes were computed using weighed index overlay analysis (WIOA), analytic hierarchy process (AHP) and fuzzy logic technique. Through this integrated GIS analysis, groundwater prospect map of the study area was prepared qualitatively. Field verification at observation wells was used to verify identified potential zones and depth of water measured at observation wells. Generated map from weighed overlay using AHP performed very well in predicting the groundwater surface and hence this methodology proves to be a promising tool for future.

The Salem Smart Power Center: An Assessment of Battery Performance and Economic Potential

Energy Technology Data Exchange (ETDEWEB)

Balducci, Patrick J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Alam, M. J.E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Viswanathan, Vilayanur [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wu, Di [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Crawford, Aladsair J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mongird, Kendall [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Weimar, Mark R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Somani, Abhishek [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Whitener, Kevin [Portland General Electric, OR (United States)

2017-09-21

This paper presents an assessment of the economic potential of a 5 MW/1.25 MWh Energy Storage System (ESS) installed at the Salem Smart Power Center (SSPC), a smart grid technology demonstration facility owned and operated by Portland General Electric (PGE) in Salem, Oregon. The ESS and the grid conditions in which it operates were modeled using Pacific Northwest National Laboratory’s Battery Storage Evaluation Tool (BSET) to explore tradeoffs between services, and to develop optimal control strategies. This assessment monetized the value derived from nine services the SSPC could provide to PGE and the customers it serves. The ESS and the grid conditions in which it operates were modeled using PNNL’s in-house optimization tool BSET to explore tradeoffs between services, and to develop optimal control strategies. The analysis resulted in a number of lessons that provide crucial insights into the practical application of ESS, including; The SSPC, which was originally conceived as a research and test facility and built with the prevailing maturity technology level, was built at a cost ($20.4 million) that exceeds current day prices ($5.4 million) for a similarly designed and built 5 MW/1.25 MWh system; In terms of economic operation, the SSPC is currently underutilized, deployed only for primary frequency response. PNNL modeling indicates that optimal operation of the ESS could generate an additional value of $2.3 million over 20 years. It should also be noted that primary frequency response is the highest benefit application but requires a response from the SSPC only 17 hours each year. While optimally engaged, the ESS would provide arbitrage and ancillary services 78 percent of the time, but those services generate only 27 percent of the total value; Participation in Western EIM represents an interesting opportunity for PGE with a potential to generate $2.1 million value in PV terms over 20 years in the 5-min real-time market; With an energy to power ratio of

Cost comparison of 4x500 MW coal-fuelled and 4x850 MW CANDU nuclear generating stations

International Nuclear Information System (INIS)

Costa, M.

1981-01-01

The lifetime costs for a 4x850 MW CANDU generating station are compared to those for 4x500 MW bituminous coal-fuelled generating stations. Two types of coal-fuelled stations are considered; one burning U.S. coal which includes flue gas desulfurization and one burning Western Canadian coal. Current estimates for the capital costs, operation and maintenance costs, fuel costs, decommissioning costs and irradiated fuel management costs are shown. The results show: (1) The accumulated discounted costs of nuclear generation, although initially higher, are lower than coal-fuelled generation after two or three years. (2) Fuel costs provide the major contribution to the total lifetime costs for coal-fuelled stations whereas capital costs are the major item for the nuclear station. (3) The break even lifetime capacity factor between nuclear and U.S. coal-fuelled generation is projected to be 5%; that for nuclear and Canadian coal-fuelled generation is projected to be 9%. (4) Large variations in the costs are required before the cost advantage of nuclear generation is lost. (5) Comparison with previous results shows that the nuclear alternative has a greater cost advantage in the current assessment. (6) The total unit energy cost remains approximately constant throughout the station life for nuclear generation while that for coal-fuelled generation increases significantly due to escalating fuel costs. The 1978 and 1979 actual total unit energy cost to the consumer for several Ontario Hydro stations are detailed, and projected total unit energy costs for several Ontario Hydro stations are shown in terms of escalated dollars and in 1980 constant dollars

Water use/reuse and wastewater management practices at selected Canadian coal fired generating stations

Energy Technology Data Exchange (ETDEWEB)

Kissel, R.

1984-08-01

Recommended Codes of Practice are currently being developed by Environment Canada aimed at ensuring that the aquatic environment is not significantly impacted upon by wastewater discharges from steam electric generating stations. A study was carried out to: develop a reliable data base of the physical and chemical characteristics of water and wastewater streams at representative generating stations; study advanced water reuse/recirculation and wastewater management to evaluate their potential future use in power generating stations; and to examine and evaluate the relevant aspects of best practical technology as proposed by Environment Canada in the Recommended Codes of Practice. Studies were carried out at Dalhousie Generating Station (GS), New Brunswick, Poplar River GS, Saskatchewan, Battle River GS, Alberta, and Milner GS, Alberta. The studies included on-site flow monitoring and sampling, chemical analyses, treatability studies and engineering analyses of water and wastewater systems. Extensive chemical characterizations of the water and wastewater streams were completed. Some problems were identified with the recirculating bottom ash system at Dalhousie which was a significant wastewater producer, coal pile runoff which caused significant wastewater, and iron which was the principal discharge criteria metal. 14 refs., 41 figs., 2 tabs.

Geophysical exploration for uranium in Suryamalai batholith, Salem District, Tamil Nadu, India

Energy Technology Data Exchange (ETDEWEB)

Anantharaman, K B; Sethuram, S [Department of Atomic Energy, Hyderabad (India). Atomic Minerals Div.

1984-08-01

Abnormally radioactive granitoids are targets of uranium exploration because they can be the source for uranium deposits as well as the hosts. Significant uranium mineralization is known to occur northwest of Suryamalai granite batholith at Kullampatti situated 40 km southwest of Salem. This paper embodies the geophysical exploration for uranium, using results of magnetic and radiometric methods. The investigations revealed that uranium mineralization is structurally controlled and such structures have magnetic expression. Incidentally, correlation of anomalous content of W with U is also brought to light.

33 CFR 165.554 - Security Zone; Three Mile Island Generating Station, Susquehanna River, Dauphin County...

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Security Zone; Three Mile Island... Areas Fifth Coast Guard District § 165.554 Security Zone; Three Mile Island Generating Station... waters of the Susquehanna River in the vicinity of the Three Mile Island Generating Station bounded by a...

A Renewably Powered Hydrogen Generation and Fueling Station Community Project

Science.gov (United States)

Lyons, Valerie J.; Sekura, Linda S.; Prokopius, Paul; Theirl, Susan

2009-01-01

The proposed project goal is to encourage the use of renewable energy and clean fuel technologies for transportation and other applications while generating economic development. This can be done by creating an incubator for collaborators, and creating a manufacturing hub for the energy economy of the future by training both white- and blue-collar workers for the new energy economy. Hydrogen electrolyzer fueling stations could be mass-produced, shipped and installed in collaboration with renewable energy power stations, or installed connected to the grid with renewable power added later.

AECB staff annual assessment of the Point Lepreau Nuclear Generating Station

International Nuclear Information System (INIS)

1997-06-01

The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of reactor safety at the Point Lepreau Generating Station in 1996. Point Lepreau operated safely but the worsening trends in NB Power's safety performance leads to the conclusion that urgent action is required. NB Power is required to report formally to the AECB on progress with measures to improve safety management every six months. Further licensing action will be taken on NB Power if it fails to make the improvements

76 FR 1197 - Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of...

Science.gov (United States)

2011-01-07

... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-528, 50-529, 50-530; NRC-2009-0012] Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of the Final Supplement 43... of operation for the Palo Verde Nuclear Generating Station (PVNGS). Possible alternatives to the...

Characterization of solid radwaste generated at Virginia Power's Surry and North Anna stations

International Nuclear Information System (INIS)

Lippard, D.W.; Elguindy, H.; Nelson, R.A.

1987-01-01

This paper describes the results of a study on characterization of the major constituents of the solid radwaste generated at Virginia Power's North Anna and Surry Power Stations. The characterization consisted of identifying the individual constituents of the dry active waste (DAW) and estimating the fraction of the total DAW (both weight and volume) made up by each constituent. The analysis of the characterization of solid waste streams generated at both North Anna and Surry stations has lead to recommending techniques for both source minimization and waste volume reduction

33 CFR 165.552 - Security Zone; Oyster Creek Generation Station, Forked River, Ocean County, New Jersey.

Science.gov (United States)

2010-07-01

... Generation Station, Forked River, Ocean County, New Jersey. 165.552 Section 165.552 Navigation and Navigable... Coast Guard District § 165.552 Security Zone; Oyster Creek Generation Station, Forked River, Ocean... part. (2) No person or vessel may enter or navigate within this security zone unless authorized to do...

Strategy for success in maintenance management at Point Lepreau nuclear generating station

International Nuclear Information System (INIS)

White, R.M.

1987-01-01

Improvements in availability of the station and in productivity of workers were achieved at Point Lepreau Nuclear Generating Station through implementation of a Maintenance Management System, which incorporates work planning and outage management techniques. Eight software systems on a VAX 11/70 minicomputer control work orders, temporary and permanent design changes, parts and material inventories, time keeping, and project management. All maintenance is coordinated through a regular planning meeting

AECB staff annual assessment of the Pickering A and B Nuclear Generating Stations for the year 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The Pickering Nuclear Generating Station (PNGS) is located on the north shore of Lake Ontario, about 32 km east of downtown Toronto. It consists of two stations, PNGS-A and PNGS-B. Each station contains four reactor units. PNGS-A consists of Units 1 to 4, while PNGS-B consists of Units 5 to 8. Each unit can generate about 540 megawatts of electricity. All eight units are located within a single enclosure. Ontario Hydro`s Pickering Nuclear Division has assigned one Station Director with authority over both stations, but each station has its own organization. AECB issue a separate operating licence for each station. This report presents the Atomic Energy Control Board staff assessment of the Pickering stations` safety performance in 1994 and other aspects that they consider to have significant impact on nuclear safety. AECB based their conclusions on their observations, audits, inspections and review of information that Ontario Hydro submits to them as required by the station Operating Licences. 11 tabs., 8 figs.

AECB staff annual assessment of the Pickering A and B Nuclear Generating Stations for the year 1994

International Nuclear Information System (INIS)

1995-06-01

The Pickering Nuclear Generating Station (PNGS) is located on the north shore of Lake Ontario, about 32 km east of downtown Toronto. It consists of two stations, PNGS-A and PNGS-B. Each station contains four reactor units. PNGS-A consists of Units 1 to 4, while PNGS-B consists of Units 5 to 8. Each unit can generate about 540 megawatts of electricity. All eight units are located within a single enclosure. Ontario Hydro's Pickering Nuclear Division has assigned one Station Director with authority over both stations, but each station has its own organization. AECB issue a separate operating licence for each station. This report presents the Atomic Energy Control Board staff assessment of the Pickering stations' safety performance in 1994 and other aspects that they consider to have significant impact on nuclear safety. AECB based their conclusions on their observations, audits, inspections and review of information that Ontario Hydro submits to them as required by the station Operating Licences. 11 tabs., 8 figs

Commercial grade item (CGI) dedication of generators for nuclear safety related applications

International Nuclear Information System (INIS)

Das, R.K.; Hajos, L.G.

1993-01-01

The number of nuclear safety related equipment suppliers and the availability of spare and replacement parts designed specifically for nuclear safety related application are shrinking rapidly. These have made it necessary for utilities to apply commercial grade spare and replacement parts in nuclear safety related applications after implementing proper acceptance and dedication process to verify that such items conform with the requirements of their use in nuclear safety related application. The general guidelines for the commercial grade item (CGI) acceptance and dedication are provided in US Nuclear Regulatory Commission (NRC) Generic Letters and Electric Power Research Institute (EPRI) Report NP-5652, Guideline for the Utilization of Commercial Grade Items in Nuclear Safety Related Applications. This paper presents an application of these generic guidelines for procurement, acceptance, and dedication of a commercial grade generator for use as a standby generator at Salem Generating Station Units 1 and 2. The paper identifies the critical characteristics of the generator which once verified, will provide reasonable assurance that the generator will perform its intended safety function. The paper also delineates the method of verification of the critical characteristics through tests and provide acceptance criteria for the test results. The methodology presented in this paper may be used as specific guidelines for reliable and cost effective procurement and dedication of commercial grade generators for use as standby generators at nuclear power plants

Energy and exergy analysis of electricity generation from natural gas pressure reducing stations

International Nuclear Information System (INIS)

Neseli, Mehmet Alparslan; Ozgener, Onder; Ozgener, Leyla

2015-01-01

Highlights: • Forecasting the recoverable energy from natural gas pressure reduction stations. • Electricity generation through pressure reduction stations via turboexpanders. • A thermodynamics analysis of PRS. - Abstract: Electricity generation or power recovery through pressure reduction stations (PRS) for general use has not been realized in Izmir. The main objective of the present study was to do a case study for calculating electricity to be recovered in one natural gas pressure reduction stations in Izmir. It is the first forecasting study to obtain energy from natural gas pressure-reducing stations in Izmir. Energy can be obtained from natural gas PRS with turbo-expanders instead of using throttle valves or regulators from the PRS. The exergy performance of PRS with TE is evaluated in this study. Exergetic efficiencies of the system and components are determined to assess their individual performances. Based upon pressure change and volumetric flow rate, it can be obtained by recovering average estimated installed capacity and annual energy 494.24 kW, 4113.03 MW h, respectively. In terms of estimated installed capacity power and annual energy, the highest level is 764.88 kW, approximately 6365.34 MW h, in Aliaga PRS. Also it can be seen that CO 2 emission factor average value is 295.45 kg/MW h

75 FR 76040 - Dell Products LP, Winston-Salem (WS-1) Division, Including On-Site Leased Workers From Adecco...

Science.gov (United States)

2010-12-07

..., Winston-Salem, North Carolina. The notice was published in the Federal Register on April 23, 2010 (75 FR... from Staffing Solutions, South East, and Omni Resources and Recovery. The notices were published in the... firm. The workers are engaged in employment related to the production of desktop computers. New...

76 FR 2710 - Dell Products LP, Winston-Salem (WS-1) Division, Including On-Site Leased Workers From Adecco...

Science.gov (United States)

2011-01-14

..., APN and ICONMA, Winston-Salem, North Carolina. The notice was published in the Federal Register on... Seaton Corporation. The notices were published on the Federal Register on April 19, 2010 (75 FR 20385... workers are engaged in employment related to the production of desktop computers. New information shows...

Experience on environmental qualification of safety-related components for Darlington Nuclear Generating Station

International Nuclear Information System (INIS)

Yu, A.S.; Kukreti, B.M.

1987-01-01

The proliferation of Nuclear Power Plant safety concerns has lead to increasing attention over the Environmental Qualification (EQ) of Nuclear Power Plant Safety-Related Components to provide the assurance that the safety related equipment will meet their intended functions during normal operation and postulated accident conditions. The environmental qualification of these components is also a Licensing requirement for Darlington Nuclear Generating Station. This paper provides an overview of EQ and the experience of a pilot project, in the qualification of the Main Moderator System safety-related functions for the Darlington Nuclear Generating Station currently under construction. It addresses the various phases of qualification from the identification of the EQ Safety-Related Components List, definition of location specific service conditions (normal, adbnormal and accident), safety-related functions, Environmental Qualification Assessments and finally, an EQ system summary report for the Main Moderator System. The results of the pilot project are discussed and the methodology reviewed. The paper concludes that the EQ Program developed for Darlington Nuclear Generating Station, as applied to the qualification of the Main Moderator System, contained all the elements necessary in the qualification of safety-related equipment. The approach taken in the qualification of the Moderator safety-related equipment proves to provide a sound framework for the qualification of other safety-related components in the station

Computer functions in overall plant control of candu generating stations

International Nuclear Information System (INIS)

Chou, Q.B.; Stokes, H.W.

1976-01-01

System Planning Specifications form the basic requirements for the performance of the plant including its response to abnormal situations. The rules for the computer control programs are devised from these, taking into account limitations imposed by the reactor, heat transport and turbine-generator systems. The paper outlines these specifications and the limitations imposed by the major items of plant equipment. It describes the functions of each of the main programs, their interactions and the control modes used in the existing Ontario Hydro's nuclear station or proposed for future stations. Some simulation results showing the performance of the overall unit control system and plans for future studies are discussed. (orig.) [de

FIND: Douglas Point Nuclear Generating Station, Units 1 and 2

International Nuclear Information System (INIS)

Moore, M.M.

1975-12-01

This index is presented as a guide to microfiche items 1 through 136 in Docket 50448, which was assigned to Potomac Electric Power Company's Application for Licenses to construct and operate Douglas Point Nuclear Generating Station, Units 1 and 2. Information received from August, 1973 through July, 1975 is included

Environmental radiation monitoring data for Point Lepreau Generating Station, 1988. Annual publication

Energy Technology Data Exchange (ETDEWEB)

Sutherland, J K

1989-01-01

Annual report presenting a compilation of the 1988 environmental radiation monitoring program data from samples collected around the Point Lepreau Nuclear Generating Station (PLNGS) and at reference stations remote from PLNGS. About 1,700 analyses were made on 1,200 samples to monitor environmental radiation, including air filters, airborne water vapour, sea water, well water, milk, beach sediments, clams, fish, lobster, dulse, crabs, scallops and lichen. Background radiation is measured by thermoluminescence dosimetry.

Environmental radiation monitoring data for Point Lepreau Generating Station, 1987. Annual publication

Energy Technology Data Exchange (ETDEWEB)

Sutherland, J K

1988-01-01

Annual report presenting a compilation of the 1987 environmental radiation monitoring program data from samples collected around the Point Lepreau Nuclear Generating Station (PLNGS) and at reference stations remote from PLNGS. About 1,800 analyses were made on 1,300 samples to monitor environmental radiation, including air filters, airborne water vapour, sea water, well water, milk, beach sediments, clams, fish, lobster, dulse, crabs, scallops and periwinkles. Background radiation is measured by thermoluminescence dosimetry.

Eddy current magnetic bias x-probe qualification and inspection of steam generator Monel 400 tubing in Pickering Nuclear Generating Station

International Nuclear Information System (INIS)

Lepine, B.A.; Van Langen, J.; Obrutsky, L.

2006-01-01

This paper presents an overview of the x-probe MB 350 eddy current inspection array probe, for detection of open OD axial crack-like flaws in Monel 400 tubes at Pickering Nuclear Generating Station. This report contains a selection of inspection results from the field inspections performed with this probe during the 2003 and 2004 period at Pickering Nuclear Generating Station A and B. During the 2003 in-service eddy current inspection results of Pickering Nuclear Generating Station A (PNGS-A) Unit 2, a 13 mm (0.5 inch) long axial indication was detected by the CTR1 bobbin and CTR2-C4 array probes in Tube R25-C52 of Steam Generator (SG) 11 in the hot leg sludge pile region. An experimental magnetic bias X-probe, specially designed by Zetec for inspection of Monel 400 tubing, was deployed and the indication was characterized as a potential out diameter (OD) axially oriented crack. Post-inspection tube pulling and destructive examination confirmed the presence of an Environmentally Assisted Crack (EAC), approximately 80% deep and 13mm long. Due to the significance of this discovery, Ontario Power Generation (OPG) requested AECL to initiate a program for qualification of the X-probe MB 350 for the detection of OD axial cracks in medium to high magnetic permeability μ r Monel 400 PNGS-A and B steam generator tubing at different locations. The X-probe MB 350 subsequently has been deployed as a primary inspection probe for crack detection for PNGS steam generators. (author)

Aerial radiological survey of the Rancho Seco Nuclear Generating Station, Clay Station, California, 18 January 1980 to 1 February 1980

International Nuclear Information System (INIS)

1980-11-01

An airborne radiological survey of 260 km 2 area centered over the Rancho Seco Nuclear Generating Station was made 18 January through 1 February 1980. Detected radioisotopes and their associated gamma ray exposure rates were consistent with that expected from normal background emitters, except directly over the station. Count rates observed at 90 m altitude were converted to exposure rates at 1 m above the ground and are presented in the form of an isopleth map

IEEE Std 649-1980: IEEE standard for qualifying Class 1E motor control centers for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard describes the basic principles, requirements, and methods for qualifying Class 1E motor control centers for outside containment applications in nuclear power generating stations. Qualification of motor control centers located inside containment in a nuclear power generating station is beyond the scope of this standard. The purpose of this standard is (1) to define specific qualification requirements for Class 1E motor control centers in accordance with the more general qualification requirements of IEEE Std 323-1974, IEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations; (2) to provide guidance in establishing a qualification program for demonstrating the design adequacy of Class 1E motor control centers in nuclear power generating station applications

Limerick Nuclear Generating Station vibration monitoring system

International Nuclear Information System (INIS)

Mikulski, R.

1988-01-01

Philadelphia Electric Company utilizes a vibration monitoring computer system at its Limerick Nuclear Generating Station to evaluate machine performance. Performance can be evaluated through instantaneous sampling, online static and transient data. The system functions as an alarm monitor, displaying timely alarm data to the control area. The passage of time since the system's inception has been a learning period. Evaluation through continuous use has led to many enhancements in alarm handling and in the acquisition and display of machine data. Due to the system's sophistication, a routine maintenance program is a necessity. This paper describes the system's diagnostic tools and current utilization. System development and maintenance techniques will also be discussed

AECB staff annual assessment of the Darlington Nuclear Generating Station for the year 1996

International Nuclear Information System (INIS)

1997-06-01

The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of safety at the Darlington Nuclear Generating Station for 1996. Ontario Hydro operated the station in a safe manner in 1996. All four special safety systems were fully available 100 percent of the time. There were more problems that affected the safety support systems in 1996 than in the previous year

Pre-license team training at San Onofre Nuclear Generating Station

International Nuclear Information System (INIS)

Freers, S.M.; Hyman, M.

1987-01-01

Team Training at San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 has been developed to enhance the performance of station operations personnel. The FACT Training Program (Formality, Attention to Detail, Consistency and Team Effort) is the common denominator for operations team training. Compliance with good operating practices is enhanced by operators working as a team toward the same goal, using the same language, practicing the same operating and communication skills, possessing a clear understanding of individual roles and responsibilities of team members and practicing attention to detail in every task. These elements of effective teamwork are emphasized by the processes and criteria used in the Pre-License Operator Training Program at SONGS

Vinten exposure measurements of the Salem Unit 1 lower core barrel

International Nuclear Information System (INIS)

Glennon, P.T.

1988-01-01

On November 6, 1987, the lower core barrel of Salem Unit I was removed from the reactor vessel and placed in the refueling pool as part of the unit's ten year inspection program. This paper deals with the supporting actions of the dosimetry group of PSE ampersand G. Prior to the move of the lower core barrel, Westinghouse predicted dose rates at one foot in water as a function of axial distance along the core barrel. This prediction was used in planning the health physics requirements associated with the move. It was agreed that a measurement of the axial dose rates would either lend confidence to the predictions or identify weaknesses in them

Steam generator replacement at Surry Power Station

International Nuclear Information System (INIS)

McKay, H.S.

1982-01-01

The purposes of the steam generator repair program at Surry Power Station were to repair the tube degradation caused by corrosion-related phenomena and to restore the integrity of the steam generators to a level equivalent to new equipment. The repair program consisted of (1) replacing the existing lower-shell assemblies with new ones and (2) adding new moisture separation equipment to the upper-shell assemblies. These tasks required that several pieces of reactor coolant piping, feedwater piping, main steam piping, and the steam generator be cut and refurbished for reinstallation after the new lower shell was in place. The safety implications and other potential effects of the repair program both during the repair work and after the unit was returned to power were part of the design basis of the repair program. The repair program has been completed on Unit 2 without any adverse effects on the health and safety of the general public or to the personnel engaged in the repair work. Before the Unit 1 repair program began, a review of work procedures and field changes for the Unit 2 repair was conducted. Several major changes were made to avoid recurrence of problems and to streamline procedures. Steam generator replacements was completed on June 1, 1981, and the unit is presently in the startup phase of the outrage

China's CO2 emissions from power generating stations: A first exploration

OpenAIRE

Du, Limin; Hanley, Aoife; Rehdanz, Katrin

2014-01-01

Our analysis is the first of its kind to explore patterns of subsidization and CO2 emissions in China's electricity producing sector. Applying data for all power plants across China and controlling for the age, capacity and location of generating stations, we find that plants attracting a higher government subsidy are also worryingly the plants generating a disproportionate share of CO2 emissions. This distortion is incongruent with China's aspiration for a greener economy but may be eliminat...

S.I. 1987 No. 2182, The Electricity Generating Stations and Overhead Lines (Inquiries Procedure) Rules 1987

International Nuclear Information System (INIS)

1987-01-01

These Rules, which came into force on 14 January 1988, make new provision for the procedure for any public inquiry held pursuant to Section 34 of the Electricity Act 1957 in relation to applications for consent to construct or extend a generating station (including nuclear stations). The Rules were made pursuant to Section 11 of the Tribunals and Inquiries Act 1971. They revoke the previous Electricity Generating Stations and Overhead Line (Inquiries Procedures) Rules 1981. These new Rules cover the same topics as the previous Rules but aim to shorten the potential length and thus cost of inquiries. They will apply to the Inquiry to be held into the application by the Central Electricity Generating Board to build a pressurised water reactor at Hinkley Point in Somerset. (NEA) [fr

Quality planning for major plant design modifications

International Nuclear Information System (INIS)

Dulee, R.J.

1988-01-01

This paper reviews the approach and activities undertaken by Public Service Electric and Gas Company's (PSE and G's) nuclear quality assurance (QA) department to support major plant design modifications conducted during refueling outages at Salem Generating Station. It includes the planning and implementation of quality plans developed to provide both QA and quality control (QC) coverage of modification performed by contracted service organizations

Environmental radiation monitoring data for Point Lepreau Generating Station, 1990. Annual publication

Energy Technology Data Exchange (ETDEWEB)

Sutherland, J K

1991-01-01

Annual report presenting a compilation of the 1990 environmental radiation monitoring program data from samples collected around the Point Lepreau Nuclear Generating Station (PLNGS) and at reference stations remote from PLNGS. About 1,500 analyses were made on 1,100 samples to monitor environmental radiation, including air particulates, airborne water vapour, carbon dioxide in air, sea water, well water, milk, beach sediments, clams, fish, lobster, dulse, crabs, scallops, periwinkles, sea plants and lichen. Background radiation is measured by thermoluminescence dosimetry. Radon is not assessed.

IEEE standard criteria for type tests of class 1E modules used in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1977-01-01

The Institute of Electrical and Electronics Engineers has generated this document to provide direction for type testing Class 1E modules and obtaining specific type test data. It supplements IEEE Std 323-1974, Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, which describes the basic requirements for Class 1E equipment qualification. Adherence to this document alone may not suffice for assuring public health and safety because it is the integrated performance of the structures, the fluid systems, the electrical systems, the instrumentation systems of the station, and in particular, the plant protection system of which these modules are a part that prevents accidents or limits the consequences of accidents. Each applicant to the Nuclear Regulatory Commission for a license to operate a nuclear power generating station has the responsibility to assure himself and others that this document, if used, is pertinent to his application and that the integrated performance of his station is adequate

Properties of Douglas Point Generating Station heat transport corrosion products

International Nuclear Information System (INIS)

Montford, B.; Rummery, T.E.

1975-09-01

Chemical, radiochemical and structural properties of circulating and fixed corrosion products from the Douglas Point Generating Station are documented. Interaction of Monel-400 and carbon steel corrosion products is described, and the mechanisms of Monel-400 surface deposit release, and activity buildup in the coolant system, are briefly discussed. Efficiencies of filters and ion-exchangers for the removal of released radionuclides are given. (author)

On the possibility of generation of cold and additional electric energy at thermal power stations

Science.gov (United States)

Klimenko, A. V.; Agababov, V. S.; Borisova, P. N.

2017-06-01

A layout of a cogeneration plant for centralized supply of the users with electricity and cold (ECCG plant) is presented. The basic components of the plant are an expander-generator unit (EGU) and a vapor-compression thermotransformer (VCTT). At the natural-gas-pressure-reducing stations, viz., gas-distribution stations and gas-control units, the plant is connected in parallel to a throttler and replaces the latter completely or partially. The plant operates using only the energy of the natural gas flow without burning the gas; therefore, it can be classified as a fuelless installation. The authors compare the thermodynamic efficiencies of a centralized cold supply system based on the proposed plant integrated into the thermal power station scheme and a decentralized cold supply system in which the cold is generated by electrically driven vapor-compression thermotransformers installed on the user's premises. To perform comparative analysis, the exergy efficiency was taken as the criterion since in one of the systems under investigation the electricity and the cold are generated, which are energies of different kinds. It is shown that the thermodynamic efficiency of the power supply using the proposed plant proves to be higher within the entire range of the parameters under consideration. The article presents the results of investigating the impact of the gas heating temperature upstream from the expander on the electric power of the plant, its total cooling capacity, and the cooling capacities of the heat exchangers installed downstream from the EGU and the evaporator of the VCTT. The results of calculations are discussed that show that the cold generated at the gas-control unit of a powerful thermal power station can be used for the centralized supply of the cold to the ventilation and conditioning systems of both the buildings of the power station and the neighboring dwelling houses, schools, and public facilities during the summer season.

Qualifying commercial grade instruments for use in nuclear power generating stations

International Nuclear Information System (INIS)

Lamothe, R.J.; Scally, C.R.

1983-01-01

Nuclear environmental qualification of instrumentation has been successfully accomplished by many commercial grade equipment manufacturers. This paper was prepared as a guide to those manufacturers who want some insight into a qualification program. The areas addressed are the regulations and documents, the qualification program, and a case history of a chart recorder qualifications. The principal standards relating to a nuclear qualification program are IEEE Std. 323-1974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 344-1975 IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations and 10CFR50.49. Previously NUREG 0588 Interim Staff Position on Environmental Qualification of Safety-Related Equipment. These define the intent and purpose of the qualification. The qualification program itself consists of several distinct parts which require explanation, including the determination of qualified life, choice of test samples, selection of appropriate acceptance criteria, aging program, radiation testing, seismic testing, abnormal environment tests and others. The case history illustrates the qualification program and the thought processes involved

Measurements of tritium (HTO, TFWT, OBT) in environmental samples at varying distances from a nuclear generating station

Energy Technology Data Exchange (ETDEWEB)

Kotzer, T.G.; Workman, W.J.G

1999-12-01

Concentrations of tritium have been measured in environmental samples (vegetation, water, soil, air) from sites distal and proximal to a CANDU nuclear generating station in Southern Ontario (OPG-Pickering). Levels of tissue-free water tritium (TFWT) and organically bound tritium (OBT) in vegetation are as high as 24,000 TU immediately adjacent to the nuclear generating station and rapidly decrease to levels of tritium which are comparable to natural ambient concentrations for tritium in the environment (approximately {<=} 60 TU). Tritium concentrations (OBT, TFTW) have also been measured in samples of vegetation and tree rings growing substantial distances away from nuclear generating stations and are within a factor of 1 to 2 of the ambient levels of tritium measured in precipitation in several parts of Canada (approximately {<=}30 TU). (author)

Measurements of tritium (HTO, TFWT, OBT) in environmental samples at varying distances from a nuclear generating station

International Nuclear Information System (INIS)

Kotzer, T.G.; Workman, W.J.G.

1999-12-01

Concentrations of tritium have been measured in environmental samples (vegetation, water, soil, air) from sites distal and proximal to a CANDU nuclear generating station in Southern Ontario (OPG-Pickering). Levels of tissue-free water tritium (TFWT) and organically bound tritium (OBT) in vegetation are as high as 24,000 TU immediately adjacent to the nuclear generating station and rapidly decrease to levels of tritium which are comparable to natural ambient concentrations for tritium in the environment (approximately ≤ 60 TU). Tritium concentrations (OBT, TFTW) have also been measured in samples of vegetation and tree rings growing substantial distances away from nuclear generating stations and are within a factor of 1 to 2 of the ambient levels of tritium measured in precipitation in several parts of Canada (approximately ≤30 TU). (author)

Wind hazard assessment for Point Lepreau Generating Station

International Nuclear Information System (INIS)

Mullin, D.; Moland, M.; Sciaudone, J.C.; Twisdale, L.A.; Vickery, P.J.; Mizzen, D.R.

2015-01-01

In response to the CNSC Fukushima Action Plan, NB Power has embarked on a wind hazard assessment for the Point Lepreau Generating Station site that incorporates the latest up to date wind information and modeling. The objective was to provide characterization of the wind hazard from all potential sources and estimate wind-driven missile fragilities and wind pressure fragilities for various structures, systems and components that would provide input to a possible high wind Probabilistic Safety Assessment. The paper will discuss the overall methodology used to assess hazards related to tornadoes, hurricanes and straight-line winds, and site walk-down and hazard/fragility results. (author)

Some environmental effects of emissions from CANDU nuclear generating stations and heavy water plants

International Nuclear Information System (INIS)

Effer, W.R.

Non-radioactive releases during normal operation of Ontario Hydro's nuclear generating stations and heavy water plants are summarized and related to existing regulations and guidelines. Low-grade heat in the circulating cooling water discharge is the most important of the non-radioactive effluents. Some of the hydrological, biological and water quality aspects of thermal discharges are discussed in relation to the operation of Ontario Hydro's thermal generating stations on the Great Lakes. Chemical releases to air or water include chlorine, hydrogen sulphide, water treatment plant effluents, oily waste water and sewage lagoon effluents. The significance of the first two of these releases to the environment is reviewed, particularly in relation to Great Lakes water quality and biological concerns. (author)

Comparative Evaluation of Dental and Skeletal Fluorosis in an Endemic Fluorosed District, Salem, Tamil Nadu.

Science.gov (United States)

Ramesh, Maya; Malathi, N; Ramesh, K; Aruna, Rita Mary; Kuruvilla, Sarah

2017-11-01

High levels of fluoride in the drinking water, especially ground water, results in skeletal fluorosis which involves the bone and major joints. This study was conducted to assess the prevalence of skeletal fluorosis to compare with dental fluorosis in an endemically fluorosed population in the District of Salem, Tamil Nadu. Institutional ethical clearance was obtained. A total of 206 patients who reported to the Department of Hematology for blood investigations were the participants in this study. Age, sex, place, weight, height, dental fluorosis, and skeletal complaints were noted down. Body mass index was calculated, and statistical analysis was performed. Dental fluorosis was present in 63.1% and absent in 36.9% of the samples reported. Skeletal fluorosis was present in 24.8% and was absent in 75.2%. A large number of the patients had knee pain and difficulty in bending. Chi-square test was used for statistical analysis. Skeletal fluorosis and age were compared and P value was 0.00 and was significant. Dental fluorosis and skeletal fluorosis were compared and P value was found to be 0.000 and significant. There is a need to take measures to prevent dental and skeletal fluorosis among the residents of Salem district. Calcium balance should be maintained, and fluoride intake should be minimized to reduce the symptoms. The government should provide water with low fluoride level for drinking and cooking. Once the symptoms develop, treatment largely remains symptomatic, using analgesics and physiotherapy.

Improvements to feed water system of vapor generators of nuclear power stations

International Nuclear Information System (INIS)

Byerlex, W.M.

1976-01-01

The description is given of a feed water system related to the steam generators for nuclear power stations and which have a water feed ring around their upper part. This water intake system enables water hammer to be avoided even during operation under low load [fr

75 FR 15745 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

Science.gov (United States)

2010-03-30

...] Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Exemption 1.0 Background The Arizona Public Service Company (APS, the licensee) is the holder of Facility... Generating Station (PVNGS), Units 1, 2, and 3, respectively. The licenses provide, among other things, that...

75 FR 8149 - Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

Science.gov (United States)

2010-02-23

...] Arizona Public Service Company, et al. Palo Verde Nuclear Generating Station, Units 1, 2, and 3... NPF-74, issued to the Arizona Public Service Company (APS, or the licensee), for operation of the Palo Verde Nuclear Generating Station (PVNGS, the facility), Units 1, 2, and 3, respectively, located in...

Steam generator replacement at the Obrigheim nuclear power station

International Nuclear Information System (INIS)

Pickel, E.; Schenk, H.; Huemmler, A.

1984-01-01

The Obrigheim Nuclear Power Station (KWO) is equipped with a dual-loop pressurized water reactor of 345 MW electric power; it was built by Siemens in the period 1965 to 1968. By the end of 1983, KWO had produced some 35 billion kWh in 109,000 hours of operation. Repeated leaks in the heater tubes of the two steam generators had occurred since 1971. Both steam generators were replaced in the course of the 1983 annual revision. Kraftwerk Union AG (KWU) was commissioned to plant and carry out the replacement work. Despite the leakages the steam generators had been run safely and reliably over a period of 14 years until their replacement. Replacing the steam generators was completed within twelve weeks. In addition to the KWO staff and the supervising crew of KWU, some 400 external fitters were employed on the job at peak work-load periods. For the revision of the whole plant, work on the emergency systems and replacement of the steam generators a maximum number of approx. 900 external fitters were employed in the plant in addition to some 250 members of the plant crew. The exposure dose of the personnel sustained in the course of the steam generator replacement was 690 man-rem, which was clearly below previous estimates. (orig.) [de

Photovoltaic power generation field test at Saigo Police Station (police station in a heavy-snow district); Saigo keisatsusho taiyoko hatsuden field test jigyo (sekisetsu chiku no keisatsusho)

Energy Technology Data Exchange (ETDEWEB)

Matsuo, S. [Shimane Prefectural Police Department, Shimane (Japan)

1997-05-30

Contents of a fiscal 1996 photovoltaic power generation field test at a police station in a heavy-snow district are reported. The system is on the rooftop of the garage of Saigo Police Station, Saigo-cho, Shimane Prefecture, and is used for lighting, airconditioning, etc., in the police station. It is 15kW in capacity and operates on high-voltage interconnection (with back flow). The array is a 9-series/17-parallel (polycrystalline modules) system, facing 15deg eastward from due south and inclined at an angle of elevation of 17deg. Dead space on the roof is used for solar cell installation, and the applicability and stability of the photovoltaic power generation system, as installed at a police station in a heavy-snow district, were verified and, at the same, operation data were collected. The data will serve as guidelines for construction in the future, and will enable understanding about how a distributed type power generation plant should be on an isolated island. The compilation of various data about its system interconnection (with back flow) with the commercial power source is meaningful because it will work effectively in popularizing the photovoltaic power generation system. Efforts to appeal to the local population are under way, which includes letting visitors into a terrace, distributing advertising pamphlets, etc., which are quite effective in enlightening people of the new energy producing technology

Manufacture of steam generator units and components for the AGR power stations at Heysham II and Torness

International Nuclear Information System (INIS)

Glasgow, J.R.; Parkin, K.

1984-01-01

The current AGR Steam Generator is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley B/Hunterston B AGR power stations. In this paper a brief outline of the evolution of the steam generator design from the earlier gas cooled reactor stations is presented. A description of the main items of fabrication development is given. The production facilities for the manufacture of the units are described. Reference is also made to some of the work on associated components. The early experience on the construction site of installation of the steam generators is briefly outlined. (author)

Manufacture of steam generator units and components for the AGR power stations at Heysham II and Torness

Energy Technology Data Exchange (ETDEWEB)

Glasgow, J R; Parkin, K [N.E.I. Nuclear Systems Ltd., Gateshead, Tyne and Wear (United Kingdom)

1984-07-01

The current AGR Steam Generator is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley B/Hunterston B AGR power stations. In this paper a brief outline of the evolution of the steam generator design from the earlier gas cooled reactor stations is presented. A description of the main items of fabrication development is given. The production facilities for the manufacture of the units are described. Reference is also made to some of the work on associated components. The early experience on the construction site of installation of the steam generators is briefly outlined. (author)

Studies in Teaching: 2017 Research Digest. Action Research Projects Presented at Annual Research Forum (Winston-Salem, North Carolina, June 29, 2017)

Science.gov (United States)

McCoy, Leah P., Ed.

2017-01-01

This document presents the proceedings of the 22nd Annual Research Forum held June 29, 2017, at Wake Forest University in Winston-Salem, North Carolina. Included are the following 12 action research papers: (1) Using Captioned Video to Teach Listening Comprehension in a Spanish Classroom (Michelle Allen); (2) Multimodal Instruction: How Film…

Criteria for the design of the control room complex for a nuclear power generating station

International Nuclear Information System (INIS)

Anon.

1981-01-01

This Standard addresses the central control room of a nuclear power generating station and the overall complex in which this room is housed. It is not intended to cover special or normally unattended control rooms, such as those provided for radioactive waste handling or for emergency shutdown operations. The nuclear power generating station control room complex provides a protective envelope for plant operating personnel and for instrument and control equipment vital to the operation of the plant during normal and abnormal conditions. In this capacity, the control room complex must be designed and constructed to meet the following criteria contained in Appendix A of 10CFR50, General Design criteria for Nuclear Power Plants: (1) Criterion 2: design bases for protection against natural phenomena; (2) Criterion 3: fire protection; (3) Criterion 4: environmental and missile design bases; (4) Criterion 5: sharing of structures, systems and components (multiunit stations only); and (5) Criterion 19: control room

AECB staff annual assessment of the Bruce A Nuclear Generating Station for the year 1996

International Nuclear Information System (INIS)

1997-06-01

The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of reactor safety at the Bruce Nuclear Generating Station A for 1996. Ontario Hydro operated Bruce A safely in 1996, maintaining the risk to workers and the public at an acceptably low level. Special safety system performance at Bruce A was adequate. Availability targets were all met. Improvement is needed to reduce the number of operating licence non-compliances

Cordova Lake dam hydroelectric generating station case study

International Nuclear Information System (INIS)

Kerr, D.; Huxley, J.

1993-01-01

The Ontario Ministry of Natural Resources released a Crown owned site to the private water power industry as part of the small hydro site release program initiated by the Ontario Government in the mid 1980's. The Cordova Lake Dam Hydroelectric Generating Station, built on this site, has been in operation since the first week of October, 1992. Since that time, the plant has been operating with less than 1 % down time and has generated over 2,400 MWh of electricity. Algonquin Power Systems is responsible for the management and operations of the plant which includes full time monitoring from the company's Mississauga office and a part time employee at Cordova Lake. Cordova Lake Dam is located on the Crowe River at the outlet of Cordova Lake, approximately 125 kilometers east of Toronto, Ontario. The total cost of the Cordova Lake Dam project was $1.6 million. Algonquin Power contributed 20% equity to the project. Algonquin Power was also responsible for all engineering and geotechnical work and for completing the construction and equipment contracts. 1 tab., 2 figs

Probabilistic seismic hazard assessment for Point Lepreau Generating Station

Energy Technology Data Exchange (ETDEWEB)

Mullin, D. [New Brunswick Power Corp., Point Lepreau Generating Station, Lepreau, New Brunswick (Canada); Lavine, A. [AMEC Foster Wheeler Environment and Infrastructure Americas, Oakland, California (United States); Egan, J. [SAGE Engineers, Oakland, California (United States)

2015-09-15

A Probabilistic Seismic Hazard Assessment (PSHA) has been performed for the Point Lepreau Generating Station (PLGS). The objective is to provide characterization of the earthquake ground shaking that will be used to evaluate seismic safety. The assessment is based on the current state of knowledge of the informed scientific and engineering community regarding earthquake hazards in the site region, and includes two primary components-a seismic source model and a ground motion model. This paper provides the methodology and results of the PLGS PSHA. The implications of the updated hazard information for site safety are discussed in a separate paper. (author)

Probabilistic seismic hazard assessment for Point Lepreau Generating Station

Energy Technology Data Exchange (ETDEWEB)

Mullin, D., E-mail: dmullin@nbpower.com [New Brunswick Power Corporation, Point Lepreau Generating Station, Point Lepreau, NB (Canada); Lavine, A., E-mail: alexis.lavine@amecfw.com [AMEC Foster Wheeler Environment & Infrastructure Americas, Oakland, CA (United States); Egan, J., E-mail: jegan@sageengineers.com [SAGE Engineers, Oakland, CA (United States)

2015-07-01

A Probabilistic Seismic Hazard Assessment (PSHA) has been performed for the Point Lepreau Generating Station (PLGS). The objective is to provide characterization of the earthquake ground shaking that will be used to evaluate seismic safety. The assessment is based on the current state of knowledge of the informed scientific and engineering community regarding earthquake hazards in the site region, and includes two primary components--a seismic source model and a ground motion model. This paper provides the methodology and results of the PLGS PSHA. The implications of the updated hazard information for site safety are discussed in a separate paper. (author)

Secure base stations

NARCIS (Netherlands)

Bosch, Peter; Brusilovsky, Alec; McLellan, Rae; Mullender, Sape J.; Polakos, Paul

2009-01-01

With the introduction of the third generation (3G) Universal Mobile Telecommunications System (UMTS) base station router (BSR) and fourth generation (4G) base stations, such as the 3rd Generation Partnership Project (3GPP) Long Term Evolution (LTE) Evolved Node B (eNB), it has become important to

Studies in Teaching: 2016 Research Digest. Action Research Projects Presented at Annual Research Forum (Winston-Salem, North Carolina, Jun 30, 2016)

Science.gov (United States)

McCoy, Leah P., Ed.

2016-01-01

This document presents the proceedings of the 21st Annual Research Forum held June 30, 2016, at Wake Forest University in Winston-Salem, North Carolina. Included are the following 11 action research papers: The Use of Mexican Folk Art to Develop Oral and Written Language Ability and Cultural Awareness in the Secondary Spanish Classroom (Antonio…

Heat exchanger tubing materials for CANDU nuclear generating stations

International Nuclear Information System (INIS)

Taylor, G.F.

1977-07-01

The performance of steam generator tubing (nickel-chromium-iron alloy in NPD and nickel-copper alloy in Douglas Point and Pickering generating stations) has been outstanding and no corrosion-induced failures have occurred. The primary coolant will be allowed to boil in the 600 MW (electrical) CANDU-PHW reactors. An iron-nickel-chromium alloy has been selected for the steam generator tubing because it will result in lower radiation fields than the alloys used before. It is also more resistant than nickel-chromium-iron alloy to stress corrosion cracking in the high purity water of the primary circuit, an unlikely but conceivable hazard associated with higher operating temperatures. Austenitic alloy and ferritic-austenitic stainless steel tubing have been selected for the moderator coolers in CANDU reactors being designed and under construction. These materials will reduce the radiation fields around the moderator circuit while retaining the good resistance to corrosion in service water that has characterized the copper-nickel alloys now in use. Brass and bronze tubes in feedwater heaters and condensers have given satisfactory service but do, however, complicate corrosion control in the steam cycle and, to reduce the transport of corrosion products from the feedtrain to the steam generator, stainless steel is preferred for feedwater heaters and stainlss steel or titanium for condensers. (author)

Study on the distribution of "2"1"0Po in water and soil samples of Attur taluk, Salem district, Tamilnadu

International Nuclear Information System (INIS)

Murali, M.; Periyasamy, M.; Syed Mohamed, H.E; Sadiq Bukhari, A.; Abrass Begam, A.; Zahir Husain, A.

2017-01-01

The present study was carried out to investigate the distribution of the alpha emitting radionuclide, "2"1"0Po in the ground water and soil samples of Attur taluk of salem district, Tamilnadu and the concentration is observed between water and soil (1.9 mBq/L and 3.9 Bq/Kg) respectively which is less than that of the world standards. (author)

IEEE standard requirements for reliability analysis in the design and operation of safety systems for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1976-01-01

The purpose of this standard is to provide uniform, minimum acceptable requirements for the performance of reliability analyses for safety-related systems found in nuclear-power generating stations, but not to define the need for an analysis. The need for reliability analysis has been identified in other standards which expand the requirements of regulations (e.g., IEEE Std 379-1972 (ANSI N41.2-1972), ''Guide for the Application of the Single-Failure Criterion to Nuclear Power Generating Station Protection System,'' which describes the application of the single-failure criterion). IEEE Std 352-1975, ''Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Protection Systems,'' provides guidance in the application and use of reliability techniques referred to in this standard

Studies in Teaching: 2015 Research Digest. Action Research Projects Presented at Annual Research Forum (Winston-Salem, North Carolina, June 25, 2015)

Science.gov (United States)

McCoy, Leah P., Ed.

2015-01-01

This document presents the proceedings of the 20th Annual Research Forum held June 25, 2015, at Wake Forest University in Winston-Salem, North Carolina. Included are the following 21 action research papers: (1) History Lives! The Use of Simulations in a High School Social Studies Classroom (Lydia Adkins); (2) Using Francophone Music in the High…

Environmental management at the Grand Rapids Generating Station following the Unit No.1 headcover failure

International Nuclear Information System (INIS)

Windsor, D.C.

1993-01-01

Failure of the headcover of Unit 1 in the Grand Rapids generating station in March, 1992 caused the station to flood, releasing several thousand gallons of oil and removing the station from service for several weeks. Environmental considerations were a considerable part of the station restoration activities, reservoir and flow management programs and responses to public concerns arising from the accident. A major oil spill containment and cleanup program was undertaken, with station cleanup and debris disposal carried out in a manner acceptable to environmental authorities. Reservoir spillage was necessitated by the station shutdown. The spill recreated fish habitat in the spillway and walleye spawning were documented. A compensation program was developed to respond to problems caused by debris flushed from the spillway channel. On spill termination, a fish salvage program removed fish from a scour hole in the spillway channel. A proactive program of public information provided local residents with the facts about the incident and response program, and allayed concerns about public safety. 4 refs., 2 figs

Chemistry, materials and related problems in steam generators of power stations

International Nuclear Information System (INIS)

Mathur, P.K.

2000-01-01

The operational reliability and availability of power plants are considerably influenced by chemical factors. Researches all over the world indicate that several difficulties in power plants can be traced to off-normal or abnormal water chemistry conditions. Whatever the source of energy, be it fossil fuel or nuclear fuel, the ultimate aim is steam generation to drive a turbine. It is, therefore, natural that problems of water chemistry and material compatibility are similar in thermal and nuclear power stations. The present paper discusses various types of problems in the form of corrosion damages, taking place in the boiler-turbine cycles and describes different types of boiler feed water/boiler water treatments that have been in use both in nuclear and thermal power stations. Current positions in relation to requirements of boiler feed water, boiler water and steam quality have been described

Process for improving the load factor of an electricity generating power station

International Nuclear Information System (INIS)

Rostaing, Michel.

1974-01-01

A description is given of a process for improving the load factor of an electricity generating power station feeding a supply network in which all or part of the power not required by the network during off-peak hours is used for producing hydrogen which is then stored. The stored hydrogen is then burned and the heat generated is employed for superheating the steam generated by the nuclear reactor of the power plant. This combustion is carried out permanently. The hydrogen is produced by water electrolysis. The oxygen also produced in this manner is used as a comburent in the combustion of the hydrogen. The reactor is of the pressurized water type [fr

Online control loop tuning in Pickering Nuclear Generating Stations

International Nuclear Information System (INIS)

Yu, K.X.; Harrington, S.

2008-01-01

Most analog controllers in the Pickering B Nuclear Generating Stations adopted PID control scheme. In replacing the analog controllers with digital controllers, the PID control strategies, including the original tuning parameters were retained. The replacement strategy resulted in minimum effort on control loop tuning. In a few cases, however, it was found during commissioning that control loop tuning was required as a result of poor control loop performance, typically due to slow response and controlled process oscillation. Several factors are accounted for the necessities of control loop re-tuning. Our experience in commissioning the digital controllers showed that online control tuning posted some challenges in nuclear power plant. (author)

Probabilistic tsunami hazard assessment for Point Lepreau Generating Station

Energy Technology Data Exchange (ETDEWEB)

Mullin, D., E-mail: dmullin@nbpower.com [New Brunswick Power Corporation, Point Lepreau Generating Station, Point Lepreau (Canada); Alcinov, T.; Roussel, P.; Lavine, A.; Arcos, M.E.M.; Hanson, K.; Youngs, R., E-mail: trajce.alcinov@amecfw.com, E-mail: patrick.roussel@amecfw.com [AMEC Foster Wheeler Environment & Infrastructure, Dartmouth, NS (Canada)

2015-07-01

In 2012 the Geological Survey of Canada published a preliminary probabilistic tsunami hazard assessment in Open File 7201 that presents the most up-to-date information on all potential tsunami sources in a probabilistic framework on a national level, thus providing the underlying basis for conducting site-specific tsunami hazard assessments. However, the assessment identified a poorly constrained hazard for the Atlantic Coastline and recommended further evaluation. As a result, NB Power has embarked on performing a Probabilistic Tsunami Hazard Assessment (PTHA) for Point Lepreau Generating Station. This paper provides the methodology and progress or hazard evaluation results for Point Lepreau G.S. (author)

Audit of Wolf Creek Generating Station, Unit 1 technical specifications. Final technical evaluation report

International Nuclear Information System (INIS)

Stromberg, H.M.

1985-07-01

This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Wolf Creek Generating Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumptions of the Final Safety Analysis Report (FSAR) as amended, the requirements of the Safety Evaluation Report (SER) as supplemented, and the Comments and Responses to the Wolf Creek Technical Specification Draft Inspection Report. A comparative audit of the FSAR as amended, the SER as supplemented, and the Draft Inspection Report was performed with the Wolf Creek T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Wolf Creek Generating Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR, SER, and Draft Inspection Report

Groundwater quality assessment using geospatial and statistical tools in Salem District, Tamil Nadu, India

Science.gov (United States)

Arulbalaji, P.; Gurugnanam, B.

2017-10-01

The water quality study of Salem district, Tamil Nadu has been carried out to assess the water quality for domestic and irrigation purposes. For this purpose, 59 groundwater samples were collected and analyzed for pH, electrical conductivity (EC), total dissolved solids (TDS), major anions (HCO3 -, CO3 -, F-, Cl-, NO2 - + NO3 -, and SO4 2-), major cations (Ca2+ Mg2+, Na+, and K+), alkalinity (ALK), and hardness (HAR). To assess the water quality, the following chemical parameters were calculated based on the analytical results, such as Piper plot, water quality index (WQI), sodium adsorption ratio (SAR), magnesium hazard (MH), Kelly index (KI), and residual sodium carbonate (RSC). Wilcox diagram represents that 23% of the samples are excellent to good, 40% of the samples are good to permissible, 10% of the samples are permissible to doubtful, 24% of the samples are doubtful unsuitable, and only 3% of the samples are unsuitable for irrigation. SAR values shows that 52% of the samples indicate high-to-very high and low-to-medium alkali water. KI values indicate good quality (30%) and not suitable (70%) for irrigation purposes. RSC values indicate that 89% of samples are suitable for irrigation purposes. MH reveals that 17% suitable and 83% samples are not suitable for irrigation purposes and for domestic purposes the excellent (8%), good (48%), and poor (44%). The agricultural waste, fertilizer used, soil leaching, urban runoff, livestock waste, and sewages are the sources of poor water quality. Some samples are not suitable for irrigation purposes due to high salinity, hardness, and magnesium concentration. In general, the groundwater of the Salem district was polluted by agricultural activities, anthropogenic activities, ion exchange, and weathering.

Information technology as a key enabler in preparing for competition: ComEd's Kincaid Generating Station, a work in progress

International Nuclear Information System (INIS)

Borth, F.C. III; Thompson, J.W.; Mishaga, J.M.

1996-01-01

Through ComEd Fossil (Generating) Division's Competitive Action Plan (CAP) evaluation changes have been identified which are necessary to improve generating station performance. These changes are intended to improve both station reliability and financial margins, and are essential for stations to be successful in a competitive marketplace. Plant upgrades, advanced equipment stewardship, and personnel reductions have been identified as necessary steps in achieving industry leadership and competitive advantage. To deal effectively with plant systems and contend in the competitive marketplace Information Technology (IT) solutions to business problems are being developed. Data acquisition, storage, and retrieval are being automated through use of state-of-the-art Data Historians. Total plant, high resolution, long term process information will be accessed through Local/Wide Area Networks (LAN/WAN) connections from desktop PC's. Generating unit Thermal Performance Monitors accessing the Data Historian will analyze plant and system performance enabling reductions in operating costs, and improvements in process control. As inputs to proactive maintenance toolsets this data allows anticipation of equipment service needs, advanced service scheduling, and cost/benefit analysis. The ultimate goal is to optimize repair needs with revenue generation. Advanced applications building upon these foundations will bring knowledge of the costs associated with all the products a generating station offers its customer(s). An overall design philosophy along with preliminary results is presented; these results include shortfalls, lessons learned, and future options

AECB staff annual assessment of the Bruce B Nuclear Generating Station for the year 1996

International Nuclear Information System (INIS)

1997-06-01

The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of reactor safety at the Bruce Nuclear Generating Station B for 1996. It was concluded that Ontario Hydro operated Bruce B safely in 1996. Although the Bruce B plant is safe,it was noted that the number of outages and the number of secondary and tertiary equipment failures during reactor unit upsets increased. Ontario Hydro needs to pay special attention to prevent such a decrease in the safety performance at Bruce B

DESIGNING AN OPPORTUNITY FUEL WITH BIOMASS AND TIRE-DERIVED FUEL FOR COFIRING AT WILLOW ISLAND GENERATING STATION

International Nuclear Information System (INIS)

K. Payette; D. Tillman

2001-01-01

During the period October 1, 2000 - December 31, 2000, Allegheny Energy Supply Co., LLC (Allegheny) executed a Cooperative Agreement with the National Energy Technology Laboratory to implement a major cofiring demonstration at the Willow Island Generating Station Boiler No.2. Willow Island Boiler No.2 is a cyclone boiler. Allegheny also will demonstrate separate injection cofiring at the Albright Generating Station Boiler No.3, a tangentially fired boiler. The Allegheny team includes Foster Wheeler as its primary subcontractor. Additional subcontractors are Cofiring Alternatives and N.S. Harding and Associates. This report summarizes the activities associated with the Designer Opportunity Fuel program, and demonstrations at Willow Island and Albright Generating Stations. The second quarter of the project involved completing the designs for each location. Further, geotechnical investigations proceeded at each site. Preparations were made to perform demolition on two small buildings at the Willow Island site. Fuels strategies were initiated for each site. Test planning commenced for each site. A groundbreaking ceremony was held at the Willow Island site on October 18, with Governor C. Underwood being the featured speaker

Field testing of a 1,300MVA turbine generator for the Oi nuclear-power station

International Nuclear Information System (INIS)

Inoue, Toshiaki; Tajiri, Yoshiaki; Ito, Hiroyuki; Fukuda, Mitsuo.

1980-01-01

The first Mitsubishi 1,300MVA turbine generator for this power station was put into commercial operation in March 1979, and the second unit in December of that year. The turbine generators use new technology in a variety of areas, including the cooling system, to achieve great increases in capacity over previously designed generators, and are destined to become the worldwide standard for large-scale generators of this type. Valuable experience was gained in the installation and testing of the generators. The outline of the tests performed on the generators with respect to heating and vibration are described in the article. (author)

Ecological studies of wood-boring bivalves in the vicinity of the Oyster Creek Nuclear Generating Station. Progress report Sep-Nov 81

International Nuclear Information System (INIS)

Hoagland, K.E.; Crocket, L.

1982-06-01

The species composition, distribution, and population dynamics of wood-boring bivalves are being studied in the vicinity of the Oyster Creek Nuclear Generating Station, Barnegat Bay, New Jersey. Untreated wood test panels are used to collect organisms at 12 stations. Physiological tolerances of 3 species are also under investigation in the laboratory. Competition among the species is being analyzed. In the fall of 1981, Teredo bartschi remained in Oyster Creek despite continuous prolonged outages of the Oyster Creek Nuclear Generating Station

IEEE standard for qualifying class IE equipment for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1974-01-01

The Institute of Electrical and Electrical Engineers, Inc. (IEEE) standards for electrical equipment (Class IE) for nuclear power generating stations are given. The standards are to provide guidance for demonstrating and documenting the adequacy of electric equipment used in all Class IE and interface systems. Representative in containment design basis event conditions for the principal reactor types are included in the appendixes for guidance in enviromental simulation

Guide to the collection and presentation of electrical, electronic, and sensing component reliability data for nuclear-power generating stations

International Nuclear Information System (INIS)

Anon.

1979-01-01

This Guide is intended to establish a method of collecting and presenting reliability data for quantitative systematic reliability analysis in nuclear power generating stations, as outlined in IEEE Std 351-1975. Appendix D, which is not a part of IEEE Std 500-1977 but which comprises the bulk of this publication, presents tables of reliability data for nuclear power generating stations, intended for use of nuclear systems reliability analysts or design engineers

A 1500-MW(e) HTGR nuclear generating station

International Nuclear Information System (INIS)

Stinson, R.C.; Hornbuckle, J.D.; Wilson, W.H.

1976-01-01

A conceptual design of a 1500-MW(e) HTGR nuclear generating station is described. The design concept was developed under a three-party arrangement among General Atomic Company as nuclear steam supply system (NSSS) supplier, Bechtel Power Corporation as engineer-constructors of the balance of plant (BOP), and Southern California Edison Company as a potential utility user. A typical site in the lower Mojave Desert in southeastern California was assumed for the purpose of establishing the basic site criteria. Various alternative steam cycles, prestressed concrete reactor vessel (PCRV) and component arrangements, fuel-handling concepts, and BOP layouts were developed and investigated in a programme designed to lead to an economic plant design. The paper describes the NSSS and BOP designs, the general plant arrangement and a description of the site and its unique characteristics. The elements of the design are: the use of four steam generators that are twice the capacity of GA's steam generators for its 770-MW(e) and 1100-MW(e) units; the rearrangement of steam and feedwater piping and support within the PCRV; the elimination of the PCRV star foundation to reduce the overall height of the containment building as well as of the PCRV; a revised fuel-handling concept which permits the use of a simplified, grade-level fuel storage pool; a plant arrangement that permits a substantial reduction in the penetration structure around the containment while still minimizing the lengths of cable and piping runs; and the use of two tandem-compound turbine generators. Plant design bases are discussed, and events leading to the changes in concept from the reference 8-loop PCRV 1500-MW(e) HTGR unit are described. (author)

Public response to the Diablo Canyon Nuclear Generating Station

Energy Technology Data Exchange (ETDEWEB)

Pijawka, K D [Arizona State Univ., Tempe (USA)

1982-08-01

We examine the nature of the public response to the Diablo Canyon Nuclear Generating Station located in San Luis Obispo, California, from the early 1960s to the present. Four distinct phases of public intervention were discerned, based on change in both plant-related issues and in the nature of the antinuclear constituencies in the region. The level of public concern varied both geographically and temporally and is related to the area's social structure, environmental predispositions, and distribution of plant-related economic benefits. External events, such as the prolonged debate over the risk assessment of the seismic hazard and the Three Mile Island accident were found to be important factors in explaining variation in public concern and political response.

AECB staff annual assessment of the Darlington Nuclear Generating Station for the year 1995

International Nuclear Information System (INIS)

1996-06-01

This report is the Atomic ENergy Control Board staff assessment of safety at the Darlington Nuclear Generating Station for 1995. The report is based on observations made by our staff, and on information submitted to us by Ontario Hydro. Performance was satisfactory for all four special safety systems. In 1995, Ontario Hydro complied with the regulations made under the Atomic Energy Control Act, except for two instances of non-compliance with the Transport Packaging of Radioactive Materials Regulations. Radiation doses received by Ontario Hydro station staff were below the regulatory limits. In general Ontario Hydro's maintenance program was found satisfactory. 9 tabs

AECB staff annual assessment of the Pickering A and B Nuclear Generating Stations for the year 1995

International Nuclear Information System (INIS)

1996-06-01

This report is the Atomic Energy Control Board (AECB) staff assessment of safety at the Pickering Nuclear Generating Station (PNGS-A and PNGS-B) for 1995. Our on-site Project Officers and Ottawa-based specialists monitored the stations throughout the year. In 1995, compliance with the Transportation Packaging of Radioactive Materials Regulations and the Cost Recovery Fees Regulations was satisfactory. The performance of the special safety systems was good. Releases of radioactive materials from the station were low and well below the legal limits for public safety. 10 tabs., 7 figs

A Potential Transmitter Architecture for Future Generation Green Wireless Base Station

Directory of Open Access Journals (Sweden)

Mike Faulkner

2009-01-01

Full Text Available Current radio frequency power amplifiers in 3G base stations have very high power consumption leading to a hefty cost and negative environmental impact. In this paper, we propose a potential architecture design for future wireless base station. Issues associated with components of the architecture are investigated. The all-digital transmitter architecture uses a combination of envelope elimination and restoration (EER and pulse width modulation (PWM/pulse position modulation (PPM modulation. The performance of this architecture is predicted from the measured output power and efficiency curves of a GaN amplifier. 57% efficiency is obtained for an OFDM signal limited to 8 dB peak to average power ratio. The PWM/PPM drive signal is generated using the improved Cartesian sigma delta techniques. It is shown that an RF oversampling by a factor of four meets the WLAN spectral mask, and WCDMA specification is met by an RF oversampling of sixteen.

A Potential Transmitter Architecture for Future Generation Green Wireless Base Station

Directory of Open Access Journals (Sweden)

Cijvat Ellie

2009-01-01

Full Text Available Abstract Current radio frequency power amplifiers in 3G base stations have very high power consumption leading to a hefty cost and negative environmental impact. In this paper, we propose a potential architecture design for future wireless base station. Issues associated with components of the architecture are investigated. The all-digital transmitter architecture uses a combination of envelope elimination and restoration (EER and pulse width modulation (PWM/pulse position modulation (PPM modulation. The performance of this architecture is predicted from the measured output power and efficiency curves of a GaN amplifier. 57% efficiency is obtained for an OFDM signal limited to 8 dB peak to average power ratio. The PWM/PPM drive signal is generated using the improved Cartesian sigma delta techniques. It is shown that an RF oversampling by a factor of four meets the WLAN spectral mask, and WCDMA specification is met by an RF oversampling of sixteen.

Type test of Class 1E electric cables, field splices, and connections for nuclear power generating stations - 1975

International Nuclear Information System (INIS)

Anon.

1976-01-01

This Standard provides direction for establishing type tests which may be used in qualifying Class 1E electric cables, field splices, and other connections for service in nuclear power generating stations. General guidelines for qualifications are given in IEEE Std 323-1974, Standard for Qualifying Class 1E Electric Equipment for Nuclear Power Generating Stations. Categories of cables covered are those used for power control and instrumentation services. Though intended primarily to pertain to cable for field installation, this guide may also be used for the qualification of internal wiring of manufactured devices

An artificial intelligence (AI) NOx/heat rate optimization system for Ontario Hydro`s fossil generating stations

Energy Technology Data Exchange (ETDEWEB)

Luk, J.; Frank, A.; Bodach, P. [Ontario Hydro, Toronto, ON (Canada); Warriner, G. [Radian International, Tucker, GA (United States); Noblett, J. [Radian International, Austin, TX (United States); Slatsky, M. [Southern Company, Birmingham, AL (United States)

1999-08-01

Artificial intelligence (AI)-based software packages which can optimize power plant operations that improves heat rate and also reduces nitrogen oxide emissions are now commonly available for commercial use. This paper discusses the implementation of the AI-based NOx and Heat Rate Optimization System at Ontario Hydro`s generation stations, emphasizing the current AI Optimization Project at Units 5 and 6 of the Lakeview Generating Station. These demonstration programs are showing promising results in NOx reduction and plant performance improvement. The availability of the plant Digital Control System (DCS) in implementing AI optimization in a closed-loop system was shown to be an important criterion for success. Implementation of AI technology at other Ontario Hydro fossil generating units as part of the overall NOx emission reduction system is envisaged to coincide with the retrofit of the original plant control system with the latest DCS systems. 14 refs., 3 figs.

AECB staff annual assessment of the Point Lepreau Nuclear Generating Station for the year 1994

International Nuclear Information System (INIS)

1995-06-01

This report is the Atomic Energy Control Board assessment of safety at Point Lepreau Generating Station for 1994. AECB on-site Project Officers, and Ottawa based specialists monitored the station throughout the year. The station operated safely during 1994. Performance of the special safety systems was very good, and NB Power made important progress improving the safety management of these systems. NB Power staff failed to comply with the conditions of our Operating Licence seven times during 1994. This is an improvement from last year, but the number of compliance problems is still too high. NB Power introduced safety culture training for its staff last year. AECB is optimistic that this will help to improve compliance. The station fully met the radiation safety requirements during the year. Releases of radioactive material to the environment are well below the limits set. Radiation exposure to workers are being well controlled, and AECB believe that NB Power is maintaining these exposures 'As Low As Reasonably Achievable' for this reactor type

Draft environmental statement related to the operation of Hope Creek Generating Station (Docket No. 50-354)

International Nuclear Information System (INIS)

Wagner, D.H.

1984-06-01

This report contains an assessment of the environmental impact associated with the operation of the Hope Creek Generating Station pursuant to the National Environment Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environmental impacts, environmental consequences and mitigating actions, and environmental and economic benefits and costs associated with station operation. Land use and terrestrial and aquatic ecological impacts will be small. No operational impacts to historic and archeological sites are anticipated. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. Socioeconomic impacts of the project are anticipated to be minimal. The action called for is the issuance of an operating license for Hope Creek Generating Station, Unit 1

Likelihood and consequences of fuel string compression at Point Lepreau Generating Station

International Nuclear Information System (INIS)

Reid, P.J.; Gibb, R.A.

1996-01-01

During an accident which results in fuel heatup, axial thermal expansion of the fuel string relative to the pressure tube will occur. If the temperature transient is sufficiently severe, the fuel string may contact the shieled plugs at both ends of the channel. Any additional axial thermal expansion will result in deformation of fuel and fuel channel components, leading to tensile or compressive stresses in the different fuel channel components. If these loads become sufficiently large, they could result in failure of a fuel channel component or to channel failure due to bending of a fuel element under load. The analysis described in this paper demonstrates that this process would not result in fuel channel failure for a design basis accident at Point Lepreau Generating Station (PLGS), even if the station were retubed to 'as-built' channel lengths. (author)

Public response to the Diablo Canyon Nuclear Generating Station

International Nuclear Information System (INIS)

Pijawka, K.D.

1982-01-01

The authors examine the nature of the public response to the Diablo Canyon Nuclear Generating Station located in San Luis Obispo, California, from the early 1960s to the present. Four distinct phases of public intervention were discerned, based on change in both plant-related issues and in the nature of the antinuclear constituencies in the region. The level of public concern varied both geographically and temporally and is related to the area's social structure, environmental predispositions, and distribution of plant-related economic benefits. External events, such as the prolonged debate over the risk assessment of the seismic hazard and the Three Mile Island accident were found to be important factors in explaining variation in public concern and political response

Public response to the Diablo Canyon Nuclear Generating Station

International Nuclear Information System (INIS)

Pijawka, K.D.

1982-01-01

We examine the nature of the public response to the Diablo Canyon Nuclear Generating Station located in San Luis Obispo, California, from the early 1960s to the present. Four distinct phases of public intervention were discerned, based on change in both plant-related issues and in the nature of the antinuclear constituencies in the region. The level of public concern varied both geographically and temporally and is related to the area's social structure, environmental predispositions, and distribution of plant-related economic benefits. External events, such as the prolonged debate over the risk assessment of the seismic hazard and the Three Mile Island accident were found to be important factors in explaining variation in public concern and political response. (author)

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

Rate of generation of tritium during the operation of Tsuruga Power Station Unit No. 2

International Nuclear Information System (INIS)

Funamoto, Hisao; Yoshinari, Masaharu; Fukuda, Masayuki; Makino, Shinichi; Watari, Tuneo

1994-01-01

Total amount of 3 H activity in primary coolant due to the operation of Tsuruga Power Station Unit No. 2 was estimated. The 3 H inventory was measured for samples from the spent fuel pool, primary coolant and miscellaneous tanks. From the result of the measurement and the data of environmental release of 3 H, the rate of generation of 3 H in the reactor was found to be 25 TBq/GWa. Since Tsuruga Power Station Unit No. 2 is a PWR type reactor, we presume that most of the 3 H in primary coolant is formed by 10 B(n, 2α) 3 H reaction. It is necessary to release about 23 TBq/GWa of 3 H to maintain the station inventory at the present level. (author)

Purification and solidification of reactor wastes at a Canadian nuclear generating station

International Nuclear Information System (INIS)

Buckley, L.P.; Burt, D.A.

1981-06-01

Chalk River Nuclear Laboratories are developing methods to condition power reactor wastes and to immobilize their radionuclides. Evaporation alone and combined with bituminization has been an important part of the program. After testing at the laboratories a 0.5 m 2 wiped-film evaporator was sent to the Douglas Point Nuclear Generating Station (220 MWe) to demonstrate its suitability to handle typical reactor liquid wastes. Two specific tasks undertaken with the wiped-film evaporator were successfully completed. The first was purification of contaminated heavy water which had leaked from the moderator circuit. The heavy water is normally recovered, cleaned by filters and ion-exchange resin and then upgraded by electrolysis. Cleaning the heavy water with the wiped-film evaporator produced better quality water for upgrading than had been achieved by any previous method and at much lower operating cost. The second task was to concentrate and immobilize a decontamination waste. The waste was generated from the decontamination of pump bowls used in the primary heat transport circuit. The simultaneous addition of the liquid waste and bitumen emulsion to the wiped-film evaporator produced a solid containing 30 wt% waste solids in a bitumen matrix. The volume reduction achieved was 16:1 based on the volumes of initial liquid waste and the final product generated. The quantity sent to storage was 20 times less than had the waste been immobilized in a cement matrix. The successful demonstration has resulted in a proposal to install a wiped-film evaporator at the station to clean heavy water and immobilize decontamination wastes. (author)

IEEE Std 649-1991: IEEE standard for qualifying Class 1E motor control centers for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1993-01-01

The basic principles, requirements, and methods for qualifying Class 1E motor control centers for both harsh and mild environment applications in nuclear power generating stations are described. In addition to defining specific qualification requirements for Class 1E motor control centers and their components in accordance with the more general qualification requirements of IEEE Std 323-1983, this standard is intended to provide guidance in establishing a qualification program for demonstrating the adequacy of Class 1E motor control centers in nuclear power generating station applications

Weather Radar Stations

Data.gov (United States)

Department of Homeland Security — These data represent Next-Generation Radar (NEXRAD) and Terminal Doppler Weather Radar (TDWR) weather radar stations within the US. The NEXRAD radar stations are...

Generation of real-time global ionospheric map based on the global GNSS stations with only a sparse distribution

Science.gov (United States)

Li, Zishen; Wang, Ningbo; Li, Min; Zhou, Kai; Yuan, Yunbin; Yuan, Hong

2017-04-01

The Earth's ionosphere is part of the atmosphere stretching from an altitude of about 50 km to more than 1000 km. When the Global Navigation Satellite System (GNSS) signal emitted from a satellite travels through the ionosphere before reaches a receiver on or near the Earth surface, the GNSS signal is significantly delayed by the ionosphere and this delay bas been considered as one of the major errors in the GNSS measurement. The real-time global ionospheric map calculated from the real-time data obtained by global stations is an essential method for mitigating the ionospheric delay for real-time positioning. The generation of an accurate global ionospheric map generally depends on the global stations with dense distribution; however, the number of global stations that can produce the real-time data is very limited at present, which results that the generation of global ionospheric map with a high accuracy is very different when only using the current stations with real-time data. In view of this, a new approach is proposed for calculating the real-time global ionospheric map only based on the current stations with real-time data. This new approach is developed on the basis of the post-processing and the one-day predicted global ionospheric map from our research group. The performance of the proposed approach is tested by the current global stations with the real-time data and the test results are also compared with the IGS-released final global ionospheric map products.

Models for the transient stability of conventional power generating stations connected to low inertia systems

Science.gov (United States)

Zarifakis, Marios; Coffey, William T.; Kalmykov, Yuri P.; Titov, Sergei V.

2017-06-01

An ever-increasing requirement to integrate greater amounts of electrical energy from renewable sources especially from wind turbines and solar photo-voltaic installations exists and recent experience in the island of Ireland demonstrates that this requirement influences the behaviour of conventional generating stations. One observation is the change in the electrical power output of synchronous generators following a transient disturbance especially their oscillatory behaviour accompanied by similar oscillatory behaviour of the grid frequency, both becoming more pronounced with reducing grid inertia. This behaviour cannot be reproduced with existing mathematical models indicating that an understanding of the behaviour of synchronous generators, subjected to various disturbances especially in a system with low inertia requires a new modelling technique. Thus two models of a generating station based on a double pendulum described by a system of coupled nonlinear differential equations and suitable for analysis of its stability corresponding to infinite or finite grid inertia are presented. Formal analytic solutions of the equations of motion are given and compared with numerical solutions. In particular the new finite grid model will allow one to identify limitations to the operational range of the synchronous generators used in conventional power generation and also to identify limits, such as the allowable Rate of Change of Frequency which is currently set to ± 0.5 Hz/s and is a major factor in describing the volatility of a grid as well as identifying requirements to the total inertia necessary, which is currently provided by conventional power generators only, thus allowing one to maximise the usage of grid connected non-synchronous generators, e.g., wind turbines and solar photo-voltaic installations.

Aerial radiological survey of the creeks and tributaries near the Rancho Seco Nuclear Generation Station, Clay Station, California. Date of survey: December 1984

International Nuclear Information System (INIS)

1986-06-01

Radiological contamination due to man-made radionuclides was detected using hand-held instruments in the summer of 1984 in the creeks and tributaries near the Rancho Seco Nuclear Generating Station at Clay Station, California. To help determine the extent of the contamination an aerial radiological survey centered over the creeks and tributaries and including the Rancho Seco facility was conducted during the period 3 to 15 December 1984. Radiological contaminants were detected along a 9-mile segment of the system of creeks in the area. These contaminants included cesium-134, cesium-137, and cobalt-60. Radiation measurements away from the contaminated areas were the same as those made during the aerial radiological survey conducted in 1980

Selected elements and organic chemicals in streambed sediment in the Salem area, Oregon, 1999

Science.gov (United States)

Tanner, Dwight Q.

2002-09-13

Analysis of streambed sediments in the Salem, Oregon, area showed anomalously large concentrations of some elements and organic chemicals, indicating contamination from anthropogenic and/or geologic sources. The streambed sediment sample from Clark Creek, an urban basin, had large concentrations of polycyclic aromatic hyrdocarbons (PAHs), organochlorines, cadmium, lead, and zinc. The sample from the East Fork of Pringle Creek, which is a mostly urban basin, had the highest concentrations of DDD, DDE, and DDT compounds. Aldrin was detected in streambed sediment at only one site, the East Fork of Pringle Creek. Ten of the 14 sites sampled had exceedances of the sediment quality guidelines of the Canadian Council of Ministers of the Environment (CCME), and 8 sites had exceedances of guidelines from the Puget Sound Dredged Disposal Analysis (PSDDA) Program.

The structural aging assessment program: ranking methodology for CANDU nuclear generating station concrete components

International Nuclear Information System (INIS)

Philipose, K.E.; Muhkerjee, P.K.; McColm, E.J.

1997-01-01

Most of the major structural components in CANDU nuclear generating stations are constructed of reinforced concrete. Although passive in nature, these structures perform many critical safety functions in the operation of each facility. Aging can affect the structural capacity and integrity of structures. The reduction in capacity due to aging is not addressed in design codes. Thus a program is warranted to monitor the aging of safety-related CANDU plant structures and to prioritize those that require maintenance and repairs. Prioritization of monitoring efforts is best accomplished by focusing on those structures judged to be the most critical to plant performance and safety. The safety significance of each sub-element and its degradation with time can be evaluated using a numerical rating system. This will simplify the utility's efforts, thereby saving maintenance costs while providing a higher degree of assurance that performance is maintained. This paper describes the development of a rating system (ranking procedure) as part of the Plant Life Management of CANDU generating station concrete structures and illustrates its application to an operating plant. (author)

Liquid radwaste processing, operational experience utilizing Duratek Mobile Process System (MPS)

International Nuclear Information System (INIS)

Hunkele, W.; Jensen, C.E.; Duratek Corp., Beltsville, MD)

1985-01-01

The use of Duratek's Mobile Process System (MPS) employing sluiceable pressure vessels and improved operational techniques generates operational efficiencies including volume reduction (VR), reduced personnel labor and exposure and higher flowrates for cleanup of liquid radwaste streams in an operating nuclear power plant (Salem Generating Station). Significant additional VR is achievable based on laboratory and on-site experience utilizing Durasil 70. Under high conductivity, actual waste stream conditions, this proprietary media has demonstrated through-puts of a magnitude 15 times higher than organic cation resin. A long-term problem, cobalt species removal, is mitigated by this media

Processing of sump sludges at the Commonwealth Edison Byron Nuclear Generating Station

International Nuclear Information System (INIS)

Herrmann, D.; Gardner, D.A.; Taylor, E.R. Jr.

1990-01-01

A basic criterion for the disposal of radioactive waste by shallow land burial is that the material must not contain free liquids. In addition burial sites' requirements regarding radioactive waste containing oils, even though solidified, are restrictive. At Commonwealth Edison Byron Nuclear Generating Station a methodology for processing treated waste sludges, originating form the turbine building's floor drains was developed and implemented. As a result of this effort, 322 drums of oil and water sludge were processed. A dry cake, i.e., no free liquids, was produced, packaged, and readied for disposal. The dry cake contained less than 2% oil. The liquid phases resulting from the processing of the treated waste sludge were oil (that was to be processed for disposal as non-radioactive) and filtrate containing less than 5 ppm total suspended solids (TSS) and oil/grease. The filtrate TSS was below the Station's National Pollution Discharge Elimination System (NPDES) permit release limits. 4 figs

Quality management for design engineering for San Onofre nuclear generating station

International Nuclear Information System (INIS)

Thompson, P.C.; Baker, R.L.

1991-01-01

Quality management, as applied to design engineering for the San Onofre nuclear generating station, provides a systematic process for data collection and analysis of performance indicators for quality, cost, and delivery of design modifications for the three operating units. Southern California Edison (SCE) and Bechtel Power Corporation (BPC) have collaborated to establish a performance baseline from nearly 2 years of data. This paper discusses how the baseline was developed and how it can be used to predict and assess future performance. It further discusses new insights to the engineering process and opportunities for improvements that have been identified

UMTS Network Stations

Science.gov (United States)

Hernandez, C.

2010-09-01

The weakness of small island electrical grids implies a handicap for the electrical generation with renewable energy sources. With the intention of maximizing the installation of photovoltaic generators in the Canary Islands, arises the need to develop a solar forecasting system that allows knowing in advance the amount of PV generated electricity that will be going into the grid, from the installed PV power plants installed in the island. The forecasting tools need to get feedback from real weather data in "real time" from remote weather stations. Nevertheless, the transference of this data to the calculation computer servers is very complicated with the old point to point telecommunication systems that, neither allow the transfer of data from several remote weather stations simultaneously nor high frequency of sampling of weather parameters due to slowness of the connection. This one project has developed a telecommunications infrastructure that allows sensorizadas remote stations, to send data of its sensors, once every minute and simultaneously, to the calculation server running the solar forecasting numerical models. For it, the Canary Islands Institute of Technology has added a sophisticated communications network to its 30 weather stations measuring irradiation at strategic sites, areas with high penetration of photovoltaic generation or that have potential to host in the future photovoltaic power plants connected to the grid. In each one of the stations, irradiance and temperature measurement instruments have been installed, over inclined silicon cell, global radiation on horizontal surface and room temperature. Mobile telephone devices have been installed and programmed in each one of the weather stations, which allow the transfer of their data taking advantage of the UMTS service offered by the local telephone operator. Every minute the computer server running the numerical weather forecasting models receives data inputs from 120 instruments distributed

Steam generator maintenance and life management at Embalse Nuclear Station

International Nuclear Information System (INIS)

Sainz, R.; Diaz, G.; Sveruga, H.; Ramakrishnan, T.K.; Azeez, S.

2004-01-01

The Embalse Nuclear Station has four steam generators (SGs) with inverted vertical U tubes manufactured by Babcock and Wilcox Canada (B and W). These are main components, both from the operative point of view as the heat transfer from the Primary Heat Transport System (PHTS) to the Secondary System, and from the point of view of safety, as they are the part of the PHTS and its radioactive inventory pressure barrier. In addition, they are one of the most important cost-related elements for potential life extensions. Maintenance and inspections are carried out in order to maintain a high availability of the SGs, as they have had a positive impact on the operational availability of the plant, and to reduce the tube failure probabilities, thus minimizing the amount of radioactive effluents and taking care of the condition of the main components in order to enable the plant life management and the planning of the plant life extension. The most relevant maintenance activities performed have been the inspections performed on 100% of the tubes every 3 years. the mechanical cleaning of the inside of the tubes, the sludge removal from the secondary side tubesheet, the divider plate replacement, and the inspection of internals of the secondary side.Thanks to the latter and to the eddy current inspections, the degradation in the U-bend supports was detected early and every effort is being made to repair them shortly. Besides, a life management program has been started covering the entire plant starting with this important component. The Embalse Nuclear Station's SGs show a low percentage of plugged tubes compared to other stations in similar conditions, but they must be monitored continually and systematically if a life extension is intended. (author)

Microbial Beneficiation of Salem Iron Ore Using Penicillium purpurogenum

Science.gov (United States)

Mishra, M.; Pradhan, M.; Sukla, L. B.; Mishra, B. K.

2011-02-01

High alumina and silica content in the iron ore affects coke rate, reducibility, and productivity in a blast furnace. Iron ore is being beneficiated all around the world to meet the quality requirement of iron and steel industries. Choosing a beneficiation treatment depends on the nature of the gangue present and its association with the ore structure. The advanced physicochemical methods used for the beneficiation of iron ore are generally unfriendly to the environment. Biobeneficiation is considered to be ecofriendly, promising, and revolutionary solutions to these problems. A characterization study of Salem iron ore indicates that the major iron-bearing minerals are hematite, magnetite, and goethite. Samples on average contains (pct) Fe2O3-84.40, Fe (total)-59.02, Al2O3-7.18, and SiO2-7.53. Penicillium purpurogenum (MTCC 7356) was used for the experiment . It removed 35.22 pct alumina and 39.41 pct silica in 30 days in a shake flask at 10 pct pulp density, 308 K (35 °C), and 150 rpm. In a bioreactor experiment at 2 kg scale using the same organism, it removed 23.33 pct alumina and 30.54 pct silica in 30 days at 300 rpm agitation and 2 to 3 l/min aeration. Alumina and silica dissolution follow the shrinking core model for both shake flask and bioreactor experiments.

Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Salem nuclear power plant, Unit 1

International Nuclear Information System (INIS)

Laudenbach, D.H.

1979-03-01

The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Salem nuclear power plant, Unit 1. Design basis criteria used to evaluate the acceptability of the system include operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

AECB staff annual assessment of the Pickering A and B Nuclear Generating Stations for the year 1996

International Nuclear Information System (INIS)

1997-06-01

The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of reactor safety at the Pickering A and B Generating Stations for 1996. PNGS-A and PNGS-B operated safely during 1996. Although the risk to the workers and the public is low, major safety related changes are necessary at the stations and the sustainability of those changes needs to be demonstrated. Improvement is needed by Ontario Hydro in meeting the time limits for reporting reportable events. Ontario Hydro's follow up to events and causal factor analyses continue to need improvements. Improvements are needed to operational safety and reactor maintenance at both A and B. There are signs of improvement through Ontario Hydro's plan for recovery, and in station management changes. There also appears to be commitment to safety expressed at the highest level of the utility

North Anna Power Station - Unit 1: Overview of steam generator replacement project activities

International Nuclear Information System (INIS)

Gettler, M.W.; Bayer, R.K.; Lippard, D.W.

1993-01-01

The original steam generators at Virginia Electric and Power Company's (Virginia Power) North Anna Power Station (NAPS) Unit 1 have experienced corrosion-related degradation that require periodic inspection and plugging of steam generator tubes to ensure their continued safe and reliable operation. Despite improvements in secondary water chemistry, continued tube degradation in the steam generators necessitated the removal from service of approximately 20.3 percent of the tubes by plugging, (18.6, 17.3, and 25.1 for steam generators A, B, and C, respectively). Additionally, the unit power was limited to 95 % during, its last cycle of operation. Projections of industry and Virginia Power experience indicated the possibility of mid-cycle inspections and reductions in unit power. Therefore, economic considerations led to the decision to repair the steam generators (i.e., replace the steam generator lower assemblies). Three new Model 51F Steam Generator lower assembly units were ordered from Westinghouse. Virginia Power contracted Bechtel Power Corporation to provide the engineering and construction support to repair the Unit 1 steam generators. On January 4, 1993, after an extended coastdown period, North Anna Unit 1 was brought off-line and the 110 day (breaker-to-breaker) Steam Generator Replacement Project (SGRP) outage began. As of this paper, the outage is still in progress

Safety research of insulating materials of cable for nuclear power generating station

Science.gov (United States)

Lee, C. K.; Choi, J. H.; Kong, Y. K.; Chang, H. S.

1988-01-01

The polymers PE, EPR, PVC, Neoprene, CSP, CLPE, EP and other similar substances are frequently used as insulation and protective covering for cables used in nuclear power generating stations. In order to test these materials for flame retardation, environmental resistance, and cable specifications, they were given the cable normal test, flame test, chemical tests, and subjected to design analysis and loss of coolant accident tests. Material was collected on spark tests and actual experience standards were established through these contributions and technology was accumulated.

Analysis methodology of power generation/cogeneration designs in VNG (Vehicular Natural Gas) stations; Metodologia de analise de projetos de geracao/cogeracao em postos GNV (Gas Natural Veicular)

Energy Technology Data Exchange (ETDEWEB)

Romanos, Rafael Reami [Companhia de Gas de Santa Catarina (SCGAS), Florianopolis, SC (Brazil)

2008-07-01

This work presents the methodology for analysis of generation/cogeneration projects in NGV filling stations, determining the influence of critical parameters in its technical-economic viability. To achieve this methodology, it was necessary to define parameters that influence directly or indirectly the size of a generating system, as the total electric demand of the filling station, ratio (power of the compressor) / (total installed power), load factor, factor of simultaneity, technical data of major equipment, among others. The methodology has been validated by comparing with data measured in a NGV filling station and allows screening and identifying customers with technical feasibility to evolve in a generation or cogeneration project. The cogeneration with NG generators was highlighted during the analysis of the NGV filling stations and was feasible for establishments which have large thermal demand, as filling stations along the road with large amounts of electric showers in changing rooms. (author)

Design and installation of a strategically placed algae mesh barrier at OPG Pickering Nuclear Generating Station

International Nuclear Information System (INIS)

Marttila, D.; Patrick, P.; Gregoris, C.

2009-01-01

Ontario Power Generation's Pickering Nuclear has experienced a number of events in which attached algae have become entrained in the water intake costing approximately $30M over the 1995-2005 period as a result of deratings, Unit shutdowns and other operational issues. In 2005-2006 OPG and Kinectrics worked collaboratively on evaluating different potential solutions to reduce the impact of algae on the station. One of the solutions developed by Kinectrics included a strategically placed barrier net designed to regulate algae flow into the station intake. In 2006, Kinectrics designed and installed the system, the first of its kind at a Nuclear Power Plant in Canada. The system was operational by May 2007. OPG completed an effectiveness study in 2007 and concluded the barrier system had a beneficial effect on reducing algae impact on the station. (author)

Development of an HTS hydroelectric power generator for the hirschaid power station

Energy Technology Data Exchange (ETDEWEB)

Fair, Ruben; Lewis, Clive; Eugene, Joseph; Ingles, Martin, E-mail: ruben.fair@converteam.co [Advanced Technology Group, Converteam, Rugby, CV21 1BD (United Kingdom)

2010-06-01

This paper describes the development and manufacture of a 1.7MW, 5.25kV, 28pole, 214rpm hydroelectric power generator consisting of superconducting HTS field coils and a conventional stator. The generator is to be installed at a hydro power station in Hirschaid, Germany and is intended to be a technology demonstrator for the practical application of superconducting technology for sustainable and renewable power generation. The generator is intended to replace and uprate an existing conventional generator and will be connected directly to the German grid. The HTS field winding uses Bi-2223 tape conductor cooled to about 30K using high pressure helium gas which is transferred from static cryocoolers to the rotor via a bespoke rotating coupling. The coils are insulated with multi-layer insulation and positioned over laminated iron rotor poles which are at room temperature. The rotor is enclosed within a vacuum chamber and the complete assembly rotates at 214rpm. The challenges have been significant but have allowed Converteam to develop key technology building blocks which can be applied to future HTS related projects. The design challenges, electromagnetic, mechanical and thermal tests and results are presented and discussed together with applied solutions.

IEEE Std 650-1990: IEEE standard for qualification of Class 1E static battery chargers and inverters for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

Methods for qualifying static battery chargers and inverters for Class 1E installations in a mild environment outside containment in nuclear power generating stations are described. The qualification methods set forth employ a combination of type testing and analysis, the latter including a justification of methods, theories, and assumptions used. These procedures meet the requirements of IEEE Std 323-1983, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations

Role of quality circles in dose control programs at Kaiga generating station

International Nuclear Information System (INIS)

Varadhan, R.S.; Sukumar, T.S.; Ramamurthy, K.; Nageswara Rao, G.

2003-01-01

To operate the nuclear power station with maximum capacity factors and lowest collective dose it is imperative that a sense of belongingness among the employees is essential. Quality Circles provide an opportunity to the plant personnel irrespective of their grade or discipline to come together to solve the work related problems in a scientific manner to enhance the productivity and safety in the work environment. The concept of Quality Circles came to Kaiga during July 1998. The thought revolution grew slowly and steadily and brought big gains to the station. The organized thoughts and concerted actions in field resulted in development of good work culture among the employees, an important input to achieve super excellence in power generation in the most cost effective manner. This also is a means to set challenging targets and make and break the records among the NPCIL units. The genesis of Quality Circles, the methodology of QC working, promotional activities, the progress and programs of Quality Circles are discussed in this presentation. (author)

The generation of simple compliance boundaries for mobile communication base station antennas using formulae for SAR estimation.

Science.gov (United States)

Thors, B; Hansson, B; Törnevik, C

2009-07-07

In this paper, a procedure is proposed for generating simple and practical compliance boundaries for mobile communication base station antennas. The procedure is based on a set of formulae for estimating the specific absorption rate (SAR) in certain directions around a class of common base station antennas. The formulae, given for both whole-body and localized SAR, require as input the frequency, the transmitted power and knowledge of antenna-related parameters such as dimensions, directivity and half-power beamwidths. With knowledge of the SAR in three key directions it is demonstrated how simple and practical compliance boundaries can be generated outside of which the exposure levels do not exceed certain limit values. The conservativeness of the proposed procedure is discussed based on results from numerical radio frequency (RF) exposure simulations with human body phantoms from the recently developed Virtual Family.

Manufacture of the 300 MW steam generator and pressure stabilizer for Qinshan Nuclear Power Station

International Nuclear Information System (INIS)

Qian Yi; Miao Deming.

1989-01-01

A brief description of the manufacturing process of the steam generator and pressure stabilizer for 300 MWe Qinshan Nuclear Power Station in Shanghai Boiler Works is presented, with special emphasis on fabrication facilities, test procedures and technological evaluations during the manufaturing process-imcluding deep driling of tubesheets, welding of tubes to tube-sheets and tube rolling tests

Study of sources, dose contribution and control measures of Argon-41 at Kaiga Generating Station

International Nuclear Information System (INIS)

Venkata Ramana, K.; Shrikrishna, U.V.; Manojkumar, M.; Ramesh, R.; Madhan, V.; Varadhan, R.S.

2001-01-01

Air is used as a medium for cooling calandria vault and thermal shield systems in the earlier Pressurised Heavy Water Reactors (Rajasthan Atomic Power Station and Madras Atomic Power Station) in India. This leads to production of significant quantity of 41 Ar in calandria vault and thermal shield cooling systems due to neutron activation of 40 Ar present in air (∼1% v/v). The presence of 41 Ar in reactor building contributes significant external doses to plant personnel during reactor operation and the release of this radionuclide to the environment result in dose to the public in the vicinity of the plants. An attempt is made to eliminate Argon-41 production in Indian standard Pressurised Heavy Water Reactors (Narora Atomic Power Station, Kakrapar Atomic Power Station, Kaiga Generating Station -1 and 2 and Rajasthan Atomic Power Station-3 and 4), by filling the calandria vault with demineralized water and providing a separate Annulus Gas Monitoring System (AGMS) for detecting leaks from calandria tube or pressure tube using Carbon dioxide as a medium. However, 41 Ar is produced in the Annulus Gas Monitoring System, Primary Heat Transport cover gas system and moderator cover gas system due to ingress of air into the systems during operational transients or due to trace quantity of air present as an impurity in the gases used for the above systems. A study was conducted to identify and quantify the sources of 41 Ar in the work areas. This report brings out the sources of 41 Ar, reasons for 41 Ar production and the results of the measures incorporated to reduce the presence of 41 Ar in the above systems. (author)

Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station

International Nuclear Information System (INIS)

Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Dawson, J.W.; Brunk, J.L.; Jokela, T.A.

1985-01-01

This report summarizes the information compiled in 1984 while assessing the environmental impact of radionuclides in aquatic releases from the Rancho Seco Nuclear Power Generating Station. Gamma-emitting radionuclides discharged since 1981 are found in many of the dietary components derived from the creeks receiving the effluent wastewater. Some soils and crops are found to contain radionuclides that originate from the contaminated water that was transferred to land during the irrigation season. 134 Cs and 137 Cs are the primary gamma-emitting radionuclides detected in the edible flesh of fish from the creeks. Concentrations in the flesh of fish decreased exponentially with distance from the plant. No significant differences in the 137 Cs activity were found between male and female fish of equal size, but concentrations may vary in fish of different size, with the season and diet. 21% of the total 137 Cs and 134 Cs discharged between 1981 and 1984 is associated with the creek sediments to a distance of 27 km from the plant. Fractions of the missing inventory have been transferred to land during the irrigation season or to downstream regions more distant than 27 km from the plant. The radiocesium content of the sediments in 1984 decreased significantly in a downstream direction, much in the same manner as concentrations decreased in fish. Radioactivity originating from the plant was not above detection limits in any terrestrial food item sampled beyond 6.5 km from the plant. Based on the usage factors provided by individuals interviewed in a 1984 survey, the fish and aquatic-organism ingestion pathway contributed the largest radiological dose to humans utilizing products contaminated with the radionuclides in the liquid wastes discharged from the Rancho Seco Nuclear Power Generating Station in 1984

Review of occupational radiation exposures in all biennial shutdown maintenance of Kaiga generating station

International Nuclear Information System (INIS)

Murukan, E.K.; Vinod Kumar, T.; Austine, N.X.; Soumia Menon, M.; Girish Kumar, K.; Rao, M.M.L.N.; Venkataramana, K.

2008-01-01

Full text: Kaiga generating station 1 and 2 consists of twin units of 220 M We pressurized heavy water reactors located in Karnataka, India. Major maintenance activities of one of the twin units are taken up once in two years (biennial shutdown) to execute system maintenance, system up gradation, surveillance and in-service inspection (ISI) jobs. BSDs are mandatory activities to comply with regulatory requirement to ensure the safety and reliability of plant system equipment. More than 65% of the station collective dose is contributed by biennial shutdown (BSD) jobs. It is observed that the man rem consumed during normal operation of the plant is less than 35% of the total man rem consumed. Since BSD jobs contributes significantly to station collective dose, an effective implementation of radiation protection programme specific to BSD is the key to control the occupational exposure. Various improvements in the field of radiation protection practices and process systems are adopted to achieve lowest collective dose at par with international standards. The key areas identified for application of various strategies to achieve ALARA were Man rem budgeting, Radiological condition monitoring, Radiation protection practices, Identification of critical jobs and Work groups, Work planning and execution, and Radioactive waste management. Review of collective doses of all the BSD jobs performed in the station since year 2004 and various measures incorporated to achieve ALARA exposures to plant personnel are briefly discussed in this paper. (author)

AECB staff annual assessment of the Bruce A Nuclear Generating Station for the year 1995

International Nuclear Information System (INIS)

1996-06-01

The Atomic Energy Control Board conducts a staff assessment of safety at Bruce Nuclear Generating Station A for 1995. On-site Project Officers and Ottawa based specialists monitored the station throughout the year. Ontario Hydro operated Bruce A safely in 1995, maintaining the risk to workers and the public at an acceptably low level. Radiation doses to workers and releases to the environment were well below regulatory limits. However, Ontario Hydro must improve contamination control at Bruce A. Special safety system performance a Bruce A was less than adequate. The negative pressure containment system and units 4's shutdown system two exceeded unavailability targets in 1995. However, we are satisfied Ontario Hydro is taking appropriate action to correct this. 5 tabs., 5 figs

Purification and solidification of reactor wastes at a Canadian nuclear generating station

International Nuclear Information System (INIS)

Buckley, L.P.; Burt, D.A.

1981-01-01

The study aimed at development and demonstration of volume reduction and solidification of CANDU reactor wastes has been underway at Chalk River Nuclear Laboratories in the Province of Ontario, Canada. The study comprises membrane separation processes, evaporator appraisal and immobilization of concentrated wastes in bitumen. This paper discusses the development work with a wiped-film evaporator and the successful completion of demonstration tests at Douglas Point Nuclear Generating Station. Heavy water from the moderator system was purified and wastes arising from pump bowl decontamination were immobilized in bitumen with the wiped-film evaporator that was used in the development tests at Chalk River

Radioactive emission data from Canadian nuclear generating stations 1986 to 1995

International Nuclear Information System (INIS)

1997-05-01

All nuclear generating station (NGSs) release small quantities of radioactivity in a controlled manner into both the atmosphere (as gaseous effluents) and adjoining water bodies (as liquid effluents). The purpose of this document is to report on the magnitude of these emissions for each operating NGS in Canada and to indicate how these emissions compare with the relevant limitations imposed by the AECB as part of its regulatory and licensing program. The data show that the levels of emissions of gaseous and liquid effluents from all currently operating NGSs are well below the values mandated by the AECB. In fact, since 1987 no emissions have exceeded 1% of those values. 3 tabs., 46 figs

78 FR 13378 - National Register of Historic Places; Notification of Pending Nominations and Related Actions

Science.gov (United States)

2013-02-27

... Monastery, 5700 N. Harlem Dr., Chicago, 13000048 Storkline Furniture Corporation Factory, 4400-4418 W. 26th St., Chicago, 13000049 MASSACHUSETTS Essex County North Street Fire Station, 142 North St., Salem...

Field testing of behavioral barriers for cooling water intake structures -test site 1 - Pickering Nuclear Generating Station

International Nuclear Information System (INIS)

Patrick, P.H.; McKinley, R.S.; Micheletti, W.C.

1988-01-01

A multi-year research program was developed by the Electric Power Research Institute to evaluate the effectiveness of selected behavioral systems for fish exclusion at sites representative of different aquatic environments. The first test site was the Pickering Nuclear Generating Station (NGS) located on Lake Ontario which represented the Great Lakes environment. A single pneumatic popper, a low frequency, high amplitude sound deterrent, was found to effectively exclude adult alewife, the principal species impinged at Pickering NGS. An air bubble curtain, used either alone or combined with strobe lights, was not a consistent deterrent. Effectiveness of air bubbles was only enhanced when used in association with a popper. Strobe lights were the least effective of the three devices tested. Operation of all three devices together did not surpass the effectiveness of the popper when used alone. Sound deterrents show promise for fish exclusion at generating stations located on the Great Lakes

78 FR 32278 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

Science.gov (United States)

2013-05-29

... Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to Information in Tier 1, Table... Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation, Municipal... Table 3.3-1, ``Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Buildings, and Annex...

The Association between Cariogenic Factors and the Occurrence of Early Childhood Caries in Children from Salem District of India.

Science.gov (United States)

Stephen, Arokiaraj; Krishnan, Ramesh; Chalakkal, Paul

2017-07-01

Various aetiological factors for Early Childhood Caries (ECC) have been suggested in literature, but the role of each factor has been disputed in various studies. To evaluate the association between ECC and its related factors in children between three to six years of age, from rural, semi-urban and urban schools in the district of Salem (India). The study consisted of children between three to six years of age, selected randomly from schools in semi-urban, urban and rural schools at Salem. Questionnaire (comprising of the factors associated with ECC) and parental consent forms were sent to each of the parents of the school children. Filled questionnaires and parental consent forms were obtained from a total of 2771 children, out of which 1771 were boys and 1000 were girls. Clinical examination for ECC was carried out according to the WHO criteria, by a single examiner and an assistant to eliminate inter-examiner variability. Statistical analysis was carried out using the student's independent t-test and ANOVA (one way analysis of variance). Out of a total of 2771 children examined, only 443 (315 boys and 128 girls) children were found to have ECC (16 %). Significant correlations were found between the occurrence of ECC and various factors like age of parents, number of siblings, on-demand breast feeding and bottle feeding habits and sweetened pacifier use. However, factors such as age and gender of the child, type of birth and duration of pregnancy, had no significant correlation with the occurrence of ECC. The need for educating parents on the ill effects of improper breast feeding and bottle feeding habits is important.

IEEE guide for general principles of reliability analysis of nuclear power generating station protection systems

International Nuclear Information System (INIS)

Anon.

1975-01-01

Presented is the Institute of Electrical and Electronics Engineers, Inc. (IEEE) guide for general principles of reliability analysis of nuclear power generating station protection systems. The document has been prepared to provide the basic principles needed to conduct a reliability analysis of protection systems. Included is information on qualitative and quantitative analysis, guides for failure data acquisition and use, and guide for establishment of intervals

Activity transport in nuclear generating stations

International Nuclear Information System (INIS)

Mitchell, A.B.

1975-01-01

The objective of this paper is to give a basic understanding of the operational limitations caused by radiation fields in the present design of CANDU-PHW reactors. A simple model of activity transport is described, and the significance of various radioisotopes identified. The impact which radiation fields have at the Divisional, Station Manager and Operation levels, is outlined in the context of typical work situations. (author)

75 FR 53985 - Arizona Public Service Company, et al., Palo Verde Nuclear Generating Station, Unit 3; Temporary...

Science.gov (United States)

2010-09-02

... NUCLEAR REGULATORY COMMISSION [Docket No. STN 50-530; NRC-2010-0281] Arizona Public Service Company, et al., Palo Verde Nuclear Generating Station, Unit 3; Temporary Exemption 1.0 Background Arizona Public Service Company (APS, the licensee) is the holder of Facility Operating License No. NPF-74, which...

40 CFR 52.1570 - Identification of plan.

Science.gov (United States)

2010-07-01

....'s electric arc furnace and tunnel kiln, Burlington County, NJ COAD approval dated February 3, 1995... County 2.0 Atlantic City Electric Deepwater Station Penns Grove, Salem County 1.5 E. I. du Pont de... City Electric B. L. England Station Beesley Point, Cape May County 2.0 Hunt Wesson Foods, Inc Bridgeton...

Environmental and public interface for Point Aconi generating station, Point Aconi, Nova Scotia

Energy Technology Data Exchange (ETDEWEB)

Toner, T P

1993-01-01

Nova Scotia Power's most recent generating station is a 165 MW coal-fired circulating fluidized bed (CFB) unit located at Point Aconi on the northern tip of Boularderie Island. This paper discusses the environmental and public interfaces associated with this project, particularly on the unique items and issues requiring delicate and/or innovative approaches for their successful completion. Specific issues discussed include clarification of the process, the turnkey arrangement, the community liaison committee, freshwater supply, air emissions and dealings with commercial growers, dealings with lobster fishermen, dealings with Native peoples, and the transmission line.

Thermal mapping studies at Kadra reservoir near Kaiga generating station site

International Nuclear Information System (INIS)

Ravi, P.M.; Nayak, P.D.; Sudhakar, J.; Mishra, D.G.; Hegde, A.G.

2007-01-01

An inherent problem in nuclear and thermal power plants are the release of heat energy into the environment through cooling system to water bodies such as lakes, rivers, estuaries and oceans. Two NPPs of Kaiga Generating Station, discharge the thermal effluent to the nearby Kadra reservoir. This paper presents the results of three year long comprehensive thermal mapping studies conducted by ESL, KGS as part of the Thermal Ecological Studies sponsored by Board of Research in Nuclear Sciences (BRNS), Department of Atomic Energy. Present studies clearly demonstrate that the thermally influenced zone in the reservoir is limited to a small volume of the reservoir and is not likely to lead any irreversible adverse impact on the ecosystem of the reservoir. (author)

75 FR 13606 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3...

Science.gov (United States)

2010-03-22

... NUCLEAR REGULATORY COMMISSION [Docket Nos. STN 50-528, STN 50-529, and STN 50-530; NRC-2010-0114] Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3; Environmental...-74, issued to Arizona Public Service Company (APS, the licensee), for operation of the Palo Verde...

Generic implications of ATWS events at the Salem Nuclear Power Plant: generic implications. Vol. 1

International Nuclear Information System (INIS)

1983-04-01

This report is the first of two volumes. It documents the work of an interoffice, interdisciplinary NRC Task Force established to determine the generic implications of two anticipated transients without scram (ATWS) at the Salem Nuclear Power Plant, Unit 1 on February 22 and 25, 1983. A second report will document the NRC actions to be taken based on the work of the Task Force. The Task Force was established to address three questions: (1) Is there a need for prompt action for similar equipment in other facilities. (2) Are NRC and its licensees learning the sefety-management lessons, and, (3) How should the priority and content of the ATWS rule be adjusted. A number of short-term actions were taken through Bulletins and an Information Notice. Intermediate-term actions to address the generic issues will be addressed in the separate report and implemented through appropriate regulatory mechanisms

Design and development of steam generators for the AGR power stations at Heysham II/Torness

Energy Technology Data Exchange (ETDEWEB)

Charcharos, A N; Jones, A G [National Nuclear Corp. Ltd., Cheshire (United Kingdom)

1984-07-01

The current AGR steam generator design is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley/Hunterston AGR power stations. These units have demonstrated proven control and reliability in service. In this paper the factors which have dictated the design and layout of the latest AGR steam generators are described and reference made to the latest high temperature design techniques that have been employed. Details of development work to support the design and establish the performance characteristics over the range of plant operating conditions are also given. To comply with current UK safety standards, the AGR steam generators and associated plant are designed to accommodate seismic loadings. In addition, provision is made for an independent heat removal system for post reactor trip operations. (author)

Design and development of steam generators for the AGR power stations at Heysham II/Torness

International Nuclear Information System (INIS)

Charcharos, A.N.; Jones, A.G.

1984-01-01

The current AGR steam generator design is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley/Hunterston AGR power stations. These units have demonstrated proven control and reliability in service. In this paper the factors which have dictated the design and layout of the latest AGR steam generators are described and reference made to the latest high temperature design techniques that have been employed. Details of development work to support the design and establish the performance characteristics over the range of plant operating conditions are also given. To comply with current UK safety standards, the AGR steam generators and associated plant are designed to accommodate seismic loadings. In addition, provision is made for an independent heat removal system for post reactor trip operations. (author)

Reconstruction of steam generators super emergency feadwater supply system (SHNC) and steam dump stations to the atmosphere system PSA

International Nuclear Information System (INIS)

Kuzma, J.

2001-01-01

Steam Generators Super Emergency Feadwater Supply System (SHNC) and Steam Dump Stations to the Atmosphere System (PSA) are two systems which cooperate to remove residual heat from reactor core after seismic event. SHNC assure feeding of the secondary site of steam generator (Feed) where after heat removal.from primary loops, is relieved to the atmosphere by PSA (Bleed) in form of steam. (author)

Generating power stations and optimization energetic of processes; Centrales generadoras y optimacion energetica de procesos

Energy Technology Data Exchange (ETDEWEB)

Gutierrez Ramirez, Ranulfo; Fernandez Montiel, Manuel Francisco [Instituto de Investigaciones Electricas, Temixco, Morelos (Mexico)

1999-07-01

Some recent experiences of the Management of Thermal Processes of the Instituto de Investigaciones Electricas (IIE) related to the works on generating power stations of electricity, plants of cogeneration and energy saving are presented. [Spanish] Se presentan algunas experiencias recientes de la Gerencia de Procesos Termicos del Instituto de Investigaciones Electricas (IIE) relacionadas con los trabajos sobre centrales generadoras de electricidad, plantas de cogeneracion y ahorro de energia.

Characterization of potential zones of dust generation at eleven stations in the southern Sahara

Science.gov (United States)

Clark, I.; Assamoi, P.; Bertrand, J.; Giorgi, F.

Synoptic wind data for multi-decadal periods at eleven stations located in the southern Sahara region (Agadez, Atar, Bilma, Dori, Gao, Kayes, Nema, Niamey, Nouadhibou, Ouagadougou and Tessalit) are used to study the monthly dust deflation power over the region. We found that, regardless of the conditions of the soil, the deflation power (or wind efficiency) is not sufficient to generate significant amounts of aerosols south of 15°N. North of this latitude, the deflation power is much larger, with potential zones of either very strong deflation (Nouadhibou and Bilma) or severe deflation (Gao, Tessalit, Nema, Atar, Agadez). Stations in the Sahel region such as Gao, Agadez and Tessalit are characterized by a gradual reinforcement of the deflation power between 1970 and 1984 in correspondence of increasing desertification over the region. During this same period, Bilma, a well know region of dust source, experienced a major reduction in deflation power due to shifts in large scale wind patterns.

Advances in power station construction

International Nuclear Information System (INIS)

Anon.

1986-01-01

This book is about power stations - specifically about the construction of modern power stations by the Central Electricity Generating Board in England and Wales over the past decade. It describes the work of the CEGB's Generation Development and Construction Division, perhaps better known throughout the world as simply 'Barnwood' where it has its Headquarters in Gloucester, UK. Barnwood was formed in the early 1970s to concentrate the CEGB's then dispersed engineering construction resources to cope with the smaller number but greatly increased size and complexity of modern power station projects. Perhaps uniquely over the ten years since its formation Barnwood has managed the construction of all types of station; coal-fired, oil-fired, nuclear, pumped storage and hydro. This book tells the story of these various projects and gives detailed descriptions of the respective stations. However, it is not intended as a comprehensive description of power station technology. Rather it is intended to convey the scale of such projects and the many decisions and compromises which have to be made in the course of managing their construction

AECB staff annual assessment of the Point Lepreau Nuclear Generating Station for the year 1995

International Nuclear Information System (INIS)

1996-06-01

The Atomic Energy Control Board conducts a staff assessment of safety at Point Lepreau Generating Station for 1995. On-site Project Officers and Ottawa based specialists monitored the station throughout the year. Point Lepreau operated safely during 1995 which was an unusual year for the station. The station was shut down for a planned five month outage to allow NB Power to complete maintenance on the reactor's pressure tubes. NB Power failed to comply with the terms of the Operating Licence we issue on fourteen occasions in 1995. In addition, NB Power reported an unusually large number of events. None of the events themselves directly affected public safety, if this level of performance continues unchecked, it might result in increased risk from operation in the future. Human error was an important feature of these problems. NB Power had already introduced safety culture training for their staff, but they will need to undertake further work urgently to resolve the problems. Three of Point Lepreau's special safety systems failed to meet their availability targets during 1995. NB Power's safety analysis program progress slowed during 1995, due to the additional workload from the outage. The Point Lepreau's training, quality assurance and safeguards related activities continued to function satisfactorily. They have assigned additional resources to emergency preparedness planning, which should enable them to take a more pro-active approach in this area. 7 tabs., 5 figs

Socio-economic impacts of nuclear generating stations

International Nuclear Information System (INIS)

Weisiger, M.L.; Pijawka, K.D.

1982-07-01

This report documents a case study of the socio-economic impacts of the construction and operation of the St. Lucie nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period, 1980-1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

IEEE No. 323, IEEE trial-use standard: General guide for qualifying Class I electric equipment for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This document describes the basic requirements for the qualification of Class I electric equipment. This is equipment which is essential to the safe shutdown and isolation of the reactor or whose failure or damage could result in significant release of radioactive material. The purpose of this document is to provide guidance for demonstrating the qualifications of electrical equipment as required in the IEEE Std 279 -- Criteria for Nuclear Power Generating Station Protection Systems, and IEEE Std 308 -- Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations. The qualification methods described may be used in conjunction with the Guides for qualifying specific types of equipment, (see Foreword), for updating qualification following modifications or for qualifying equipment for which no applicable Guide exists

El estreno de Las brujas de Salem en el teatro español de Madrid (1956-1957

Directory of Open Access Journals (Sweden)

Gil Fombellida, M. Carmen

2002-06-01

Full Text Available In 1956, the director of the Español theatre, José Tamayo, decided to stage this play by Arthur Miller, backed by the warm welcome on the part of the audience, by the critics that other works from the same author had received, such as, for example. Death of a salesman, which had also been directed by Tamayo in 1952, as well as by the increasing interest that Miller's theatrical proposals arose during the 50s. The political situation at that moment, the censorship and the general public's tastes marked the debut of The Crucible (Las brujas de Salem at Madrid's stages. The artistic proposal by Tamayo turned out as risky as the ideological one, mostly taking into account that the plays that were succeeding at that moment were musical comedies and revues. Against all odds, the play situated among one of the most watched ones and one that created most expectation among specialised columnists of the time. An analysis of the numerous critics that appeared after its presentation explains the curiosity that this setup originated, as well as the reasons for its success: the ideological connotations of the play, the quality of its adaptation, its spectacular staging and the work carried out by most actors and actresses, all which justified the great welcome on the part of spectators and the running of the play until performance number 99 was reached.En 1956, el director del teatro Español de Madrid, José Tamayo, decidió poner en escena el drama de Arthur Miller, La brujas de Salem (The Crucible, respaldado por la gran acogida de los espectadores y la crítica hacia otros de los textos del escritor norteamericano. La muerte de un viajante, dirigido también por Tamayo en 1952, y por el creciente interés que las propuestas escénicas de Miller despertaron durante la década de los cincuenta. Las circunstancias políticas del momento, la censura y los gustos del gran público marcaron el estreno de Las brujas de Salem en los escenarios madrileños. La

Methodology for characterizing the environmental impacts of hydroelectric generating stations : a case study of Farmer Rapids

International Nuclear Information System (INIS)

Lemieux, C.; Renaud, S.; Begin, P.; Belzile, L.; Caumartin, J.

2006-01-01

This paper described a novel methodology used to characterize the downstream section of a generating station that was not navigable by boat. The method was used as part of a fish habitat characterization study conducted in the Farmers Rapids area of Quebec. The purpose of the study was to identify the discharges and water levels needed to preserve fish habitats in the region. Initially, experimental fishing was undertaken to locate, validate and characterize fish habitats. Habitat models were then developed using a microhabitat modelling method to establish pertinent discharges and water levels. In order to model areas that were not navigable by boat, discharges released by the generating station were reduced to a minimum to temporarily decrease water levels and expose the river. High definition aerial photography and topographic mapping was conducted. The information obtained from the 2 procedures was then used to describe and map the riverbed substrate as well as the bathymetry and aquatic habitats. A 2D hydrodynamic model was then used to simulate water flows in the area at various discharges. The results of the hydrodynamic models and the habitat models were then used to establish appropriate discharges for optimal fish habitats

IEEE recommended practices for seismic qualification of Class 1E equipment for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1975-01-01

The IEEE has developed this document to provide direction for developing programs to seismically qualify Class 1E equipment for nuclear power generating stations. It supplements IEEE Std 323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, which describes the basic requirements for equipment qualification. The Class 1E equipment to be qualified by produres or standards established by this document are of many forms, characteristics, and materials; therefore, the document presents many acceptable methods with the intent of permitting the user to make a judicious selection from among the various options. In making such a selection, the user should choose those that best meet a particular equipment's requirements. Further, in using this document as a specification for the purchase of equipment, the many options should also be recognized and the document invoked accordingly. It is recommended that the need for specific standards for the seismic qualifiction of particular kinds of equipment be evaluated by those responsible for such documents and that consideration be given to the application of particular methods from these documents which are most suitable

Operating experience feedback report -- turbine-generator overspeed protection systems: Commercial power reactors. Volume 11

International Nuclear Information System (INIS)

Ornstein, H.L.

1995-04-01

This report presents the results of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) review of operating experience of main turbine-generator overspeed and overspeed protection systems. It includes an indepth examination of the turbine overspeed event which occurred on November 9, 1991, at the Salem Unit 2 Nuclear Power Plant. It also provides information concerning actions taken by other utilities and the turbine manufacturers as a result of the Salem overspeed event. AEOD's study reviewed operating procedures and plant practices. It noted differences between turbine manufacturer designs and recommendations for operations, maintenance, and testing, and also identified significant variations in the manner that individual plants maintain and test their turbine overspeed protection systems. AEOD's study provides insight into the shortcomings in the design, operation, maintenance, testing, and human factors associated with turbine overspeed protection systems. Operating experience indicates that the frequency of turbine overspeed events is higher than previously thought and that the bases for demonstrating compliance with NRC's General Design Criterion (GDC) 4, Environmental and dynamic effects design bases, may be nonconservative with respect to the assumed frequency

O paraíso não é aqui: a violência contra a mulher emTatiana Salem Levy

Directory of Open Access Journals (Sweden)

Paula Queiroz Dutra

2016-01-01

Full Text Available Este trabajo tiene como objetivo analizar las representaciones de las distintas formas de violencia contra la mujer en la novela Paraíso (2014, de la escritora brasileña Tatiana Salem Levy. Se busca comprender y problematizar la representación del dolor del otro y del posicionamiento de las mujeres frente a situaciones de violencia dentro de la novela. Además, se pretende observar si la representación de la violencia sufrida por los personajes femeninos, tanto en el espacio público como en el doméstico, contribuye a una crítica a la violencia contra la mujer, deconstruyendo estereotipos de sumisión y victimización.

IEEE standard for qualification of class 1E lead storage batteries for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1979-01-01

IEEE Std 323-1974, Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, was developed to provide guidance for demonstrating and documenting the adequacy of electrical equipment used in all Class 1E and interface systems. This standard, IEEE Std 535-1979, was developed to provide specific methods and type test procedures for lead storage batteries in reference to IEEE Std 323-1974

Electric utilities deregulation and its impact on nuclear power generating stations

International Nuclear Information System (INIS)

Trehan, N.K.

1998-01-01

Under restructuring and deregulation, it is not clear as to who would have the responsibility, and what obligations the market participants would have to ensure that the electrical system reliability (stability) is maintained. Due to the dynamic nature of the electrical grid, especially with the implementation of restructuring and deregulation, vulnerabilities exist which may impact the reliability (stability) of the offsite electrical power system. In a nuclear power generating unit, an offsite electric power system and an onsite electric power system are required to permit the functioning of structures, systems, and components which are important to safety. The safety function for each system is to provide sufficient capacity and capability to assure that the containment integrity is maintained during power operation or in the event of a postulated accident. Analyses performed by the applicants must verify that the electrical grid remains stable in the event of a loss of the nuclear unit generator, the largest other unit on the grid or the most critical transmission line. The stability of the electric grid is assumed in the safety analyses and a change in it would impact those analyses. However, it may impact the availability of a stable electric power to the safety buses because of the limited number of available transmission lines. This paper discusses electrical power generation and demand, reserve margins, power transfer capability, development of new innovative technologies to compensate for lack of the construction of transmission lines, legislation for the formulation of a self regulation organization (SRO), grid disturbances that may lead to a voltage collapse, and the vulnerabilities which may impact the availability of a stable power to the nuclear power generating stations

Use of intelligent loop diagrams at San Onofre Nuclear Generation Station (SONGS)

International Nuclear Information System (INIS)

Groves, J.E.; Johnson, K.I.; Foulk, J.; Reinschmidt, K.F.; Tutos, N.C.

1991-01-01

The use of advanced information systems will result in five million dollars potential cost reduction and two years less time for producing over 2000 Instrumentation and Control Loop Diagrams for the three nuclear units at San Onofre Nuclear Generating Station (SONGS). This new information technology will also assist plant management at SONGS in generating even larger savings from reduction in operations and maintenance costs. The key element of the new solution is the use of plant drawings, the traditional primary source of plant information, for on-line access to all plant databases and information systems, by replacing paper drawings with intelligent electronic drawings. The implementation of this concept for the Instrumentation and Control Loop Diagrams, presently in progress, is part of the Integrated Nuclear Data Management Systems (INDAMS) program at SONGS, a joint effort which includes support from Stone and Webster Advanced Systems Development Services, International Business Machines Corporation (IBM), and Dassault Systems of France. The initial results have encouraged plant management to speed up the implementation process

The ''controbloc'', a programmable automatic device for the 1,300 MW generation of power stations

International Nuclear Information System (INIS)

Pralus, B.; Winzelle, J.C.

1983-01-01

Technological progress in the field of microelectronics has led to the development of an automatic control device, the ''controbloc'', for operating and controlling nuclear power plants. The ''controbloc'' will be used in automatic systems with a high degree of safety and versatility and is now being installed in the first of the new generation 1,300 MW power stations. The main characteristics of the device and the evaluation tests which have been carried out are described [fr

Radio-location of mobile stations in third generation networks

Directory of Open Access Journals (Sweden)

Milan Manojle Šunjevarić

2013-06-01

Full Text Available Mobile station localization in mobile networks started with simple methods (e.g. Cell-ID method which required only slight modifications of network infrastructures. Principally, it was about network localization by which a localization service became available to all types of mobile phones. Due to low precision, the initiated development of more sophisticated methods has not been finished yet. Among the advanced location-based methods are those based on the measurement of location parameters in the time domain. In this paper the general consideration of radio location methods in 3G (UMTS radio networks is presented. The use of time based measurement methods was analysed in detail. Due to the limited article length, the use of other locating methods in 3G networks (based on power measurements, on radio direction measurement, and on cells identification – Cell ID and global positioning system - GPS are not described. Introduction Mobile station localization within modern cellular networks increases the level of user security and opens wide opportunities for commercial operators who provide this service. The major obstacle for the implementation of this service, which also prevents its practical usage, is the modification of the existing network infrastructure. In general, depending on the infrastructure used, positioning methods can be divided into two groups: integrated and independent. Integrated methods are primarily created for communication networks. A possibility to locate users represents just an additional service within a radio network. Independent methods are totally detached from the communication network in which the user whose location is being determined is. Radio location methods Determining the location of a mobile radio station is performed by determining the intersection of two or more lines of position. These lines represent the position of the set of points at which the mobile station may be located. These lines can be: (a

The Energy Cost Analysis of Hybrid Systems and Diesel Generators in Powering Selected Base Transceiver Station Locations in Nigeria

Directory of Open Access Journals (Sweden)

Peter Ozaveshe Oviroh

2018-03-01

Full Text Available As more locations gain access to telecommunication, there is a growing demand to provide energy in a reliable, efficient and environmentally friendly manner while effectively addressing growing energy needs. Erratic power supply and rising operation costs (OPEX in Nigeria have increased the need to harness local renewable energy sources. Thus, identifying the right generator schedule with the renewable system to reduce OPEX is a priority for operators and vendors. This study evaluates the energy costs of hybrid systems with different generator schedules in powering base transceiver stations in Nigeria using the Hybrid Optimization Model for Electric Renewable (HOMER. A load range of 4 kW to 8 kW was considered using: (i an optimised generator schedule; (ii forced-on generator schedule and (iii the generator-only schedule. The results showed an optimal LCOE range between averages of USD 0.156/kWh to 0.172/kWh for the 8 kW load. The percent energy contribution by generator ranges from 52.80% to 60.90%, and by the solar PV system, 39.10% to 47.20%. Excess energy ranges from 0.03% to 14.98%. The optimised generator schedule has the highest solar PV penetration of 56.8%. The OPEX savings on fuel ranges from 41.68% to 47% for the different load schedules and carbon emission savings of 4222 kg to 31,428.36 kg. The simulation results shows that powering base stations using the optimised hybrid system schedule would be a better option for the telecom industry.

Application of best estimate and uncertainty safety analysis methodology to loss of flow events at Ontario's Power Generation's Darlington Nuclear Generating Station

International Nuclear Information System (INIS)

Huget, R.G.; Lau, D.K.; Luxat, J.C.

2001-01-01

Ontario Power Generation (OPG) is currently developing a new safety analysis methodology based on best estimate and uncertainty (BEAU) analysis. The framework and elements of the new safety analysis methodology are defined. The evolution of safety analysis technology at OPG has been thoroughly documented. Over the years, the use of conservative limiting assumptions in OPG safety analyses has led to gradual erosion of predicted safety margins. The main purpose of the new methodology is to provide a more realistic quantification of safety margins within a probabilistic framework, using best estimate results, with an integrated accounting of the underlying uncertainties. Another objective of the new methodology is to provide a cost-effective means for on-going safety analysis support of OPG's nuclear generating stations. Discovery issues and plant aging effects require that the safety analyses be periodically revised and, in the past, the cost of reanalysis at OPG has been significant. As OPG enters the new competitive marketplace for electricity, there is a strong need to conduct safety analysis in a less cumbersome manner. This paper presents the results of the first licensing application of the new methodology in support of planned design modifications to the shutdown systems (SDSs) at Darlington Nuclear Generating Station (NGS). The design modifications restore dual trip parameter coverage over the full range of reactor power for certain postulated loss-of-flow (LOF) events. The application of BEAU analysis to the single heat transport pump trip event provides a realistic estimation of the safety margins for the primary and backup trip parameters. These margins are significantly larger than those predicted by conventional limit of the operating envelope (LOE) analysis techniques. (author)

A recommended approach for calculating degraded voltage relay setpoints for nuclear generating stations

International Nuclear Information System (INIS)

Jancauskas, J.R.

1994-01-01

The purpose of degrading voltage relays (DVRs) is to ensure that adequate voltage is available to operate all Class 1E loads at all voltage distribution levels. Should voltage drop below the setpoint of the DVRs, the Class 1E power system is disconnected from its supply and resequenced onto the diesel generators in order to restore system voltages to acceptable levels. These relays represent one of the two levels of voltage protection required for the onsite power system. Determining the proper setpoint for degraded voltage relays in nuclear generating stations is a complex task which requires a complete understanding of the Class 1E power distribution system. Despite the importance of degraded voltage relay setpoint calculations, most of the available references only give clues on how not to set these relays rather than provide guidance on how to determine the appropriate setpoint. This paper presents an approach for performing these calculations which attempts to ensure that all of the relevant design issues are addressed

[STEM on Station Education

Science.gov (United States)

Lundebjerg, Kristen

2016-01-01

The STEM on Station team is part of Education which is part of the External Relations organization (ERO). ERO has traditional goals based around BHAG (Big Hairy Audacious Goal). The BHAG model is simplified to a saying: Everything we do stimulates actions by others to advance human space exploration. The STEM on Station education initiate is a project focused on bringing off the earth research and learning into classrooms. Educational resources such as lesson plans, activities to connect with the space station and STEM related contests are available and hosted by the STEM on Station team along with their partners such as Texas Instruments. These educational activities engage teachers and students in the current happenings aboard the international space station, inspiring the next generation of space explorers.

Tritium releases from the Pickering Nuclear Generating Station and birth defects and infant mortality in nearby communities 1971-1988

International Nuclear Information System (INIS)

Johnson, K.C.; Rouleau, J.

1991-10-01

This study was commissioned to examine whether there were elevated rates of stillbirth, birth defects, or death in the first year of life between 1971 and 1988 among offspring of residents of communities within a 25-kilometre radius of the Pickering Nuclear Generating Station. The study was also to investigate whether there were any statistical associations between the monthly airborne or waterborne tritium emissions from the Pickering Nuclear Generating Station and the rates of these reproductive outcomes. Overall analysis did not support a hypothesis of increased rates of stillbirths, neonatal mortality or infant mortality near the Pickering Nuclear Generating Station, or a hypothesis of increased birth prevalence of birth defects for 21 of 22 diagnostic categories. The prevalence of Down Syndrome was elevated in both Pickering and Ajax; however, there was no consistent pattern between tritium release levels and Down Syndrome prevalence, chance could not be ruled out for the associations between Down Syndrome and tritium releases or ground-monitored concentrations, the association was detected in an analysis where multiple testing was done which may turn up significant associations by change, and maternal residence at birth and early in pregnancy needs to be verified. The association between Down Syndrome and low-level radiation remains indeterminate when existing evidence from epidemiological studies is summed. The estimated radiation exposure from the nuclear plant for residents of Pickering and Ajax is lower by a factor of 100 than the normal natural background radiation. Further study is recommended. (21 tabs., 29 figs., 5 maps, 37 refs.)

Solid polymer electrolyte water electrolysis system development. [to generate oxygen for manned space station applications

Science.gov (United States)

1975-01-01

Solid polymer electrolyte technology used in a water electrolysis system (WES) to generate oxygen and hydrogen for manned space station applications was investigated. A four-man rated, low pressure breadboard water electrolysis system with the necessary instrumentation and controls was fabricated and tested. A six man rated, high pressure, high temperature, advanced preprototype WES was developed. This configuration included the design and development of an advanced water electrolysis module, capable of operation at 400 psig and 200 F, and a dynamic phase separator/pump in place of a passive phase separator design. Evaluation of this system demonstrated the goal of safe, unattended automated operation at high pressure and high temperature with an accumulated gas generation time of over 1000 hours.

AECB staff annual assessment of the Bruce B Nuclear Generating Station for the year 1994

International Nuclear Information System (INIS)

1995-06-01

AECB staff believes Ontario Hydro operated Bruce B safely in 1994. The Bruce B reactors will remain limited to 88% full power until Ontario Hydro is able to demonstrate that it is safe to operate at higher powers. Ontario Hydro's compliance with AECB regulations and the Operating Licence was satisfactory. AECB found no major violations. The station performance was similar to previous years. Radiation doses to workers and the public were well below the legal limits and also remained below Ontario Hydro's internal targets. Worker radiation doses increased slightly but were comparable to previous years. Inspection of pressure tubes and steam generator tubes by Ontario Hydro showed continuing tube degradation. However, we believe that Ontario Hydro made progress in correcting and managing these problems. Ontario Hydro carried out a full-scale fire drill at Bruce B in 1994. AECB witnessed the drill and were pleased to observe a significant improvement in the station's fire-fighting capability. 7 tabs., 4 figs

IEEE standard for type test of class 1E electric cables, field splices, and connections for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1974-01-01

The Institute of Electrical and Electronics Engineers has generated this document to provide guidance for developing a program to type test cables, field splices, and connections and obtain specific type test data. It supplements IEEE Std 323-1974 Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations, which describes basic requirements for equipment qualification. It is the integrated performance of the structures, fluid systems, the electrical systems, the instrumentation systems of the station, and in particular, the plant protection system, that limits the consequences of accidents. Seismic effects on installed cable systems are not within the scope of this document. Section 2 of this guide is an example of type tests. It is the purpose of this guide to deal with cable and connections; however, at the time of issue, detailed examples of tests for connections were not available

Data communications method for mobile network in fourth generation communications system, involves delivering decoded data to mobile station from relay station, where mobile station receives data from both relay and base stations

DEFF Research Database (Denmark)

2008-01-01

The method involves utilizing a base station (BS) (100) to transmit data to a relay station (RS) (110) and a mobile station (MS) (120), where the data includes two messages. The BS is utilized to transmit the two messages by utilizing a linear combination method, and the data is received in the RS...

Aerial radiological survey of the San Onofre Nuclear Generating Station and surrounding area, San Clemente, California

International Nuclear Information System (INIS)

Hilton, L.K.

1980-12-01

An airborne radiological survey of an 11 km 2 area surrounding the San Onofre Nuclear Generating Station was made 9 to 17 January 1980. Count rates observed at 60 m altitude were converted to exposure rates at 1 m above the ground and are presented in the form of an isopleth map. Detected radioisotopes and their associated gamma ray exposure rates were consistent with that expected from normal background emitters, except directly over the plant

Socio-economic impacts of nuclear generating stations: Arkansas Nuclear One Station case study

International Nuclear Information System (INIS)

Pijawka, K.D.

1982-07-01

This report documents a case study of the socio-economic impacts of the construction and operation of the Arkansas Nuclear One nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

Mattagami River Lake sturgeon entrainment : Little Long generating station facilities

International Nuclear Information System (INIS)

Seyler, J.; Evers, J.; McKinley, S.; Evans, R.R.; Prevost, G.; Carson, R.; Phoenix, D.

1996-01-01

This project and publication is the result of a collaborative effort by other Large River Ecosystem Unit of Northeast Science (NEST), Ontario Hydro in Kapuskasing, and the New Post First Nation in Cochrane, Ontario, designed to investigate potential solutions to minimize or eliminate the problem of trapped lake sturgeon in the Adam Creek Diversion. The Adam Creek Dam is used to divert excess water from the Mattagami River hydroelectric complex which consists of the Little Long, Smoky Falls, Harmon and Kipling generating stations. The lake sturgeon entrainment problem in the area was discovered in 1990. Potential solutions to the problem include the redirection of flows to mainstream, the placement of a rope barrier, electrical deterrents, physical/electrical guidance systems, sound deterrents, gate modifications, and the continued relocation of fish. The advantages and disadvantages of each of these potential solutions are discussed. Results of the analysis indicated that perceptual and physical barriers have the greatest potential to minimize lake sturgeon entrainment in Adam Creek. 25 refs., 2 tabs., 3 figs., 6 appendices

Environmental emissions control programs at Lambton TGS [Thermal Generating Station

International Nuclear Information System (INIS)

Kalvins, A.K.

1992-01-01

Ontario Hydro's air emissions control programs at Lambton thermal generating station, both committed and planned, are reviewed, and their potential impacts on emissions, effluents and wastes are discussed. Control technologies examined include flue gas conditioning, wet limestone scrubbing, combustion process modifications, urea injection, and selective catalytic reduction. The implementation of these technologies has the potential to create new solid and liquid waste disposal problems, the full extent of which is often not realized at the process selection stage. For example, selective noncatalytic reduction using urea injection can lead to increased CO emissions, escape of unreacted ammonia from the stack at levels of 5-50 ppM, increase in N 2 O emissions, contamination of fly ash, gypsum and waste water with ammonia, and an increase in CO 2 emissions of less than 0.4% due to increased power consumption. Optimum performance of the air emissions control systems, with minimum negative impact on the environment, requires consideration of the impact of these systems on all waste streams. 11 refs., 3 figs., 1 tab

IEEE Std 383-1974: IEEE standard for type test of Class IE electric cables, field splices, and connections for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard provides direction for establishing type tests which may be used in qualifying Class 1E electric cables, field splices, and other connections for service in nuclear power generating stations. General guidelines for qualifications are given in IEEE Std 323-1974, Standard for Qualifying Class IE Electric Equipment for Nuclear Power Generating Stations. Categories of cables covered are those used for power control and instrumentation services. Though intended primarily to pertain to cable for field installation, this guide may also be used for the qualification of internal wiring of manufactured devices. This guide does not cover cables for service within the reactor vessel

Prevalence of Oral Mucosal Lesions among Dental Patients with Mixed Habits in Salem District - A Study

Science.gov (United States)

Karthik, R.; Mohan, N.

2017-01-01

Background: The practice of betel nut chewing with or without tobacco is still practiced in south india, salem inspite of its harmful effects. Methodology: 200 Patients visiting the outpatient department, Oral medicine and radiology from Aug 2015 to Aug 2016. Result and Conclusion: In our study, 3 women were exclusively churut smokers. Thirty-eight percent of the dental patients were beedi smoker, 32% were tobacco chewers, 12% were both betel nut and tobacco chewers, 8% were exclusively betel nut chewers, 1% of the dental population were exclusively churut smokers. Mean age group of the study population is 50.2 (14.4). There are 28 females and 172 males in the study group. Chi-square test revealed a statistically significant difference (P = 0.001) between males and females based on soft-tissue findings and no statistically significant difference (P = 0.572) between males and females based on distribution of hard-tissue findings. PMID:29284937

Experience with reactor power cutback system at Palo Verde nuclear generating station

International Nuclear Information System (INIS)

Chari, D.R.; Rec, J.R.; Simoni, L.P.; Eimar, R.L.; Sowers, G.W.

1987-01-01

Palo Verde Nuclear Generating Station (PVNGS) is a three unit site which illustrates System 80 nuclear steam supply system (NSSS) design. The System 80 NSSS is the Combustion Engineering (C-E) standard design rated at 3817 Mwth. PVNGS Units 1 and 2 achieved commercial operation on February 13, 1986 and September 22, 1986, respectively, while Unit 3 has a forecast date for commercial operation in the third quarter of 1987. The System 80 design incorporates a reactor power cutback system (RPCS) feature which reduces plant trips caused by two common initiating events: loss of load/turbine trip (LOL) and loss of one main feedwater pump (LOMFWP). The key design objective of the RPCS is to improve overall plant availability and performance, while minimizing challenges to the plant safety system

A multi state simulation model of the maintenance for a power generating station

International Nuclear Information System (INIS)

Karlsson, B.O.

1980-09-01

A multistate simulation model for a thermal power generating station is described. The performance is modelled as a function of the system structure, the component reliability, the number of repair crews, the repair times and the availability of spare parts. Each component can be in either of four states: failed, working, postponed, or standby. A component will be in the postponed state, if due to failures in other components it is turned off. Two different types of failures are assumed: minor and severe. Evaluation of the system state is performed by repeated use of four elementary system functions: series, parallel, k-out-of-n, and standby k/l/n. Numerical results for a case study are presented. (author)

Recent experience related to neutronic transients in Ontario Hydro CANDU nuclear generating stations

International Nuclear Information System (INIS)

Frescura, G.M.; Smith, A.J.; Lau, J.H.

1991-01-01

Ontario Hydro presently operates 18 CANDU reactors in the province of Ontario, Canada. All of these reactors are of the CANDU Pressurized Heavy Water design, although their design features differ somewhat reflecting the evolution that has taken place from 1971 when the first Pickering unit started operation to the present as the Darlington units are being placed in service. Over the last three years, two significant neutronic transients took place at the Pickering Nuclear Generating Station 'A' (NGS A) one of which resulted in a number of fuel failures. Both events provided valuable lessons in the areas of operational safety, fuel performance And accident analysis. The events and the lessons learned are discussed in this paper

Utilization of waste heat from electricity generating stations

International Nuclear Information System (INIS)

Robertson, R.F.S.

1977-06-01

Historically the nuclear power station has been designed solely as an electricity producer. But in Canada today only 15 percent of our energy consumption is as electricity. The non-electrical needs today are supplied almost entirely by natural gas and oil. There is an incentive to see whether a nuclear station could supply energy for some of these non-electrical needs, thus freeing gas and oil for uses for which they may be more valuable and suitable, especially in transportation. A group located at the Whiteshell Nuclear Research Establishment undertook a series of studies to examine this problem. These studies were done in sufficient depth to provide technological and economic answers, and as a result several reports have been published on various topics. In this report, the findings from these studies are drawn together in an assessment of the potential in Canada for using waste heat. (author)

Duke Power Company - McGuire Nuclear Station: steam-generator hideout return and cleanup

International Nuclear Information System (INIS)

Anon.

1986-01-01

McGuire Nuclear Station steam generator hideout return and cleanup are discussed. Hideout return data are presented for Unit 1 shutdowns that occurred on November 23, 1984, and April 19, 1985, and a Unit 2 shutdown on January 25, 1985. The data are presented as the concentrations of various species as a function of time after power reduction and primary water temperature. The steam generator blowdown as a function of time after power reduction is also presented. The concentrations of sodium, potassium, calcium, magnesium, aluminum, iron, and copper cations, and chloride, fluoride, sulfate, phosphate and nitrite anions were monitored during the each shutdown. Silica was also measured in the two 1985 shutdowns. The return of sulfate, phosphate, calcium and magnesium showed retrograde solubility. Silica concentrations showed an increase as the temperature decreased to about 450 to 500 0 F and then they decreased as the temperature decreased. McGuire has a holf point at 300 at 350 0 F to clean up the steam generator secondary water. The return of sulfates should occur within 4 to 6 hours. The blowdown is maximized to reduce the secondary water impurity concentrations. Cleanup continues until the sulfate concentration is reduced to below 100 ppb. At that point cooldown is continued

IEEE Standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1980-01-01

This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1979 and IEEE Std 308-1978, can be demonstrated by using the procedures provided in this Standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other types batteries are beyond the scope of this Standard

On the legal nature of electricity supply contracts concluded by electricity companies and power stations generating electricity from renewable energy sources

International Nuclear Information System (INIS)

Herrmann, B.J.

1998-01-01

Section 2 of the German Act for enhanced use of electricity from renewable energy sources (StEG) defines the obligation to contract but not the contractual obligations, i.e. the conditions of performance of the contract (supply and purchase of electricity and the legal obligations of contractors). The analysis here shows that characterising this mandatory contract required by the act as an agreement of purchase and sale more appropriately describes the legal nature of the contract and the intent of the legislator than other contracts for supply and purchase of electricity, as for instance those concluded by electric utilities and their customers. One specific aspect elaborated by the author is that the StEG does not constitute an obligation to supply on the part of the renewable energy generating power station, so that the power station operator is not obliged to ensure availability of the electricity at any time or in terms of supplies that can be called off by the purchasing utility, whereas the electric utility is obliged by section 2 of the StEG to purchase the contractual amounts from the generating station. (orig./CB) [de

Chemistry control experiences at Kaiga Generating Station (KGS), NPCIL

International Nuclear Information System (INIS)

Harikrishna, K.; Somasundaram, K.M.; Sanathkumar, V.V.; Nageswara Rao, G.

2006-01-01

The Chemistry control section at Kaiga Generating Station (KGS), NPCIL had keenly pursued many developmental works and projects which had not only improved the system performance and reliability but also largely benefited the Station by many ways. The highlights of some of the major developmental works that have contributed significantly are: 1. Studies on frequent and sharp rise in dew point values of AGMS: In the Annulus Gas Monitoring Systems (AGMS) of KGS units, it was observed that the system dew points were rising very sharply and abruptly. The systematic studies revealed the presence of Hydrogen impurity in CO 2 gas cylinders, hence emphasized the need to ensure the gaseous contents before injecting the media from the cylinders to the system. 2. a. Studies on frequent tube failures of TG auxiliary coolers: The detailed studies and investigation revealed that under deposit corrosion contributed by microbiological attack was the main cause for frequent failures of 90/10 Cupro Nickel cooler tubes which could be minimized either by resorting to periodical mechanical/chemical cleaning of cooler tubes or by regular chemical treatment with a suitable chemical formulation. b. Development of suitable chemical formulation for chemical cleaning of TG auxiliary coolers: A series of in-house experiments at site resulted in developing a suitable chemical formulation for effective cleaning of 90/10 Cupro Nickel cooler tubes. The formulation with 1 % w/w Citric acid with pH adjusted to 8.0 by Ammonia in first step followed by 1 % w/w EDTA with pH adjusted to 9.0 by Hydrazine in the second step could yield more than 90 % cleanliness. 3. Chemical cleaning of cooling circuits of AHUs: An in-house formulation was developed and used for chemical cleaning of cooling circuits (with copper tubes) of AHUs. Post chemical cleaning, the room temperatures decreased by 3-4 degC, hence resulted in better cooling. 4. Enhancement in service period of BBD IX columns: The service period of

Selective analysis of power plant operation on the Hudson River with emphasis on the Bowline Point Generating Station. Volume 1

International Nuclear Information System (INIS)

Barnthouse, L.W.; Cannon, J.B.; Christensen, S.G.

1977-07-01

A comprehensive study of the effects of power plant operation on the Hudson River was conducted. The study included thermal, biological, and air quality effects of existing and planned electrical generating stations. This section on thermal impacts presents a comprehensive mathematical modeling and computer simulation study of the effects of heat rejection from the plants. The overall study consisted of three major parts: near-field analysis; far-field analysis; and zone-matched near-field/far-field analysis. Near-field analyses were completed for Roseton, Danskammer, and Bowline Point Generating Stations, and near-field dilution ratios range from a low of about 2 for Bowline Point and 3 for Roseton to a maximum of 6 for both plants. The far-field analysis included a critical review of existing studies and a parametric review of operating plants. The maximum thermal load case, based on hypothetical 1974 river conditions, gives the daily maximum cross-section-averaged and 2-mile-segment-averaged water temperatures as 83.80 0 F in the vicinity of the Indian Point Station and 83.25 0 F in the vicinity of the Bowline Station. This maximum case will be significantly modified if cooling towers are used at certain units. A full analysis and discussion of these cases is presented. A study of the Hudson River striped bass population is divided into the following eight subsections: distribution of striped bass eggs, larvae, and juveniles in the Hudson River; entrainment mortality factor; intake factor; impingement; effects of discharges; compensation; model estimates of percent reduction; and Hudson River striped bass stock

Control room habitability survey of licensed commercial nuclear power generating stations

International Nuclear Information System (INIS)

Driscoll, J.W.

1988-10-01

This document presents the results of a survey of control room habitability systems at twelve commercial nuclear generating stations. The survey, conducted by Argonne National Laboratory (ANL), is part of an NRC program initiated in response to concerns and recommendations of the Advisory Committee on Reactor Safeguards (ACRS). The major conclusion of the report is that the numerous types of potentially significant discrepancies found among the surveyed plants may be indicative of similar discrepancies throughout the industry. The report provides plant-specific and generalized findings regarding safety functions with respect to the consistency of the design, construction, operation and testing of control room habitability systems and corresponding Technical Specifications compared with descriptions provided in the license basis documentation including assumptions in the operator toxic gas concentration and radiation dose calculations. Calculations of operator toxic gas concentrations and radiation doses were provided in the license basis documentation and were not performed by the ANL survey team. Recommendation for improvements are provided in the report

Petrology and geochemistry of dolerite dykes of Dharmapuri and Salem districts of Tamil Nadu

International Nuclear Information System (INIS)

Jayabalan, M.; Umamaheswaran, O.; Suresh, A.

2012-01-01

Dolerite dyke sets occur distributed in the Dharmapuri and Salem districts of northern Tamil nadu. These dykes have been emplaced in the older basement composed of granulite and gneissic rocks and cut across the later formed lineament controlled alkaline complexes. They are composed of medium to coarse calcic plagioclase and clinopyroxene with biotite, amphibole, uralite, olivine, orthopyroxene, and anhedral quartz as accessories. Based on geochemical characters, the olivine bearing dykes are classed as Type I and the quartz bearing dykes as Type II. The Type I dykes resemble basalt and the Type II dykes, basaltic andesite. They display LILE> HFSE in terms of abundance. The REE values indicate enrichment of LREE relative to MREE and HREE and an E-MORB or Plume MORB signature. The geochemistry of the sampled dykes suggests derivation from a mantle plume. This plume was emplaced into the garnet lherzolite layer and subsequently into the shallower spinel lherzolite layer in the mantle. Polybaric melting of lherzolite protoliths with varying proportions of garnet and spinel occurred with subsequent fractionation to produce a source melts with E-MORB characteristics. Emplacement of these dykes was aided by crustal extension and associated fracturing to develop a dyke swarm. (author)

Co-ordination of federal and provincial environmental assessment processes for the Point Lepreau Generating Station Solid Radioactive Waste Management Facility modifications

International Nuclear Information System (INIS)

Hickman, C.; Thompson, P.D.; Barnes, J.

2006-01-01

Modification of the Solid Radioactive Waste Management Facility at Point Lepreau Generating Station is required to accommodate waste generated during and after an 18-month maintenance outage during which the station would be Refurbished. The modification of the facility triggered both federal and provincial environmental assessment requirements, and these assessments were conducted in a 'coordinated' and cooperative fashion. In this project, the coordinated approach worked well, and provided some significant advantages to the proponent, the public and the regulators. However, there are opportunities for further improvement in future projects, and this paper explores the advantages and disadvantages of this 'co-ordinated' approach. As part of this exploration, there is a discussion of administrative and regulatory changes that the province is considering for the environmental assessment process, and a discussion of the need for a formal 'harmonization' agreement. (author)

IEEE C37.105-1987: IEEE standard for qualifying Class 1E protective relays and auxiliaries for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard describes the basic principles, requirements, and methods for qualifying Class 1E protective relays and auxiliaries such as test and control switches, terminal blocks, and indicating lamps for applications in nuclear power generating stations. When properly employed it can be used to demonstrate the design adequacy of such equipment under normal, abnormal, design basis event and post design basis event conditions in accordance with ANSI/IEEE Std 323-1983. When protective relays and auxiliaries are located in areas not subject to harsh environments, environmental qualification is not required. Protective relays and auxiliaries located inside primary containment in a nuclear power generating station present special conditions beyond the scope of this document. The qualification procedure presented is generic in nature. Other methods may be used at the discretion of the qualifier, provided the basic precepts of ANSI/IEEE Std 32301983 are satisfied

Radioactivity in coal, ashes and selected wastewaters from Canadian coal-fired steam electric generating stations

International Nuclear Information System (INIS)

1985-09-01

Coal is known to contain naturally occurring radioactive elements and there has been speculation that as a results, coal-fuelled power generation stations may be significant emitters of these substances. In this report, the subject of radioactivity is introduced. The kinds of radioactive substances which occur naturally in coal formations, the nature of their emissions and the existing information on their behaviour and their effects on environmental organisms are also reviewed. The results of an examination of levels of alpha, beta and gamma radiaton levels, and the substances which produce them in coals, fly ashes, bottom ashes and related wastewaters at six Canadian coal-fuelled power stations are presented. Difficulties in studies of this nature and the potential effects of these releases on organisms in the adjacent aquatic environment are discussed. Existing and potential technologies for the removal of these substances from wastewaters are examined. In general the releases in wastewaters from the six stations were found to be lower than those known to cause short-term or acute biological effects. The potential for long-term effects from such low-level releases could not be accurately assessed because of the paucity of information. A number of recommendations for: improvements in further studies of this nature; the further examination of the fate of naturally occurring radionuclides in the environment; and the determination of the long-term effects of low levels of naturally occurring radioactive substances on aquatic organisms, are made

The contribution of small hydro power stations to the electricity generation in Greece: Technical and economic considerations

International Nuclear Information System (INIS)

Kaldellis, J.K.

2007-01-01

Hydropower is the most widely used renewable energy source worldwide, contributing almost with 18.5% to the fulfillment of the planet electricity generation. However, most locations in Europe appropriate for the installation of large hydro power stations have already been exploited. Furthermore, there is a significant local communities' opposition towards new large power stations; hence, small hydro power stations remain one of the most attractive opportunities for further utilization of the available hydro potential. Greece and more precisely the country's mainland possesses a significant hydro-power potential which is up to now only partially exploited. In parallel, a large number of private investors have officially expressed their interest in creating small hydro power stations throughout the country, encouraged by the significant Greek State subsidy opportunities for renewable energy applications. However, up to now a relatively small number of projects have been realized, mainly due to decision-making problems, like the administrative bureaucracy, the absence of a rational national water resources management plan and the over-sizing of the proposed installations. Certainly, if the above problems are suitably treated, small hydro-power plants can be proved considerably profitable investments, contributing also remarkably to the national electricity balance and replacing heavy polluting lignite and imported oil. In the context of the above interesting issues, the present study reviews in detail the existing situation of small hydropower plants in Greece and investigates their future prospects as far as the energy, economic and environmental contribution are concerned

Management of main generator condition during long term plant shut down at Higashidori Nuclear Power Station Unit 1

International Nuclear Information System (INIS)

Kato, Seiji

2014-01-01

Higashidori Nuclear Power Station Unit 1 shut down on February 6, 2011 to start 4th refuel outage. On March 11, 2011, we keep going refuel outage on this moment a large earthquake occurred and tsunami was generated following it which called 'Great East Japan Earthquake'. Refuel outage takes 3 ∼ 5 months normally but Higashidori NPS still keeping shut down over 3 years due to some issues. In this paper, we introduce about management of Main generator condition during long term plant shut down situation in addition to normal plant shut down situation to keep well. (author)

Risk impact of planned maintenance configuration at South Texas Project Electric Generating Station

International Nuclear Information System (INIS)

Loh, W.T.; Fleming, K.N.; Grantom, C.R.

2004-01-01

This paper is based on a study done for the Houston Lighting and Power Company. The purpose of this study is to estimate the risk impact of planned maintenance configurations at South Texas Project Electric Generating Station (STPEGS). To date, the focus of the STP probabilistic safety assessment (PSA) program has been to analyze risk in terms of estimates of accident frequencies that are expressed on a time-averaged basis. Thus, estimates of quantities such as severe core damage frequency have been made such that the temporal variations of this frequency with changing plant configurations are averaged out over time. The only condition that has been imposed on these estimates is that the plant is initially operating at full power when potential initiating events might occur. (author)

Sources of the wind power stations

International Nuclear Information System (INIS)

Chudivani, J.; Huettner, L.

2012-01-01

The paper deals with problems of the wind power stations. Describes the basic properties of wind energy. Shows and describes the different types of electrical machines used as a source of electricity in the wind power stations. Shows magnetic fields synchronous generator with salient poles and permanent magnets in the program FEMM. Describes methods for assessing of reversing the effects of the wind power stations on the distribution network. (Authors)

Water pollution and thermal power stations

International Nuclear Information System (INIS)

Maini, A.; Harapanahalli, A.B.

1993-01-01

There are a number of thermal power stations dotting the countryside in India for the generation of electricity. The pollution of environment is continuously increasing in the country with the addition of new coal based power stations and causing both a menace and a hazard to the biota. The paper reviews the problems arising out of water pollution from the coal based thermal power stations. (author). 2 tabs

Diagnostic testing and repair of Hollingsworth Generating Station`s Unit One

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-31

This paper presents a case history of the diagnosis of a hydroelectric generator problem and the corrections implemented. The problem involved an excessive rotor imbalance coupled with a static air gap imbalance that cause severe load-sensitive vibrations. The problem constrained the plant from operating the generator unit throughout the range of its nameplate rating and caused periodic failure of the generator guide and thrust bearing. The paper describes the vibration survey and mechanical survey of the generator rotor, the pre-overhaul diagnosis, the repairs undertaken to the rotor, and the generator performance after the repair, with comparison to the pre-repair condition. The paper concludes with a discussion of the economic, operational, and logistic issues involved in the overhaul.

Power station instrumentation

International Nuclear Information System (INIS)

Jervis, M.W.

1993-01-01

Power stations are characterized by a wide variety of mechanical and electrical plant operating with structures, liquids and gases working at high pressures and temperatures and with large mass flows. The voltages and currents are also the highest that occur in most industries. In order to achieve maximum economy, the plant is operated with relatively small margins from conditions that can cause rapid plant damage, safety implications, and very high financial penalties. In common with other process industries, power stations depend heavily on control and instrumentation. These systems have become particularly significant, in the cost-conscious privatized environment, for providing the means to implement the automation implicit in maintaining safety standards, improving generation efficiency and reducing operating manpower costs. This book is for professional instrumentation engineers who need to known about their use in power stations and power station engineers requiring information about the principles and choice of instrumentation available. There are 8 chapters; chapter 4 on instrumentation for nuclear steam supply systems is indexed separately. (Author)

Electricity supplies in a French nuclear power station

International Nuclear Information System (INIS)

2011-01-01

As the operation of a nuclear power station requires a power supply system enabling this operation as well as the installation safety, this document describes how such systems are designed in the different French nuclear power stations to meet the requirements during a normal operation (when the station produces electricity) or when it is stopped, but also to ensure power supply to equipment ensuring safety functions during an incident or an accident occurring on the installation. More precisely, these safety functions are provided by two independent systems in the French nuclear power stations. Their operation is briefly described. Two different types of nuclear reactors are addressed: pressurised water reactors (PWR) of second generation, EPR (or PWR of third generation)

Confirmatory Survey Results for the Reactor Building Dome Upper Structural Surfaces, Rancho Saco Nuclear Generating Station, Herald, California

International Nuclear Information System (INIS)

Wade C. Adams

2006-01-01

Results from a confirmatory survey of the upper structural surfaces of the Reactor Building Dome at the Rancho Seco Nuclear Generating Station (RSNGS) performed by the Oak Ridge Institute for Science and Education for the NRC. Also includes results of interlaboratory comparison analyses on several archived soil samples that would be provided by RSNGS personnel. The confirmatory surveys were performed on June 7 and 8, 2006

Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992

International Nuclear Information System (INIS)

Hebdon, F.J.

1993-03-01

On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility's actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities

AECL's participation in the commissioning of Point Lepreau generating station unit 1

International Nuclear Information System (INIS)

Chawla, S.; Singh, K.; Yerramilli, S.

1983-05-01

Support from Atomic Energy of Canada Ltd. (AECL) to Point Lepreau during the commissioning program has been in the form of: seconded staff for commissioning program management, preparation of commissioning procedures, and hands-on commissioning of several systems; analysis of test results; engineering service for problem solving and modifications; design engineering for changes and additions; procurement of urgently-needed parts and materials; technological advice; review of operational limits; interpretation of design manuals and assistance with and preparation of submissions to regulatory authorities; and development of equipment and procedures for inspection and repairs. This, together with AECL's experience in the commissioning of other 600 MWe stations, Douglas Point and Ontario Hydro stations, provides AECL with a wide range of expertise for providing operating station support services for CANDU stations

Co-ordination of federal and provincial environmental assessment processes for the Point Lepreau Generating Station Solid Radioactive Waste Management Facility modifications

Energy Technology Data Exchange (ETDEWEB)

Hickman, C.; Thompson, P.D. [Point Lepreau Generating Station, Point Lepreau Refurbishment Project, Lepreau, New Brunswick (Canada); Barnes, J. [Jacques Whitford Environment Ltd., Fredericton, New Brunswick (Canada)

2006-07-01

Modification of the Solid Radioactive Waste Management Facility at Point Lepreau Generating Station is required to accommodate waste generated during and after an 18-month maintenance outage during which the station would be Refurbished. The modification of the facility triggered both federal and provincial environmental assessment requirements, and these assessments were conducted in a 'coordinated' and cooperative fashion. In this project, the coordinated approach worked well, and provided some significant advantages to the proponent, the public and the regulators. However, there are opportunities for further improvement in future projects, and this paper explores the advantages and disadvantages of this 'co-ordinated' approach. As part of this exploration, there is a discussion of administrative and regulatory changes that the province is considering for the environmental assessment process, and a discussion of the need for a formal 'harmonization' agreement. (author)

Niagara pumping generation station inundation mapping and consequence analysis with ArcGIS and Mike 21

Energy Technology Data Exchange (ETDEWEB)

Grover, Patrick; Khayer, Yasmin; Naumov, Aleksey [4DM Inc., Toronto, (Canada); Zhang, Yibing [Ontario Power Generation, Toronto, (Canada)

2010-07-01

Inundation mapping is a key factor of Ontario Power Generation's dam safety program. It is the basis for determining the hazard potential classification of the dam by modelling the consequences of a hypothetical dam failure. This paper presented the project for updating the inundation mapping and consequence analysis study at the Niagara Pump generating station (PGS) reservoir. A complete hydrotechnical assessment of the Niagara PGS reservoir was conducted. The modelling of various breach scenarios was carried out using the 2-D hydrodynamic software MIKE 21 in order to provide the hydraulic data necessary for producing the inundation maps. Updated EPRP maps were produced and a consequence analysis was performed which confirmed the existing hazard classification. The ArcGIS system was used as the underlying framework for all major components of the project. It was found that the use of GIS technologies improve the efficiency of both modelling and analysis.

Superfund Record of Decision (EPA Region 2): NL Industries, Salem County, Pedricktown, NJ. (First remedial action), September 1991

Energy Technology Data Exchange (ETDEWEB)

1991-09-27

The 44-acre NL Industries site is an inactive, secondary lead smelting facility in Pedricktown, Salem County, New Jersey. The site overlies the Cape May aquifer, a potential source of drinking water for local residents. In 1989, EPA began a multi-phased removal action. The Focused Feasibility Study resulted in the issuance of the Early Remedial Action Record of Decision (ROD), designated as Operable Unit (OU2). The nature and extent of remaining contamination on the site and areas adjacent to the site in various environmental media, such as soil, sediment, ground water, surface water, and air, are currently being evaluated and will be addressed as OU1 in a subsequent ROD. The primary contaminants of concern affecting the slag and lead oxide piles, sediment, debris, and standing surface water are metals including arsenic, chromium, and lead. The selected remedial action for the site is included.

Radiological Effluent Technical Specifications (RETS) implementation: Zion Generating Station Units 1 and 2

International Nuclear Information System (INIS)

Serrano, W.; Akers, D.W.; Duce, S.W.; Mandler, J.W.; Simpson, F.B.; Young, T.E.

1985-06-01

A review of the Radiological Effluent Technical Specifications (RETS) of the Zion Generating Station Units 1 and 2 was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7 of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by both EG and G and the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual was reviewed and generally found to be consistent with the NRC review guidelines. 35 refs., 2 figs., 1 tab

Lithological mapping of Kanjamalai hill using hyperspectral remote sensing tools in Salem district, Tamil Nadu, India

Science.gov (United States)

Arulbalaji, Palanisamy; Balasubramanian, Gurugnanam

2017-07-01

This study uses advanced spaceborne thermal emission and reflection radiometer (ASTER) hyperspectral remote sensing techniques to discriminate rock types composing Kanjamalai hill located in the Salem district of Tamil Nadu, India. Kanjamalai hill is of particular interest because it contains economically viable iron ore deposits. ASTER hyperspectral data were subjected to principal component analysis (PCA), independent component analysis (ICA), and minimum noise fraction (MNF) to improve identification of lithologies remotely and to compare these digital data results with published geologic maps. Hyperspectral remote sensing analysis indicates that PCA (R∶G∶B=2∶1∶3), MNF (R∶G∶B=3∶2∶1), and ICA (R∶G∶B=1∶3∶2) provide the best band combination for effective discrimination of lithological rock types composing Kanjamalai hill. The remote sensing-derived lithological map compares favorably with a published geological map from Geological Survey of India and has been verified with ground truth field investigations. Therefore, ASTER data-based lithological mapping provides fast, cost-effective, and accurate geologic data useful for lithological discrimination and identification of ore deposits.

An artificial intelligence heat rate/NOx optimization system for Ontario Hydro`s Lambton Generating Station

Energy Technology Data Exchange (ETDEWEB)

Luk, J.; Bachalo, K.; Henrikson, J. [Ontario Hydro, Toronto, ON (Canada); Roland, W.; Booth, R.C.; Parikh, N.; Radl, B. [Pegasus Technologies Ltd., Painesville, OH (United States)

1998-12-01

The utilization of artificial Intelligence (AI)-based software programs to optimize power plant operations by simultaneously improving heat rate performance and reducing NOx emissions was discussed. While many AI programs were initially used for demonstration purposes, they are now available for commercial use due to their promising results. In 1996, the Fossil Business Unit of Ontario Hydro initiated a study to evaluate AI technology as a tool for optimizing heat rate and NOx reduction in coal fired stations. Tests were conducted at Units 3 and 4 of the Lambton Generation Station, located just south of Sarnia, Ontario. The tests were conducted to examine three desirable options: (1) achieve at least 0.5 per cent improvement in heat rate concurrently with a NOx reduction of at least 5 per cent, (2) optimize on `heat rate` only with minimum improvement of 2 per cent, and optimize `minimal NOx` only with reduction target of 20 per cent or more, and (3) reach a collaborative agreement with a supplier to further explore and develop AI optimization applications for other advanced and more complex plant processes. Results indicated that NOx reduction and heat rate improvement are not contradictory goals. 15 refs., 1 fig.

EMI environment EMC considerations concerning equipment upgrades at a nuclear utility power generating station a case history

International Nuclear Information System (INIS)

Metcalf, M.J.

1993-01-01

As equipment is upgraded during scheduled power outages in nuclear power generating stations, more and more utilities will be faced with the problem of dealing with Electromagnetic Compatibility (EMC) issues that have evolved with the trend of manufacturers designing equipment based around state-of-the-art high technology logic devices. This paper lists Commonwealth Edison Company (CECO) equipment that was scrutinized by National Technical Systems (NTS) for its EMI impact. The test requirements and test procedures for assessing EMI and EMC are outlined. Although on-site mapping data was gathered to assist CECO for the upgrade described here of the Auxiliary Electric Equipment Room of a Westinghouse Eagle 21 Reactor Protection System at the Zion Unit No.1 Station, blanket mapping of every location for every upgrade is a short term, expensive solution to the EMI problem. It is concluded that the primary problem of lack of system and component level EMI specifications must be addressed by a governing body. 7 refs., 2 figs

Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro's Bruce Nuclear Generating Station 'A'

International Nuclear Information System (INIS)

Day, J.E.; Baker, R.L.

1995-01-01

Ontario Hydro at the Bruce Nuclear Generating Station 'A' has undertaken a program to render the station's liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology

MHD power station with coal gasification

International Nuclear Information System (INIS)

Brzozowski, W.S.; Dul, J.; Pudlik, W.

1976-01-01

A description is given of the proposed operating method of a MHD-power station including a complete coal gasification into lean gas with a simultaneous partial gas production for the use of outside consumers. A comparison with coal gasification methods actually being used and full capabilities of power stations heated with coal-derived gas shows distinct advantages resulting from applying the method of coal gasification with waste heat from MHD generators working within the boundaries of the thermal-electric power station. (author)

Evaluation of the Performance of ClimGen and LARS-WG models in generating rainfall and temperature time series in rainfed research station of Sisab, Northern Khorasan

Directory of Open Access Journals (Sweden)

najmeh khalili

2016-10-01

Full Text Available Introduction:Many existing results on water and agriculture researches require long-term statistical climate data, while practically; the available collected data in synoptic stations are quite short. Therefore, the required daily climate data should be generated based on the limited available data. For this purpose, weather generators can be used to enlarge the data length. Among the common weather generators, two models are more common: LARS-WG and ClimGen. Different studies have shown that these two models have different results in different regions and climates. Therefore, the output results of these two methods should be validated based on the climate and weather conditions of the study region. Materials and Methods:The Sisab station is 35 KM away from Bojnord city in Northern Khorasan. This station was established in 1366 and afterwards, the meteorological data including precipitation data are regularly collected. Geographical coordination of this station is 37º 25׳ N and 57º 38׳ E, and the elevation is 1359 meter. The climate in this region is dry and cold under Emberge and semi-dry under Demarton Methods. In this research, LARG-WG model, version 5.5, and ClimGen model, version 4.4, were used to generate 500 data sample for precipitation and temperature time series. The performance of these two models, were evaluated using RMSE, MAE, and CD over the 30 years collected data and their corresponding generated data. Also, to compare the statistical similarity of the generated data with the collected data, t-student, F, and X2 tests were used. With these tests, the similarity of 16 statistical characteristics of the generated data and the collected data has been investigated in the level of confidence 95%. Results and Discussion:This study showed that LARS-WG model can better generate precipitation data in terms of statistical error criteria. RMSE and MAE for the generated data by LAR-WG were less than ClimGen model while the CD value of

LM5000 gas turbine generating plant for Tenaga Nasional Berhad Sultan Salahuddin Abdul Aziz power station (Malaysia)

Energy Technology Data Exchange (ETDEWEB)

Ishizuka, T.; Shioya, Y.; Furuya, M.; Saito, K. [Ishikawajima-Harima Heavy Indutries Co. Ltd., Tokyo (Japan)

1995-01-01

The LM5000 gas turbine generating plant (35,000 kW) for Tenaga Nasional Berhad Sultan Salahuddin Abdul Aziz Power Station (Malaysia) was outlined. The lightweight power turbine of 16 ton was adopted to reduce an on-site installation time, and integrated into a single package together with the gas generator, while all the auxiliary units were assembled completely before delivery. Because the plant was for peak cut use, the hydraulic starting unit was adopted, in particular, considering starting operation, and the diesel engine generator was provided to drive the unit in complete power failure. The reliability of operation and monitoring was also enhanced by triplicated digital control. The plant output capacity was well beyond the required one during actual operation, and the thermal efficiency of 36.0-36.3% was obtained. Because the power plant was installed in the rainy western part of Malaysia, protective measures of the plant from rain were taken into careful consideration, for example, the air intake port of the air-cooled generator was faced downward, and provided with a condensation eliminator. 4 figs.

the Preliminary Research Based on Seismic Signals Generated by Hutubi Transmitting Seismic Station with One Large-volume Airgun Array

Science.gov (United States)

Wang, Q.; Su, J.; Wei, Y.; Zhang, W.; Wang, H.; Wang, B.; Ji, Z.

2017-12-01

For studying the subsurface structure and its subtle changes, we built the Hutubi transmitting seismic station with one large-volume airgun array at one artificial water pool in the northern segment of Tianshan mountain, where earthquakes occurred frequently. The airgun array consists of six airguns with every airgun capacity of 2000in3, and the artificial water pool with the top diameter of 100m, bottom diameter of 20m and the depth of 18m.We started the regular excitation experiment with the large-volume airgun source every week since June, 2013. Using seismic signals geneated by the Hutubi airgun source, we made the preliminary research on the airgun source, waveform characteristics and the subsurface velocity changes in the northern Tiansh mountain. The results are as follows: The seismic signal exited by the airgun source is characteristic of low-frequency ,and the dominant frequency is in the range of 2 6Hz. The Hutubi transmitting seismic station can continuously generate long-distance detectable and highly repeatable signals, and the correlation coefficient of sigals is greater than 0.95; and the longest propagation distance arrives to 380km, in addition, the 5000-shot stacked sigal using the phase weighted stack technique can be identified in the station, which is about 1300km from the Hutubi transmitting seismic station. Hutubi large-volume airgun source is fitted to detect and monitor the regional-scale subsurface stress state. Applying correlation test method, we measured weak subsurface velocity changes in the northern Tianshan mountain, and found that the several stations, which are within 150km from the the Hutubi transmitting seismic station, appeared 0.1 0.2% relative velocity changes before the Hutubi MS6.2 earthquake on Dec.8, 2016.

Decontamination and disposal of Sb-124 at Palo Verde Nuclear Generating Station

International Nuclear Information System (INIS)

Miller, A.D.; Hillmer, T.P.; Kester, J.W.; Hensch, J.R.

1988-01-01

Palo Verde Nuclear Generating Station (PVNGS) is a three unit Combustion Engineering pressurized water reactor site. Each unit consists of an identical, self contained 1270 MWe reactor. This standardized design allows sharing of design improvements and equipment leading to optimum operation of the individual units. One design improvement, identified early into the operation of Unit 1, involved the elemental antimony content of the seals and bearings within the reactor coolant pumps. Normal wear of these components releases small amounts of elemental antimony. This antimony in turn deposits on in-core surfaces and activates to produce the isotopes Sb-122 and Sb-124. These isotopes emit highly energetic gamma rays which contribute significantly to the exposure and radwaste disposal charges at PVNGS. For these reasons, the Antimony Removal Program was undertaken to remove the radioactive and elemental antimony from the nuclear steam supply system at all three units. The work presented here describes the antimony decontamination and disposal

Review insights on the probabilistic risk assessment for the Limerick Generating Station

International Nuclear Information System (INIS)

1984-08-01

In recognition of the high population density around the Limerick Generating Station site and the proposed power level, the Philadelphia Electric Company, in response to NRC staff requests, conducted and submitted between March 1981 and November 1983 a probabilistic risk assessment (PRA) on internal event contributors and a severe accident risk assessment on external event contributors to assess risks posed by operation of the plant. The applicant has developed perspectives using PRA models on the safety profile of the Limerick plant and has altered the plant design to reduce accident vulnerabilities identified in these PRAs. The staff's review of the Limerick PRA has particularly emphasized the dominant accident sequences and the resulting insights into demonstration of compliance with regulatory requirments, unique design features and major plant vulnerabilities to assess the need for any additional measures to further improve the safety of the LGS. The staff's review insights and PRA safety review conclusions are presented in this report

Technical Analysis of the Hydrogen Energy Station Concept, Phase I and Phase II

Energy Technology Data Exchange (ETDEWEB)

TIAX, LLC

2005-05-04

Phase I Due to the growing interest in establishing a domestic hydrogen infrastructure, several hydrogen fueling stations already have been established around the country as demonstration units. While these stations help build familiarity with hydrogen fuel in their respective communities, hydrogen vehicles are still several years from mass production. This limited number of hydrogen vehicles translates to a limited demand for hydrogen fuel, a significant hurdle for the near-term establishment of commercially viable hydrogen fueling stations. By incorporating a fuel cell and cogeneration system with a hydrogen fueling station, the resulting energy station can compensate for low hydrogen demand by providing both hydrogen dispensing and combined heat and power (CHP) generation. The electrical power generated by the energy station can be fed back into the power grid or a nearby facility, which in turn helps offset station costs. Hydrogen production capacity not used by vehicles can be used to support building heat and power loads. In this way, an energy station can experience greater station utility while more rapidly recovering capital costs, providing an increased market potential relative to a hydrogen fueling station. At an energy station, hydrogen is generated on-site. Part of the hydrogen is used for vehicle refueling and part of the hydrogen is consumed by a fuel cell. As the fuel cell generates electricity and sends it to the power grid, excess heat is reclaimed through a cogeneration system for use in a nearby facility. Both the electrical generation and heat reclamation serve to offset the cost of purchasing the equivalent amount of energy for nearby facilities and the energy station itself. This two-phase project assessed the costs and feasibility of developing a hydrogen vehicle fueling station in conjunction with electricity and cogenerative heat generation for nearby Federal buildings. In order to determine which system configurations and operational

Safety design of next generation SUI of CANDU stations

International Nuclear Information System (INIS)

Nasimi, Elnara; Gabbar, Hossam A.

2013-01-01

Highlights: ► Review of current SUI technologies and challenges. ► Propose a new type of SUI detectors. ► Propose a new SUI system architecture and layout. ► Propose implementation procedure for SUI with reduced risks. - Abstract: Due to the age and operating experience of Nuclear Power Plants, equipment ageing and obsolescence has become one of the main challenges that need to be resolved for all systems, structures and components in order to ensure a safe and reliable production of energy. This paper summarizes the research into a methodology for modernization of Start-Up Instrumentation (SUI), both in-core and Control Room equipment, using a new generation of detectors and cables in order to manage obsolescence. The main objective of this research is to develop a new systematic approach to SUI installation/replacement procedure development and optimization. Although some additional features, such as real-time data monitoring and storage/archiving solutions for SUI systems are also examined to take full advantage of today's digital technology, the objectives of this study do not include detailed parametrical studies of detector or system performance. Instead, a number of technological, operational and maintenance issues associated with Start-Up Instrumentation systems at Nuclear Power Plants (NPPs) will be identified and a structured approach for developing a replacement/installation procedure that can be standardized and used across all of the domestic CANDU (Canadian Deuterium Uranium) stations is proposed.

IEEE Std 317-1972: IEEE standard for electric penetration assemblies in containment structures for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard prescribes the mechanical, electrical, and test requirements for the design, construction, and installation of electric penetration assemblies in containment structures for stationary nuclear power generating stations. The electric conductor and insulation characteristics of external circuits which connect to penetration assemblies are beyond the scope of these criteria. If there should be any conflict between this standard and those documents referenced herein, this standard shall take precedence over the referenced documents

Diagnostic testing and repair of Hollingsworth Generating Station`s Unit One

Energy Technology Data Exchange (ETDEWEB)

Atkins, R.; Epple, W.; Stevenson, D. [Great Lakes Power Ltd., Sault Ste. Marie, ON (Canada); Brotherton, L.; Crahan, M.; Ghate, A.

1995-12-31

A case history of the diagnosis and corrections implemented to resolve vibration problems in a 22,222 kVA hydroelectric generator was presented. The problem prevented the utility from operating the unit throughout the range of its nameplate rating and caused periodic failures of the generator`s guide and thrust bearing. Tests identified that the rim assembly was fastened onto the spider in a manner that resulted in tilting of the rim with respect to the axis of rotation, consequently, there was an unbalanced generator static air gap. A unique repair was implemented to fully restore the rim assembly to its proper position. Problems associated with carrying out such major in-situ repairs in a remote environment and within a scheduled maintenance outage were discussed. Economic benefits and costs associated with the repair were also discussed.

IEEE guide for planning of pre-operational testing programs for class 1E power systems for nuclear-power generating stations

International Nuclear Information System (INIS)

Anon.

1976-01-01

The Institute of Electrical and Electronics Engineers (IEEE) guide for pre-operational testing of Class 1E power systems for nuclear-power generating stations is presented. The guidelines apply to power systems both ac and dc supplies but not to the equipment which utilizes the ac and dc power. The pre-operational tests are performed after appropriate construction tests

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

Nova isolates noise to quieten stations

International Nuclear Information System (INIS)

Milner, G.J.; Frank, L.D.

1993-01-01

This paper reviews a technique developed by Nova Corp., to help isolate and measure the acoustic power of individual components in a pipeline compressor and pumping station. The procedure calculates the sound pressure levels of each piece of equipment independently. Based on these measurements, a prediction can be made of the effect of various types of noise treatment techniques on the overall sound levels currently generated or proposed in a future project. This paper describes the equipment to measure the sound levels, techniques for actually measuring the compressor station or equipment area, and techniques used to generate a remediation plan

Effect of Electromagnetic Waves Generated by Base Transiver Station on Liver Enzymes in Female Rats

Directory of Open Access Journals (Sweden)

Gholam-Ali Jelodar

2013-07-01

Full Text Available Background: This study was investigating the effect of electromagnetic wave generated by mobile and base transceiver station (900 MHz on liver enzymes in both mature and immature female age.Materials and Methods: In this study, 20 rats Sprague Dawley white mature female age 8 to 9 weeks and weight 180 to 200 g and 20 rats immature age 3 to 4 weeks, weight 80 to 100 g, each age group were randomly divided in two groups (control and test. Test groups, were daily for four hours and four different times exposed to electromagnetic waves with signal generator (900 MHz, 5-meter intervals. Control groups were kept at equal condition (themperature and light in laboratory during experiment. After at the end experimental period, blood was collected by heart puncture of all animal. Exposure to EMF generated by BTS had significant effect on liver enzymes composition in mature and immature rats.Results: AST, ALT and ALP in immature-test groups decreased significantly compared with their respective control groups (p<0.05. ALP in mature-test groups increased significantly compared with their respective control groups (p<0.05.Conclusion: These result suggest that exposure to EMF generated by BTS has a deleterious effect on liver enzymes and that this effect is more sever in immature animals.

Power stations

International Nuclear Information System (INIS)

Cawte, H.; Philpott, E.F.

1980-01-01

The object is to provide a method of operating a dual purpose power station so that the steam supply system is operated at a high load factor. The available steam not required for electricity generation is used to provide process heat and the new feature is that the process plant capacity is determined to make the most economic use of the steam supply system, and not to match the passout capacity of the turbine of the turbogenerator. The product of the process plant should, therefore, be capable of being stored. A dual-purpose power station with a nuclear-powered steam source, turbogenerating means connected to the steam source and steam-powered process plant susceptible to wide variation in its rate of operation is described. (U.K.)

Surry Power Station secondary water chemistry improvement since steam generator replacement and the unit two feedwater pipe rupture

International Nuclear Information System (INIS)

Swindell, E.T.

1988-01-01

Surry Power Station has two Westinghouse-designed three-loop PWRs of 811 MWe design rating. The start of commercial operation was in July, 1972 in No.1 plant, and May, 1973 in No.2 plant. Both plants began the operation using controlled phosphate chemistry for the steam generators. In 1975, both plants were converted to all volatile treatment on the secondary side due to the tube wall thinning corrosion in the steam generators, which was associated with the phosphate sludge that was building up on the tube sheets and created acidic condition. Thereafter, condenser and air leakage and steam generator denting occurred, and after the operation of 8 years 2 month of No.1 plant and 5 years 9 months of No.2 plant, the steam generators were replaced. A major plant improvement program was designed and implemented from 1979 to 1980. The improvement in new steam generators, the modification for preventing corrosion, the addition of a steam generator blowdown recovery system, the reconstruction of condensers, the installation of full flow, deep bed condensate polishers, the addition of Dionex 8,000 on-line ion chromatograph, a long term maintenance agreement with Westinghouse and so on are reported. (Kako, I.)

78 FR 77726 - Exelon Generation Company, LLC Three Mile Island Nuclear Station, Unit 1

Science.gov (United States)

2013-12-24

... Three Mile Island Nuclear Station, Unit 1 AGENCY: Nuclear Regulatory Commission. ACTION: Exemption... License No. DPR-50, which authorizes operation of the Three Mile Island Nuclear Station, Unit 1 (TMI-1... Facility Operating License No. DPR-50, which authorizes operation of the Three Mile Island Nuclear Station...

Examination of failed studs from No. 2 steam generator at the Maine Yankee Nuclear Power Station

International Nuclear Information System (INIS)

Czajkowski, C.

1983-02-01

Three studs removed from service on the primary manway cover from steam generator No. 2 of the Maine Yankee station were sent to Brookhaven National Laboratory (BNL) for examination. The examination consisted of visual/dye penetrant examination, optical metallography and Scanning Electron Microscopy/Energy Dispersive Spectroscopy (SEM/EDS) evaluation. One bolt was through cracked and its fracture face was generally transgranular in nature with numerous secondary intergranular cracks. The report concludes that the environmenally assisted cracking of the stud was due to the interaction of the various lubricants used with steam leaks associated with this manway cover

Merchant funding for power stations

International Nuclear Information System (INIS)

Johnston, B.; Bartlam, M.

1997-01-01

The next frontier for project finance is merchant generation: the financing of IPPs without long-term offtake contracts. Banks are just beginning to finance merchant generation power stations. One of the first was Destec's Indian Queens project in Cornwall, UK. Bruce Johnston and Martin Bartlam of Wilde Sapte discuss the project. (UK)

Dam safety at Seven Sisters Generating Station

International Nuclear Information System (INIS)

Carson, R. W.; Gupta, R. C.

1996-01-01

A safety surveillance program for all hydraulic structures in Manitoba was first implemented in 1979, and updated in 1988. This contribution describes the current status of the program, and the nature of the issues that the program was designed to address. The Seven Sisters Station's dam on the Winnipeg River, about 90 km northeast of the City of Winnipeg, was used as an example. Extensive reviews of flood risks and downstream inundation potential at Seven Sisters' revealed a number of deficiencies; these findings will be incorporated into a corporate plan of overall remediation. Updating the program will also include efforts to ensure adherence to national dam safety guidelines. 5 figs

Shippingport Station Decommissioning Project

International Nuclear Information System (INIS)

McKernan, M.L.

1989-01-01

The Shippingport Atomic Power Station was located on the Ohio River in Shippingport Borough (Beaver County), Pennsylvania, USA. The US Atomic Energy Commission (AEC) constructed the plant in the mid-1950s on a seven and half acre parcel of land leased from Duquesne Light Company (DLC). The purposes were to demonstrate and to develop Pressurized Water Recovery technology and to generate electricity. DLC operated the Shippingport plant under supervision of (the successor to AEC) the Department of Energy (DOE)-Naval Reactors (NR) until operations were terminated on October 1, 1982. NR concluded end-of-life testing and defueling in 1984 and transferred the Station's responsibility to DOE Richland Operations Office (RL), Surplus Facility Management Program Office (SFMPO5) on September 5, 1984. SFMPO subsequently established the Shippingport Station Decommissioning Project and selected General Electric (GE) as the Decommissioning Operations Contractor. This report is intended to provide an overview of the Shippingport Station Decommissioning Project

Monitoring the risk of loss of heat sink during plant shutdowns at Bruce Generating Station 'A'

International Nuclear Information System (INIS)

Krishnan, K.S.; Mancuso, F.; Vecchiarelli, D.

1996-01-01

A relatively simple loss of shutdown heat sink fault tree model has been developed and used during unit outages at Bruce Nuclear Generation Station 'A' to assess, from a risk and reliability perspective, alternative heat sink strategies and to aid in decisions on allowable outage configurations. The model is adjusted to reflect the various unit configurations planned during a specific outage, and identifies events and event combinations leading to loss of fuel cooling. The calculated failure frequencies are compared to the limits consistent with corporate and international public safety goals. The importance measures generated by the interrogation of the fault tree model for each outage configuration are also used to reschedule configurations with high fuel damage frequency later into the outage and to control the configurations with relatively high probability of fuel damage to short intervals at the most appropriate time into the outage. (author)

Control room inleakage testing using tracer gases at Zion Generating station

International Nuclear Information System (INIS)

Lagus, P.L.; Brown, J.H.; Dubois, L.J.; Fleming, K.M.

1993-01-01

In order to assess the amount of air inleakage into the Control Room Envelope at Zion Generating Station (ZGS), a series of tracer gas tests using sulfur hexafluoride (SF 6 ) were performed on the Control Room ventilation system (PV system) and the Computer Room/Miscellaneous Area ventilation system (OV system) during February, 1991. Two redundant trains, denoted A and B comprise the PV system. Inleakage was measured for each train. An OV supply duct passes through the Control Room Envelope. Leakage from this duct into the Control Room would constitute air leakage into the Control room Envelope and hence any potential leakage had to be quantified. Each test attempted to measure the contribution (if any) of a particular section of PV return duct or OV supply duct to the total air inleakage into the Control Room. This paper reviews the tracer gas tests. Described here are the control room inleakage testing, HVAC equipment room duct inleakage, purge plenum inleakage, OV duct leakage into the control room envelope, vestibule PV return inleakage, TSC duct inleakage, and cable spreading room inleakage. Conclusions from the testing are presented. 5 refs., 4 figs., 7 tabs

Design and verification of computer-based reactor control system modification at Bruce-A candu nuclear generating station

International Nuclear Information System (INIS)

Basu, S.; Webb, N.

1995-01-01

The Reactor Control System at Bruce-A Nuclear Generating Station is going through some design modifications, which involve a rigorous design process including independent verification and validation. The design modification includes changes to the control logic, alarms and annunciation, hardware and software. The design (and verification) process includes design plan, design requirements, hardware and software specifications, hardware and software design, testing, technical review, safety evaluation, reliability analysis, failure mode and effect analysis, environmental qualification, seismic qualification, software quality assurance, system validation, documentation update, configuration management, and final acceptance. (7 figs.)

Zircon U-Pb age, Lu-Hf isotope, mineral chemistry and geochemistry of Sundamalai peralkaline pluton from the Salem Block, southern India: Implications for Cryogenian adakite-like magmatism in an aborted-rift

Science.gov (United States)

Renjith, M. L.; Santosh, M.; Li, Tang; Satyanarayanan, M.; Korakoppa, M. M.; Tsunogae, T.; Subba Rao, D. V.; Kesav Krishna, A.; Nirmal Charan, S.

2016-01-01

The Sundamalai peralkaline pluton is one among the Cryogenian alkaline plutons occurring in the Dharmapuri Rift Zone (DRZ) of the Salem Block in the Southern Granulite Terrane (SGT) of India. Here we present zircon U-Pb age and Lu-Hf isotopic composition, mineral chemistry and geochemistry of the pluton to explore the petrogenesis and geodynamic implications. Systematic modal variation of orthoclase, Na-plagioclase, Ca-amphibole (ferro-edenite and hastingsite) and quartz developed quartz-monzonite and granite litho units in the Sundamalai pluton. Thermometry based on amphibole-plagioclase pair suggests that the pluton was emplaced and solidified at around 4.6 kbar pressure with crystallization of the major phases between 748 and 661 °C. Estimated saturation temperature of zircon (712-698 °C) is also well within this range. However, apatite saturation occurred at higher temperatures between 835 and 870 °C, in contrast with monazite saturation (718-613 °C) that continued up to the late stage of crystallization. Estimated oxygen fugacity values (log fO2: -14 to -17) indicate high oxidation state for the magma that stabilized titanite and magnetite. The magmatic zircons from Sundamalai pluton yielded a weighted mean 206Pb/238U age of 832.6 ± 3.2 Ma. Geochemically, the Sundamalai rocks are high-K to shoshonitic, persodic (Na2O/K2O ratio > 1), silica-saturated (SiO2:65-72 wt.%), and peralkaline in composition (aluminum saturation index, ASI Sc(2-3 ppm), positive Sr anomaly and predominantly negative zircon εHf(t) values (-10.8 to -9.3 with an average of -10.2) and initial 176Hf/177Hf ratios (0.281947-0.282022) confirm a Paleoproterozoic crustal source. Based on the field and geochemical evidences, we propose that a previously metasomatized mafic lower-crustal source enriched in alkalis has undergone CO2-present partial melting as a result of asthenospheric upwelling beneath an aborted rifting along the DRZ generating the magma that crystallized the Sundamalai rocks

Development situation about the Canadian CANDU Nuclear Power Generating Stations

Energy Technology Data Exchange (ETDEWEB)

Jeon, Yu Mi; Kim, Yong Hee; Park, Joo Hwan

2009-07-15

The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century.

Development situation about the Canadian CANDU Nuclear Power Generating Stations

International Nuclear Information System (INIS)

Jeon, Yu Mi; Kim, Yong Hee; Park, Joo Hwan

2009-07-01

The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century

IEEE Std 600: IEEE trial-use standard requirements for organizations that conduct qualification testing of safety systems equipment for use in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

The purpose of this standard is to provide requirements for establishing a program for conducting qualification tests of safety systems equipment used in nuclear power generating stations. Compliance with the requirements of this standard does not assure the adequacy of the qualification tests performed. This standard applies to organizations that conduct qualification tests on equipment that has a definable safety function and is an identifiable part of a safety system for use in nuclear power generating stations. It requires a technical program, a quality assurance program, and a demonstrated ability to meet specified technical requirements. It does not apply to materials tests, production tests, normal performance testing, qualification by analysis, qualification by operating experience, or reliability tests such as diesel-generator multiple start tests. The intent of this standard is to achieve greater consistency, reliability, and reproducibility of test results and to provide adequate control of qualification testing of safety systems equipment

Rf Station For Ion Beam Staking In Hirfl-csr

CERN Document Server

Arbuzov, V S; Bushuev, A A; Dranichnikov, A N; Gorniker, E I; Kendjebulatov, E K; Kondakov, A A; Kondaurov, M; Kruchkov, Ya G; Krutikhin, S A; Kurkin, G Ya; Mironenko, L A; Motygin, S V; Osipov, V N; Petrov, V M; Pilan, Andrey M; Popov, A M; Rashenko, V V; Selivanov, A N; Shteinke, A R; Vajenin, N F

2004-01-01

BINP has developed and produced the RF station for Institute of Modern Physics (IMP), Lanzhou, China, for multipurpose accelerator complex with electron cooling. The RF station will be used for accumulation of ion beams in the main ring of the system. It was successfully tested in IMP and installed into the main accelerator ring of the complex. The RF station includes accelerating RF cavity and RF power generator with power supplies. The station works within frequency range 6.0 - 14.0 MHz, maximum voltage across the accelerating gap of the RF cavity - 20 kV. In the RF cavity the 200 VNP ferrite is utilized. A residual gas pressure in vacuum chamber does not exceed 2,5E-11 mbar. Maximum output power of the RF generator 25 kW. The data acquisition and control of the RF station is based on COMPACT - PCI bus and provides all functions of monitoring and control.

Technical evaluation of RETS-required reports for Rancho Seco Nuclear Generating Station, Unit 1 for 1983

International Nuclear Information System (INIS)

Magleby, E.H.; Young, T.E.

1985-01-01

A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Rancho Seco Nuclear Generating Station, Unit 1 were the Semiannual Effluent Release Report, January 1, 1983 to June 30, 1983 and the Radiation Exposure, Environmental Protection, Effluent and Waste Disposal Report. The principal review guidelines were the plant's specific RETS which were based on NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

Using the International Space Station (ISS) Oxygen Generation Assembly (OGA) Is Not Feasible for Mars Transit

Science.gov (United States)

Jones, Harry W.

2016-01-01

A review of two papers on improving the International Space Station (ISS) Oxygen Generation Assembly (OGA) shows that it would not save substantial mass on a Mars transit. The ISS OGA requires redesign for satisfactory operation, even for the ISS. The planned improvements of the OGA for ISS would not be sufficient to make it suitable for Mars, because Mars transit life support has significantly different requirements than ISS. The OGA for Mars should have lower mass, better reliability and maintainability, greater safety, radiation hardening, and capability for quiescent operation. NASA's methodical, disciplined systems engineering process should be used to develop the appropriate system.

Investigations of the gas-side heat transfer and flow characteristics of steam generators in AGR stations

Energy Technology Data Exchange (ETDEWEB)

Lis, J [Central Electricity Research Laboratories, Leatherhead, Surrey (United Kingdom)

1984-07-01

This paper describes the experimental and analytical investigations of the gas-side heat transfer and flow characteristics of steam generators in the AGR stations carried out by CERL. The majority of the experimental work on heat transfer and flow characteristics of close-packed tube arrangements in cross-flow of gases is carried out in a pressurised heat exchanger rig. The rig is operated on-line by a dedicated PDP 11/40 computer over the range of Reynolds number 10{sup 4} to 3x10{sup 5}. Atmospheric wind tunnels employing either small or large scale models of the specific sections of steam generators are used for a variety of supplementary and development studies. Various measurements techniques and, in particular, LDA and hot wire anemometry employed in these studies are described. The more important aspects of various investigations are illustrated by typical results. In order to ensure the efficient operation and integrity of steam generators under asymmetric boundary conditions a MIX suite of 2-dimensional codes has been developed. The codes calculate the gas and water/steam flow and temperature distributions in each channel of the steam generator taking into account thermal mixing in the gas as it passes through the generator. Application of the MIX codes to the solution of various operational problems is illustrated by typical examples and the continuing exercise of validating the codes against plant operational data is discussed. (author)

Investigations of the gas-side heat transfer and flow characteristics of steam generators in AGR stations

International Nuclear Information System (INIS)

Lis, J.

1984-01-01

This paper describes the experimental and analytical investigations of the gas-side heat transfer and flow characteristics of steam generators in the AGR stations carried out by CERL. The majority of the experimental work on heat transfer and flow characteristics of close-packed tube arrangements in cross-flow of gases is carried out in a pressurised heat exchanger rig. The rig is operated on-line by a dedicated PDP 11/40 computer over the range of Reynolds number 10 4 to 3x10 5 . Atmospheric wind tunnels employing either small or large scale models of the specific sections of steam generators are used for a variety of supplementary and development studies. Various measurements techniques and, in particular, LDA and hot wire anemometry employed in these studies are described. The more important aspects of various investigations are illustrated by typical results. In order to ensure the efficient operation and integrity of steam generators under asymmetric boundary conditions a MIX suite of 2-dimensional codes has been developed. The codes calculate the gas and water/steam flow and temperature distributions in each channel of the steam generator taking into account thermal mixing in the gas as it passes through the generator. Application of the MIX codes to the solution of various operational problems is illustrated by typical examples and the continuing exercise of validating the codes against plant operational data is discussed. (author)

Studying dynamics of indicators of nuclear power stations exploitation (the case of US nuclear power stations)

OpenAIRE

Varshavsky, Leonid

2013-01-01

Analysis of external and internal factors influencing significant improvement of economic indicators of US nuclear power stations in the 1990s is carried out. Approaches to modeling dynamics of capacity factors of nuclear power stations are proposed. Comparative analysis of dynamics of capacity factors and occupational radiation exposure for various generations of US nuclear power plants is carried out. Dynamical characteristics of «learning by doing» effects for analyzed indicators are measu...

Complex Mobile Independent Power Station for Urban Areas

Science.gov (United States)

Tunik, A. A.; Tolstoy, M. Y.

2017-11-01

A new type of a complex mobile independent power station developed in the Department of Engineering Communications and Life-Support Systems of Irkutsk National Research Technical University, is presented in this article. This station contains only solar panel, wind turbine, accumulator, diesel generator and microbial fuel cell for to produce electric energy, heat pump and solar collector to generate heat energy and also wastewater treatment plant and new complex control system. The complex mobile independent power station is intended for full power supply of a different kind of consumers located even in remote areas thus reducing their dependence from centralized energy supply systems, decrease the fossil fuel consumption, improve the environment of urban areas and solve the problems of the purification of industrial and municipal wastewater.

The next nuclear power station generation: Beyond-design accident concepts, methods, and action sequence

International Nuclear Information System (INIS)

Asmolov, V.G.; Khakh, O.Ya.; Shashkov, M.G.

1993-01-01

The problem of beyond-design accidents at nuclear stations will not be solved unless a safety culture becomes a basic characteristic of all lines of activity. Only then can the danger of accidents as an objective feature of nuclear stations be eliminated by purposive skilled and responsible activities of those implementing safety. Nuclear-station safety is provided by the following interacting and complementary lines of activity: (1) the design and construction of nuclear stations by properly qualified design and building organizations; (2) monitoring and supervision of safety by special state bodies; (3) control of the station by the exploiting organization; and (4) scientific examination of safety within the above framework and by independent organizations. The distribution of the responsibilities, powers, and right in these lines should be defined by a law on atomic energy, but there is not such law in Russian. The beyond-design accident problem is a key one in nuclear station safety, as it clear from the serious experience with accidents and numerous probabilistic studies. There are four features of the state of this topic in Russia that are of major significance for managing accidents: the lack of an atomic energy law, the inadequacy of the technical standards, the lack of a verified program package for nuclear-station designs in order to calculate the beyond-design accidents and analyze risks, and a lack of approach by designers to such accidents on the basis of international recommendations. This paper gives a brief description of three-forming points in the scientific activity: the general concept of nuclear-station safety, methods of analyzing and providing accident management, and the sequence of actions developed by specialists at this institute in recent years

Local society and nuclear power stations

International Nuclear Information System (INIS)

1984-02-01

This report was made by the expert committee on region investigation, Japan Atomic Industrial Forum Inc., in fiscal years 1981 and 1982 in order to grasp the social economic influence exerted on regions by the location of nuclear power stations and the actual state of the change due to it, and to search for the way the promotion of local community should be. The influence and the effect were measured in the regions around the Fukushima No. 1 Nuclear Power Station of Tokyo Electric Power Co., Inc., the Mihama Power Station of Kansai Electric Power Co., Inc., and the Genkai Nuclear Power Station of Kyushu Electric Power Co., Inc. The fundamental recognition in this discussion, the policy of locating nuclear power stations and the management of regions, the viewpoint and way of thinking in the investigation of the regions where nuclear power stations are located, the actual state of social economic impact due to the location of nuclear power stations, the connected mechanism accompanying the location of nuclear power stations, and the location of nuclear power stations and the acceleration of planning for regional promotion are reported. In order to economically generate electric power, the rationalization in the location of nuclear power stations is necessary, and the concrete concept of building up local community must be decided. (Kako, I.)

Aging management program of the reactor building concrete at Point Lepreau Generating Station

Science.gov (United States)

Aldea, C.-M.; Shenton, B.; Demerchant, M. M.; Gendron, T.

2011-04-01

In order for New Brunswick Power Nuclear (NBPN) to control the risks of degradation of the concrete reactor building at the Point Lepreau Generating Station (PLGS) the development of an aging management plan (AMP) was initiated. The intention of this plan was to determine the requirements for specific structural components of concrete of the reactor building that require regular inspection and maintenance to ensure the safe and reliable operation of the plant. The document is currently in draft form and presents an integrated methodology for the application of an AMP for the concrete of the reactor building. The current AMP addresses the reactor building structure and various components, such as joint sealant and liners that are integral to the structure. It does not include internal components housed within the structure. This paper provides background information regarding the document developed and the strategy developed to manage potential degradation of the concrete of the reactor building, as well as specific programs and preventive and corrective maintenance activities initiated.

Eco-technology service station: the future of gas station; Posto eco-tecnologico: o posto do futuro

Energy Technology Data Exchange (ETDEWEB)

Moura, Newton R. [PETROBRAS, Rio de Janeiro, RJ (Brazil); Daher, Humberto Antonio S. [PETROBRAS Distribuidora, Rio de Janeiro, RJ (Brazil)

2004-07-01

PETROBRAS Distribuidora and CENPES have a project to build an eco-technology service station at Ilha do Fundao, to know new technologies for vehicle fuelling, test of new vehicle natural gas compression system, and start projects with new fuels that are not available at Brazilian market. This service station concept shall be aligned with sustainability premise that are being established for both companies, that means, besides a technology focus, it shall have a social focus without any environment damage. PETROBRAS 'Board of Directors approved the expansion of PETROBRAS' Research and Development Center (CENPES) installations, including this service station construction. Some activities that will be developed at the service station are pointed out here: available of new natural gas compression system; micro-generation with micro turbine, fuel cell; and photo-voltaic cell technologies; hydrogen fuelling; oil-water system treatment; biodiesel fuelling. This station will have a show room opened to the public, with panels, videos and a CNG compressor in cut. (author)

Final environmental statement related to the operation of Limerick Generating Station, Units 1 and 2, Docket Nos. 50-352 and 50-353, Philadelphia Electric Company

International Nuclear Information System (INIS)

1989-08-01

In April 1984 the staff of the Nuclear Regulatory Commission issued its Final Environmental Statement (NUREG-0974) related to the operation of Limerick Generating Station, Units 1 and 2, (Docket Nos. 50-352 and 50-353), located on the Schuylkill River, near Pottstown, in Limerick Township, Montgomery and Chester Counties, Pennsylvania. The NRC has prepared this supplement to NUREG-0974 to present its evaluation of the alternative of facility operation with the installation of further severe accident mitigation design features. The NRC staff has discovered no substantial changes in the proposed action as previously evaluated in the Final Environmental Statement that are relevant to environmental concerns nor significant new circumstances or information relevant to environmental concerns and bearing on the licensing of Limerick Generating Station, Units 1 and 2. 15 refs., 10 tabs

Distributed power generation using microturbines

CSIR Research Space (South Africa)

Szewczuk, S

2008-11-01

Full Text Available At present, the bulk of the world is electricity is generated in central power stations. This approach, one of `economy of size generates electricity in large power stations and delivers it to load centres via an extensive network of transmission...

CSN's New Emergency Room

International Nuclear Information System (INIS)

Sendin, P.

2005-01-01

During the month of July 2005 the physical renovation works and technological updating of the basic infrastructures of the CSN Emergency Room (SALEM) were finished, allowing the Room to now have greater functionality and a broader technical capacity. Nevertheless, the technological improvement process of SALEM will reach its full potential within the next few years, once the installation currently underway of the new information integration and monitoring systems and the decision making support systems have been completed. This article describes the improvements introduced to the Room and the objectives pursued in this renovation project to convert the SALEM into a new generation room in accordance with its current technological context. (Author) 4 refs

Optimization of station battery replacement

International Nuclear Information System (INIS)

Jancauskas, J.R.; Shook, D.A.

1994-01-01

During a loss of ac power at a nuclear generating station (including diesel generators), batteries provide the source of power which is required to operate safety-related components. Because traditional lead-acid batteries have a qualified life of 20 years, the batteries must be replaced a minimum of once during a station's lifetime, twice if license extension is pursued, and more often depending on actual in-service dates and the results of surveillance tests. Replacement of batteries often occurs prior to 20 years as a result of systems changes caused by factors such as Station Blackout Regulations, control system upgrades, incremental load growth, and changes in the operating times of existing equipment. Many of these replacement decisions are based on the predictive capabilities of manual design basis calculations. The inherent conservatism of manual calculations may result in battery replacements occurring before actually required. Computerized analysis of batteries can aid in optimizing the timing of replacements as well as in interpreting service test data. Computerized analysis also provides large benefits in maintaining the as-configured load profile and corresponding design margins, while also providing the capability of quickly analyze proposed modifications and response to internal and external audits

75 FR 36700 - Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Unit 1; Environmental...

Science.gov (United States)

2010-06-28

...; Three Mile Island Nuclear Station, Unit 1; Environmental Assessment and Finding of No Significant Impact... Company, LLC (the licensee), for operation of Three Mile Island Nuclear Station, Unit 1 (TMI-1), located... Three Mile Island Nuclear Station, Units 1 and 2, NUREG-0552, dated December 1972, and Generic...

Projected costs of generating electricity from nuclear and coal-fired power stations for commissioning in 1995

International Nuclear Information System (INIS)

1986-01-01

This report updates and extends the previous NEA study, ''The Costs of Generating Electricity in Nuclear and Coal-fired Power Stations'', published by the OECD in late 1983. Despite the changed expectations concerning coal prices and the considerable movements in exchange rates since the first study was completed, the conclusions remain essentially the same. Nuclear Power is projected to be economically superior by a significant margin to coal-fired plants for base load electricity production in Europe, Japan and some regions of North America. In areas of North America in close proximity to supplies of cheap coal, this would be the more economic fuel, unless future nuclear investment costs can be reduced to match the best US and Canadian experience. In all regions considered, the economic advantage of both coal and nuclear over oil and gas-fired plants for commissioning in the mid-1990s is expected to be substantial. These conclusions are based on an analysis of cost projections for 900 MWe to 1400 MWe Light Water Reactors to be commissioned in 1995, operating at a levelised load factor of about 72 per cent over an assumed 25 years economic life and calculated with a 5 per cent (real) discount rate. This parallels the reference reactor selected for the NEA report ''The Economics of the Nuclear Fuel Cycle'', which was published by the OECD in June 1985, though it deviates somewhat from the reference conditions of the previous generation cost study. Contemporary coal-fired stations ranging in capacity from 330 MWe to 700 MWe with the same assumed economic life and load factor provide the basis for comparison. Some data are included on CANDU Pressurised Heavy Water Reactors, and a brief comment is annexed on the relevance of the comparisons for the smaller plants that may be of interest to countries with smaller electricity networks or where special circumstances apply

Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario hydro's Bruce nuclear generating station open-quotes Aclose quotes

International Nuclear Information System (INIS)

Day, J.E.; Baker, R.L.

1994-01-01

Ontario Hydro at the Bruce Nuclear Generating Station open-quotes Aclose quotes has undertaken a program to render the station's liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology

External gamma radiation monitoring in the environs of Kaiga Generating Station (KGS), using thermoluminescent dosimeters, during the period 1989-2003

International Nuclear Information System (INIS)

Basu, A.S.; Chougaonkar, M.P.; Mayya, Y.S.; Puranik, V.D.; Reji, T.K.; Ravi, P.M.; Hegde, A.G.

2005-05-01

This publication reports the results of external gamma radiation monitoring using Thermoluminescent Dosimeters (TLDs), in the environs of Kaiga Generating Station (KGS) during its preoperational survey between October 1989 and June 1998. The report also presents quarterly and annual values of air dose during the operational phase of the station between July 1998 and Dec. 2003 around the environmcnt of KGS. The results of TLD analysis, during the period October 1989-June 1998, indicate that the average annual air dose for the locations monitored, was 502± 91 μGy/a. The general background of the environs around Kaiga during the operational period, i.e. July 1998 and Dec. 2003, between 2.3 km. to 32km. has been found to be 509±74 μGy/a. The report discusses the methodology and different analyses carried out. (author)

Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report

Energy Technology Data Exchange (ETDEWEB)

Hebdon, F.J. [Institute of Nuclear Power Operations, Atlanta, GA (United States)

1993-03-01

On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility`s actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities.

A Data Management System for International Space Station Simulation Tools

Science.gov (United States)

Betts, Bradley J.; DelMundo, Rommel; Elcott, Sharif; McIntosh, Dawn; Niehaus, Brian; Papasin, Richard; Mah, Robert W.; Clancy, Daniel (Technical Monitor)

2002-01-01

Groups associated with the design, operational, and training aspects of the International Space Station make extensive use of modeling and simulation tools. Users of these tools often need to access and manipulate large quantities of data associated with the station, ranging from design documents to wiring diagrams. Retrieving and manipulating this data directly within the simulation and modeling environment can provide substantial benefit to users. An approach for providing these kinds of data management services, including a database schema and class structure, is presented. Implementation details are also provided as a data management system is integrated into the Intelligent Virtual Station, a modeling and simulation tool developed by the NASA Ames Smart Systems Research Laboratory. One use of the Intelligent Virtual Station is generating station-related training procedures in a virtual environment, The data management component allows users to quickly and easily retrieve information related to objects on the station, enhancing their ability to generate accurate procedures. Users can associate new information with objects and have that information stored in a database.

Water electrolysis plants for hydrogen and oxygen production. Shipped to Tsuruga Power Station Unit No.1, and Tokai No.2 power station, the Japan Atomic Power Co

International Nuclear Information System (INIS)

Ueno, Syuichi; Sato, Takao; Ishikawa, Nobuhide

1997-01-01

Ebara's water electrolysis plants have been shipped to Tsuruga Power Station Unit No.1, (H 2 generation rate: 11 Nm 3 /h), and Tokai No.2 Power Station (H 2 generation rate: 36 Nm 3 /h), Japan Atomic Power Co. An outcome of a business agreement between Nissho Iwai Corporation and Norsk Hydro Electrolysers (Norway), this was the first time that such water electrolysis plants were equipped in Japanese boiling water reactor power stations. Each plant included an electrolyser (for generating hydrogen and oxygen), an electric power supply, a gas compression system, a dehumidifier system, an instrumentation and control system, and an auxiliary system. The plant has been operating almost continuously, with excellent feedback, since March 1997. (author)

Communication Base Station Log Analysis Based on Hierarchical Clustering

Directory of Open Access Journals (Sweden)

Zhang Shao-Hua

2017-01-01

Full Text Available Communication base stations generate massive data every day, these base station logs play an important value in mining of the business circles. This paper use data mining technology and hierarchical clustering algorithm to group the scope of business circle for the base station by recording the data of these base stations.Through analyzing the data of different business circle based on feature extraction and comparing different business circle category characteristics, which can choose a suitable area for operators of commercial marketing.

IEEE Std 535-1986: IEEE standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 308-1980 can be demonstrated by using the procedures provided in this standard in accordance with ANSI/IEEE Std 323-1983. Battery sizing, maintenance, capacity testing, installation, charging equipment, and consideration of other type batteries are beyond the scope of this standard

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Wilson, A.

1982-11-01

The methods of establishing construction time, capital cost, availability and lifetime of different types of generating plant are described. In volume one assessments are presented for a new coal fired station, for a new AGR station and for a new PWR station - Sizewell B. Volume two, contains all diagrams, tables and appendices presented as evidence. (U.K.)

Status of thermal power generation in India-Perspectives on capacity, generation and carbon dioxide emissions

International Nuclear Information System (INIS)

Ghosh, Subhodip

2010-01-01

India's reliance on fossil-fuel based electricity generation has aggravated the problem of high carbon dioxide (CO 2 ) emissions from combustion of fossil fuels, primarily coal, in the country's energy sector. The objective of this paper is to analyze thermal power generation in India for a four-year period and determine the net generation from thermal power stations and the total and specific CO 2 emissions. The installed generating capacity, net generation and CO 2 emissions figures for the plants have been compared and large generators, large emitters, fuel types and also plant vintage have been identified. Specific emissions and dates of commissioning of plants have been taken into account for assessing whether specific plants need to be modernized. The focus is to find out areas and stations which are contributing more to the total emissions from all thermal power generating stations in the country and identify the overall trends that are emerging.

A novel feedwater system for the RETRAN model of the Palo Verde nuclear generating station

International Nuclear Information System (INIS)

Secker, P.A.; Webb, J.R.

1988-01-01

This paper presents a feedwater system model which supplies realistic boundary conditions to the RETRAN model of a Palo Verde Nuclear Generating Station reactor plant. The RETRAN thermal hydraulic code is used to analyze nuclear reactor system transients through a generalized thermal hydraulic volume/junction network. The feedwater system model is implemented using the control block modeling option available in the RETRAN code. The output of the control block model is coupled to the thermal hydraulic network by a fill junction. A forward Euler integration scheme is used by RETRAN for control block variables. The feedwater system model is formulated to allow implicit integration within the existing code framework. The potential need for small integration time steps is, therefore, alleviated. The model results are compared with test data

75 FR 30364 - Mt. Hood and Willamette National Forests, Oregon; Cascade Crossing Transmission Project

Science.gov (United States)

2010-06-01

... stations associated with the ``smart'' grid communication system, and permanent roads which would be used.... Wednesday, June 23 4-7 p.m Oregon City, Oregon City High School, 19761 S. Beavercreek Rd. Thursday, June 24 4-7 p.m Salem, McKay High School, 2440 Lancaster Dr., NE. Tuesday, June 29 4-7 p.m Mill City, Mill...

The expected environmental consequences and hazards of laser-fusion electric generating stations

International Nuclear Information System (INIS)

Devaney, J.J.; Pendergrass, J.H.

The operation of an expected early form of a laser-fusion electric power plant is described and the hazards and the environmental effects of such a station are estimated. Possible environmental impacts and hazards to mankind can occur from nuclear excursions or explosions, nuclear weapon proliferation, loss of coolant accident (LOCA), tritium releases, chemical fires and accompanying releases of radioactivity or chemicals, induced radioactivity releases (other than tritium), radioactive waste disposal, lasers, normal electrical generation and steam plant effects, external intrusions, natural disasters, land use, resource and transportation use, thermal pollution, and air and water pollution. We find the principle environmental effects to be those of a medium size chemical plant. Electric, magnetic, steam, and radioactive hazards are of a lower order. Indeed in the event of extraordinary success in getting high temperatures and densities so that more difficult nuclear species can be reacted, such as protons with boron-11, there will be no radioactivity at all and also enormously lower hazardous chemical inventories. In our plant designs, for any fusion fuels, nuclear explosions (or even excursions beyond design limits) are not possible. (author)

Solidifying power station resins and sludges

International Nuclear Information System (INIS)

Willis, A.S.D.; Haigh, C.P.

1984-01-01

Radioactive ion exchange resins and sludges arise at nuclear power stations from various operations associated with effluent treatment and liquid waste management. As the result of an intensive development programme, the Central Electricity Generating Board (CEGB) has designed a process to convert power station resins and sludges into a shielded, packaged solid monolithic form suitable for final disposal. Research and development, the generic CEGB sludge/resin conditioning plant and the CEGB Active Waste Project are described. (U.K.)

The vibrational behaviour of the generator support structure for Koeberg nuclear power station at high frequencies

International Nuclear Information System (INIS)

Lee, D.E.

1988-06-01

The vibrational behaviour of the generator support structure at Koeberg nuclear power station at frequencies primarily in the region of 80 Hz to 110 Hz was examined. The effect of soil-structure interaction and the change in stiffness of the foundation soil was investigated. Vibration tests were performed on the generator support structure and the results were compared with a theoretical finite element analysis of the structure. By varying the soil-cement foundation stiffness it was possible to demonstrate the change in dynamic behaviour of the structure in the higher frequency band 80 Hz to 110 Hz. Comment has been made on the design code DIN 4024 in view of the findings of this thesis. It was concluded that the empirical rules regarding the inclusion of the foundation in an analysis specified by the code do not cover all cases and greater cognisance of the effect of the foundation stiffness on the vibration behaviour of such machine foundations is necessary. Obvious machine frequencies higher than the operational frequencies should be analysed where it is considered necessary. 24 refs., 25 tabs., 83 figs

Periodical inspection in nuclear power stations

International Nuclear Information System (INIS)

1986-01-01

Periodical inspection is presently being made of eight nuclear power plants in nuclear power stations. Up to the present time, in three of them, failures as follows have been observed. (1) Unit 3 (PWR) of the Mihama Power Station in The Kansai Electric Power Co., Inc. Nineteen heat-transfer tubes of the steam generators were plugged up due to failure. A fuel assembly with a failed spring fixture and in another the control-rod cluster with a failed control rod fixture were replaced. (2) Unit 2 (PWR) of the Oi Power Station in The Kansai Electric Power Co., Inc. Eight heat-transfer tubes of the heat exchangers were plugged up due to failure. (3) Unit 6 (BWR) of the Fukushima Nuclear Power Station I in The Tokyo Electric Power Co., Inc. A fuel assembly with leakage was replaced. (Mori, K.)

NURE aerial gamma-ray and magnetic reconnaissance survey: Blue Ridge area, Greensboro NJ 17-12, Winston-Salem NJ 17-11, and Johnson City NJ 17-10 Quadrangles. Volume I. Narrative report

International Nuclear Information System (INIS)

1978-12-01

As part of the Department of Energy (DOE) National Uranium Resource Evaluation (NURE) Program, LKB Resources, Inc. has performed a rotary-wing, reconnaissance high sensitivity radiometric and magnetic survey in the Blue Ridge area of Virginia, North Carolina, South Carolina, Kentucky, and Tennessee. Five (5) 1:250,000 scale NTMS quadrangles (Greensboro, Winston-Salem, Johnson City, Knoxville, and Charlotte) were surveyed. A total of 15,753 line miles (25,347 kilometers) of data were collected utilizing a Sikorsky S58 and S58T helicopter. Traverse lines were flown in an east-west direction at 3.0 mile (4.8 kilometer) spacing, with tie lines flown in a north-south direction at 12 mile (20 kilometer) spacing. The data were digitally recorded at 1.0 second intervals. The NaI terrestrial detectors used in this survey had a total volume of 2,154 cubic inches. The magnetometer employed was a modified ASQ-10 fluxgate system. This report covers the Greensboro, Winston-Salem, and Johnson City NTMS 1:250,000 scale quadrangles. The Knoxville and Charlotte NTMS 1:250,000 scale quadrangles are covered in a separate report. The radiometric data were normalized to 400 feet terrain clearance, and are presented in the form of computer listings on microfiche and as stacked profile plots. Profile plots are contained in Volume II of this report. A geologic interpretation of the radiometric and magnetic data is included as part of this report

The Paks Nuclear Power Station

International Nuclear Information System (INIS)

Erdosi, N.; Szabo, L.

1978-01-01

As the first stage in the construction of the Paks Nuclear Power Station, two units of 440 MW(e) each will be built. They are operated with two coolant loops each. The reactor units are VVER 440 type water-moderated PWR type heterogeneous power reactors designed in the Soviet Union and manufactured in Czechoslovakia. Each unit operates two Soviet-made K-220-44 steam turbines and Hungarian-made generators of an effective output of 220 MW. The output of the transformer units - also of Hungarian made - is 270 MVA. The radiation protection system of the nuclear power station is described. Protection against system failures is accomplished by specially designed equipment and security measures especially within the primary circuit. Some data on the power station under construction are given. (R.P.)

Work-in-progress report on maintenance good practices for motors in nuclear power generating stations - Part 2

International Nuclear Information System (INIS)

Eckstein, E.R.; Hall, A.R.; Kasper, S.; Smith, P.R.; Subudhi, M.

1988-01-01

Motor maintenance is addressed by a variety of industry standards, utility procedures and manufacture's instructions, as well as by recently published assessments of nuclear and non-nuclear operating experience and motor reliability data. This experience supports the premise that motor failure rates are in large part related to application stress factors such as operating time, environmental factors and vibration. Due to the large number of critical motors installed in a nuclear generating station, additional considerations are necessary to effectively schedule their preventive maintenance activities. Therefore, in this part, a method for prioritizing motor maintenance based on application stresses experienced by the motors is presented

Principles of nuclear power station control

International Nuclear Information System (INIS)

Knowles, J.B.

1975-12-01

This memorandum represents lecture notes first distributed as part of a UKAEA introductory course on Reactor Technology held during November 1975. A nuclear power station is only one element of a dispersed interconnected arrangement of other nuclear and fossil-fired units which together constitute the national 'grid'. Thus the control of any one station must relate to the objectives of the grid network as a whole. A precise control of the supply frequency of the grid is achieved by regulating the output power of individual stations, and it is necessary for each station to be stable when operating in isolation with a variable load. As regards individual stations, several special control problems concerned with individual plant items are discussed, such as: controlled reactivity insertions, temperature reactivity time constants and flow instability. A simplified analysis establishes a fundamental relationship between the stored thermal energy of a boiler unit (a function of mechanical construction) and the flexibility of the heat source (nuclear or fossil-fired) if the station is to cope satisfactorily with demands arising from unscheduled losses of other generating sets or transmission capacity. Two basic control schemes for power station operation are described known as 'coupled' and 'decoupled control'. Each of the control modes has its own merits, which depend on the proposed station operating strategy (base load or load following) and the nature of the heat source. (U.K.)

Stuart Energy's experiences in developing 'Hydrogen Energy Station' infrastructure

International Nuclear Information System (INIS)

Crilly, B.

2004-01-01

'Full text:' With over 50 years experience, Stuart Energy is the global leader in the development, manufacture and integration of multi-use hydrogen infrastructure products that use the Company's proprietary IMET hydrogen generation water electrolysis technology. Stuart Energy offers its customers the power of hydrogen through its integrated Hydrogen Energy Station (HES) that provides clean, secure and distributed hydrogen. The HES can be comprised of five modules: hydrogen generation, compression, storage, fuel dispensing and / or power generation. This paper discusses Stuart Energy's involvement with over 10 stations installed in recent years throughout North America, Asia and Europe while examining the economic and environmental benefits of these systems. (author)

Solar thermal aided power generation

International Nuclear Information System (INIS)

Hu, Eric; Yang, YongPing; Nishimura, Akira; Yilmaz, Ferdi; Kouzani, Abbas

2010-01-01

Fossil fuel based power generation is and will still be the back bone of our world economy, albeit such form of power generation significantly contributes to global CO 2 emissions. Solar energy is a clean, environmental friendly energy source for power generation, however solar photovoltaic electricity generation is not practical for large commercial scales due to its cost and high-tech nature. Solar thermal is another way to use solar energy to generate power. Many attempts to establish solar (solo) thermal power stations have been practiced all over the world. Although there are some advantages in solo solar thermal power systems, the efficiencies and costs of these systems are not so attractive. Alternately by modifying, if possible, the existing coal-fired power stations to generate green sustainable power, a much more efficient means of power generation can be reached. This paper presents the concept of solar aided power generation in conventional coal-fired power stations, i.e., integrating solar (thermal) energy into conventional fossil fuelled power generation cycles (termed as solar aided thermal power). The solar aided power generation (SAPG) concept has technically been derived to use the strong points of the two technologies (traditional regenerative Rankine cycle with relatively higher efficiency and solar heating at relatively low temperature range). The SAPG does not only contribute to increase the efficiencies of the conventional power station and reduce its emission of the greenhouse gases, but also provides a better way to use solar heat to generate the power. This paper presents the advantages of the SAPG at conceptual level.

Alcohol advertising at Boston subway stations: an assessment of exposure by race and socioeconomic status.

Science.gov (United States)

Gentry, Elisabeth; Poirier, Katie; Wilkinson, Tiana; Nhean, Siphannay; Nyborn, Justin; Siegel, Michael

2011-10-01

We investigated the frequency of alcohol ads at all 113 subway and streetcar stations in Boston and the patterns of community exposure stratified by race, socioeconomic status, and age. We assessed the extent of alcohol advertising at each station in May 2009. We measured gross impressions and gross rating points (GRPs) for the entire Greater Boston population and for Boston public school student commuters. We compared the frequency of alcohol advertising between neighborhoods with differing demographics. For the Greater Boston population, alcohol advertising at subway stations generated 109 GRPs on a typical day. For Boston public school students in grades 5 to 12, alcohol advertising at stations generated 134 GRPs. Advertising at stations in low-poverty neighborhoods generated 14.1 GRPs and at stations in high-poverty areas, 63.6 GRPs. Alcohol ads reach the equivalent of every adult in the Greater Boston region and the equivalent of every 5th- to 12th-grade public school student each day. More alcohol ads were displayed in stations in neighborhoods with high poverty rates than in stations in neighborhoods with low poverty rates.

Low earth orbit environmental effects on the space station photovoltaic power generation systems

International Nuclear Information System (INIS)

Nahra, H.K.

1977-01-01

A summary of the Low Earth Orbital Environment, its impact on the photovoltaic power systems of the space station and the solutions implemented to resolve the environmental concerns or issues are described. Low Earth Orbital Environment (LEO) presents several concerns to the photovoltaic power systems of the space station. These concerns include atomic oxygen interaction with the polymeric substrate of the solar arrays, ionized environment effects on the array operating voltage, the effects of the meteoroids and debris impacts and penetration through the different layers of the solar cells and their circuits, and the high energy particle and radiation effects on the overall solar array performance. Potential solutions to some of the degrading environmental interactions that will provide the photovoltaic power system of the space station with the desired life are also summarized

Evaluation of steam generator U-tube integrity during PWR station blackout with secondary system depressurization

International Nuclear Information System (INIS)

Hidaka, Akihide; Asaka, Hideaki; Sugimoto, Jun; Ueno, Shingo; Yoshino, Takehito

1999-12-01

In PWR severe accidents such as station blackout, the integrity of steam generator U-tube would be threatened early at the transient among the pipes of primary system. This is due to the hot leg countercurrent natural circulation (CCNC) flow which delivers the decay heat of the core to the structures of primary system if the core temperature increases after the secondary system depressurization. From a view point of accident mitigation, this steam generator tube rupture (SGTR) is not preferable because it results in the direct release of primary coolant including fission products (FP) to the environment. Recent SCDAP/RELAP5 analyses by USNRC showed that the creep failure of pressurizer surge line which results in release of the coolant into containment would occur earlier than SGTR during the secondary system depressurization. However, the analyses did not consider the decay heat from deposited FP on the steam generator U-tube surface. In order to investigate the effect of decay heat on the steam generator U-tube integrity, the hot leg CCNC flow model used in the USNRC's calculation was, at first, validated through the analysis for JAERI's LSTF experiment. The CCNC model reproduced well the thermohydraulics observed in the LSTF experiment and thus the model is mostly reliable. An analytical study was then performed with SCDAP/RELAP5 for TMLB' sequence of Surry plant with and without secondary system depressurization. The decay heat from deposited FP was calculated by JAERI's FP aerosol behavior analysis code, ART. The ART analysis showed that relatively large amount of FPs may deposit on steam generator U-tube inlet mainly by thermophoresis. The SCDAP/RELAP5 analyses considering the FP decay heat predicted small safety margin for steam generator U-tube integrity during secondary system depressurization. Considering associated uncertainties in the analyses, the potential for SGTR cannot be ignored. Accordingly, this should be considered in the evaluation of merits

IEEE Std 535-1979: IEEE standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1971 and IEE Std 308-1978, can be demonstrated by using the procedures provided in this standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other type batteries are beyond the scope of this standard

Comparative study of the hydrogen generation during short term station blackout (STSBO) in a BWR

International Nuclear Information System (INIS)

Polo-Labarrios, M.A.; Espinosa-Paredes, G.

2015-01-01

Highlights: • Comparative study of generation in a simulated STSBO severe accident. • MELCOR and SCDAP/RELAP5 codes were used to understanding the main phenomena. • Both codes present similar thermal-hydraulic behavior for pressure and boil off. • SCDAP/RELAP5 predicts 15.8% lower hydrogen production than MELCOR. - Abstract: The aim of this work is the comparative study of hydrogen generation and the associated parameters in a simulated severe accident of a short-term station blackout (STSBO) in a typical BWR-5 with Mark-II containment. MELCOR (v.1.8.6) and SCDAP/RELAP5 (Mod.3.4) codes were used to understand the main phenomena in the STSBO event through the results comparison obtained from simulations with these codes. Due that the simulation scope of SCDAP/RELAP5 is limited to failure of the vessel pressure boundary, the comparison was focused on in-vessel severe accident phenomena; with a special interest in the vessel pressure, boil of cooling, core temperature, and hydrogen generation. The results show that at the beginning of the scenario, both codes present similar thermal-hydraulic behavior for pressure and boil off of cooling, but during the relocation, the pressure and boil off, present differences in timing and order of magnitude. Both codes predict in similar time the beginning of melting material drop to the lower head. As far as the hydrogen production rate, SCDAP/RELAP5 predicts 15.8% lower production than MELCOR

Aging management program of the reactor building concrete at Point Lepreau Generating Station

Directory of Open Access Journals (Sweden)

Gendron T.

2011-04-01

Full Text Available In order for New Brunswick Power Nuclear (NBPN to control the risks of degradation of the concrete reactor building at the Point Lepreau Generating Station (PLGS the development of an aging management plan (AMP was initiated. The intention of this plan was to determine the requirements for specific structural components of concrete of the reactor building that require regular inspection and maintenance to ensure the safe and reliable operation of the plant. The document is currently in draft form and presents an integrated methodology for the application of an AMP for the concrete of the reactor building. The current AMP addresses the reactor building structure and various components, such as joint sealant and liners that are integral to the structure. It does not include internal components housed within the structure. This paper provides background information regarding the document developed and the strategy developed to manage potential degradation of the concrete of the reactor building, as well as specific programs and preventive and corrective maintenance activities initiated.

Chemistry technician performance evaluation program Palo Verde Nuclear Generating Station

International Nuclear Information System (INIS)

Shawver, J.M.

1992-01-01

The Arizona Nuclear Power Project (ANPP), a three-reactor site located 50 miles west of Phoenix, Arizona, has developed and implemented a program for evaluating individual chemistry technician analytical performance on a routine basis. About 45 chemistry technicians are employed at the site, 15 at each operating unit. The technicians routinely perform trace level analyses for impurities of concern to PWRs. Each month a set of blind samples is provided by an outside vendor. The blind samples contain 16 parameters which are matrixed to approximate the PWR's primary and secondary cycles. Nine technicians receive the samples, three from each operating unit, and perform the required analyses. Acceptance criteria for successful performance on the blind parameters is based on the values found in the Institute of Nuclear Power Operations (INPO) Document 83-016, Revision 2, August 1989, Chemistry Quality Control Program. The goal of the program is to have each technician demonstrate acceptable performance on each of 16 analytical parameters. On completion of each monthly set, a summary report of all of the analytical results for the sample set is prepared. From the summary report, analytical bias can be detected, technician performance is documented, and overall laboratory performance can be evaluated. The program has been very successful at satisfying the INPO requirement that the analytical performance of each individual technician should be checked on at least a six-month frequency for all important parameters measured. This paper describes the program as implemented at the Palo Verde Nuclear Generating Station and provides a summary report and trend and bias graphs for illustrative purposes

Final Environmental Statement related to the operation of Wolf Creek Generating Station, Unit No. 1. Docket No. STN 50-482, Kansas Gas and Electric Company, et al

International Nuclear Information System (INIS)

1982-06-01

This final environmental statement contains the second assessment of the environmental impact associated with operation of Wolf Creek Generating Station Unit 1 pursuant to the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51, as amended, of the NRC's regulations. This statement examines: the affected environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial- and aquatic-ecological impacts will be small. Air-quality impacts will also be small. However, steam fog from the station's cooling lake has the potential for reducing visibility over nearby roads and bridges. A fog-monitoring program for roads and bridges near the lake has been recommended. Impacts to historic and prehistoric sites will be negligible. Chemical discharges to the Neosho River are expected to have no appreciable impacts on water quality under normal conditions and will be required to meet conditions of the station's NPDES permit. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission line facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk associated with accidental radiation exposure is very low. The net socioeconomic effects of the project will be beneficial. The action called for is the issuance of an operating license for the Wolf Creek Generating Station Unit 1

Costs of producing electricity from nuclear, coal-fired and oil-fired power stations

International Nuclear Information System (INIS)

1980-07-01

The Board publishes generation costs per kW h incurred at recently commissioned power stations so that the costs and performance of nuclear and conventional stations of roughly the same date of construction can be compared. The term 'conventional power station' is used to describe coal-fired and oil-fired steam power stations. The Board has now decided: (A) to supplement the past method of calculating costs at main stations commissioned between 1965 and 1977 by giving the associated figures for interest during construction, for research, and for training; (B) to give similar figures for the contemporary stations Hinkley Point B and the first half of Drax, (C) to provide estimates of generating costs of stations under construction; (D) to set out explicitly the relationship of this method of calculation to that employed in taking investment decisions on future stations. In this way the figures for stations in commission and under construction are arrived at more in line with the general principles of evaluating investment proposals. The present document provides this information. (author)

Assessment of whether upstream passage for Lake Sturgeon is needed at the Pointe du Bois Generating Station (Winnipeg River)

International Nuclear Information System (INIS)

Pratt, T.

2010-01-01

This document reviewed Manitoba Hydro's proposal to modernize the Pointe du Bois Generating Station (GS) on the Winnipeg River, with particular reference to the potential impacts on Lake Sturgeon in Management Unit 5 (MU5) where large numbers of the fish spawn at the base of the falls. The modernization will involve replacing the spillway, dam segments and replacing or repairing the powerhouse. The pros and cons of providing upstream fish passage for Lake Sturgeon and the generating station were outlined. The only spawning area in the MU5 area may be altered considerably due to changes in water flow, depending on the design chosen for modernization. A potential benefit of providing upstream fish passage for Lake Sturgeon would be to increase genetic diversity within the Winnipeg River. Another potential benefit would be to allow Lake Sturgeon, from the relatively dense population below the GS, to move upstream into MU4 where unfilled habitat may be available and Lake Sturgeon abundance is lower. A potential disadvantage of providing fish passage would be the loss of individual Lake Sturgeon from the healthy population in MU5 with no accompanying benefit to MU4. There would be no net gain to MU4 or MU5 if migrating Lake Sturgeon returned to MU5 rather than proceeding upstream. It was concluded that these current gaps in knowledge must be filled in order to fully assess the environmental impacts. 2 figs.

Socio-economic impacts of nuclear generating stations: Oconee case study

International Nuclear Information System (INIS)

Flynn, J.

1982-07-01

This report documents a case study of the socio-economic impacts of the construction and operation of the Oconee nuclear power stations. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of the construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

Socio-economic impacts of nuclear generating stations: Surry case study

International Nuclear Information System (INIS)

Flynn, J.

1982-07-01

This report documents a case study of the socio-economic impacts of the construction and operation of the Surry nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of the construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

New England electric utility takes the lead

Energy Technology Data Exchange (ETDEWEB)

New England Electric System has taken several steps to reduce dependence on foreign oil, save its customers money, and encourage the development of energy resources tailored to meet the region's energy needs. The heart of the plan is a stated objective of reducing annual peaking demand for electrical growth from a projected 3.1% to 1.9%. Other activities initiated are: a solar hot water demonstration project; the NEPCO's burning of a mixture of pulverized coal and residual fuel oil in one of its boilers at Salem Harbor Station in Salem, Massachusetts; purchasing and trading electricity with industrial and private small power producers; and participating in an effort to develop a plan to convert the Brayton Point power plant in Somerset, Massachusetts from oil to coal.

Prospect and problems of gas based power stations of NTPC

International Nuclear Information System (INIS)

Suryanarayana, A.

1993-01-01

The policy of the Government of India concerning utilisation of natural gas resources of the country has undergone changes over the last few years. The government decided in 1985 to allocate natural gas for power generation and in the year 1986 approved the setting up of the first series of three gas based combined cycle power projects of National Thermal Power Corporation (NTPC). The problems of gas power stations of NTPC are discussed. These are high cost of generation, completion of transmission line works to match with the commissioning of gas power stations, high price of natural gas, and fixation of tariff for sale of power from gas based power stations. (N.B.)

Some novel on-power refuelling features of CANDU stations

International Nuclear Information System (INIS)

Erwin, D.; Pendlebury, B.; Watson, J.F.; Welch, A.C.

1976-01-01

Part A of the paper describes the reasons for, and advantages resulting from, the use of flow assisted refuelling in the CANDU type nuclear reactors at the Pickering Generating Station. A separate fuel handling system is used for each reactor unit, as distinct from the system employed at the Bruce Generating station, where the fuel handling system is shared among several units. Part B of the paper describes some of the advantages of the shared concept with particular emphasis on the availability of the fuel handling system. (author)

Inspiring the Next Generation: The International Space Station Education Accomplishments

Science.gov (United States)

Alleyne, Camille W.; Hasbrook, Pete; Knowles, Carolyn; Chicoine, Ruth Ann; Miyagawa, Yayoi; Koyama, Masato; Savage, Nigel; Zell, Martin; Biryukova, Nataliya; Pinchuk, Vladimir;

Severe accident analysis of a steam generator tube rupture accident using MAAP-CANDU to support level 2 PSA for the Point Lepreau Generating Station Refurbishment Project

Energy Technology Data Exchange (ETDEWEB)

Petoukhov, S.M.; Brown, M.J. [Canadian Nuclear Laboratories, Chalk River, ON (Canada)

2015-07-01

A Level 2 Probabilistic Safety Assessment was performed for the Point Lepreau Generating Station. The MAAP-CANDU code was used to simulate the progression of postulated severe core damage accidents and fission product releases. This paper discusses the results for the reference case of the Steam Generator Tube Rupture initiating event. The reference case, dictated by the Level 2 Probabilistic Safety Assessment, was extreme and assumed most safety-related plant systems were not available: all steam generator feedwater; the emergency water supply; the moderator, shield and shutdown cooling systems; and all stages of emergency core cooling. The reference case also did not credit any post Fukushima lessons or any emergency mitigating equipment. The reference simulation predicted severe core damage beginning at 3.7 h, containment failure at 6.4 h, moderator boil off by 8.2 h, and calandria vessel failure at 42 h. A total release of 5.3% of the initial inventory of radioactive isotopes of Cs, Rb and I was predicted by the end of the simulation (139 h). Almost all noble gas fission products were released to the environment, primarily after the containment failure. No hydrogen/carbon monoxide burning was predicted. (author)

Assesment of Carbon Credits for Power Generation Systems at GSM Base Station Site

OpenAIRE

Ani, Vincent Anayochukwu; Ani, Emmanuel Onyeka

2016-01-01

Electricity production is often a source of CO2 emissions, for instance when fossil fuel is combusted in power plants. Therefore the root cause of pollution coming from telecommunication industry is the source of energy (diesel genset) the network operators used in running their Base station sites. Energy consumption of using diesel to power base station by telecom networks is a contributor to global greenhouse gas (GHG) emissions. This paper presents the comparative carbon credits of hybrid ...

Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

Energy Technology Data Exchange (ETDEWEB)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

1976-08-10

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre.

Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

International Nuclear Information System (INIS)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

1976-01-01

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre

Palo Verde Nuclear Generating Station Units 1, 2, and 3: Draft environmental statement (Docket Nos. STN 50-528, 529, and 530)

International Nuclear Information System (INIS)

1975-04-01

The proposed action is the issuance of construction permits to the Arizona Public Service Corporation for the construction of the Palo Verde Nuclear Generating Station, Units 1, 2 and 3. Preparation of the 3880-acre site will involve the clearing of up to 2500 acres of land, 1500 of which will be permanently devoted to station facilities. An additional 1200- to 1300-acre evaporation pond will ultimately be developed during the lifetime of the station. About 2200 site acres, previously devoted to agriculture, will be excluded from this land use (Sec. 4. 1). Soil disturbance during construction of the station, transmission lines, and water conveyance pipeline will tend to promote erosion and increase siltation in local ephemeral water courses. Stringent measures will be taken to minimize these effects (Sec. 4.5). Station, transmission line, and water pipeline construction will kill, remove displace, or otherwise disturb involved flora and fauna, and will eliminate varying amounts of wildlife breeding, nesting, and forage habitat. These will not be important impacts to the population stability and structure of the involved local ecosystems of the Sonoran desert; however, measures will be taken to minimize such effects (Sec. 4.3 and 4.5). Approximately 60 acres of agricultural land will be temporarily affected by construction in transmission corridors. The great majority can be returned to that use upon completion of construction, thus the impact is considered minor. Similarly, most grazing lands affected along these corridors, as well as along the water pipeline corridor, can eventually be returned to that use. New archaeological resources could be discovered along the path of final transmission corridor alignments. The applicant will take measures to locate and protect such resources if they exist. 75 refs., 24 figs., 65 tabs

Intake-to-delivered-energy ratios for central station and distributed electricity generation in California

International Nuclear Information System (INIS)

Heath, Garvin A.; Nazaroff, William W.

2007-01-01

In previous work, we showed that the intake fraction (iF) for nonreactive primary air pollutants was 20 times higher in central tendency for small-scale, urban-sited distributed electricity generation (DG) sources than for large-scale, central station (CS) power plants in California [Heath, G.A., Granvold, P.W., Hoats, A.S., Nazaroff, W.W., 2006. Intake fraction assessment of the air pollutant exposure implications of a shift toward distributed electricity generation. Atmospheric Environment 40, 7164-7177]. The present paper builds on that study, exploring pollutant- and technology-specific aspects of population inhalation exposure from electricity generation. We compare California's existing CS-based system to one that is more reliant on DG units sited in urban areas. We use Gaussian plume modeling and a GIS-based exposure analysis to assess 25 existing CSs and 11 DG sources hypothetically located in the downtowns of California's most populous cities. We consider population intake of three pollutants - PM 2.5 , NO x and formaldehyde - directly emitted by five DG technologies - natural gas (NG)-fired turbines, NG internal combustion engines (ICE), NG microturbines, diesel ICEs, and fuel cells with on-site NG reformers. We also consider intake of these pollutants from existing CS facilities, most of which use large NG turbines, as well as from hypothetical facilities located at these same sites but meeting California's best-available control technology standards. After systematically exploring the sensitivity of iF to pollutant decay rate, the iFs for each of the three pollutants for all DG and CS cases are estimated. To efficiently compare the pollutant- and technology-specific exposure potential on an appropriate common basis, a new metric is introduced and evaluated: the intake-to-delivered-energy ratio (IDER). The IDER expresses the mass of pollutant inhaled by an exposed population owing to emissions from an electricity generation unit per quantity of electric

Intake-to-delivered-energy ratios for central station and distributed electricity generation in California

Science.gov (United States)

Heath, Garvin A.; Nazaroff, William W.

In previous work, we showed that the intake fraction (iF) for nonreactive primary air pollutants was 20 times higher in central tendency for small-scale, urban-sited distributed electricity generation (DG) sources than for large-scale, central station (CS) power plants in California [Heath, G.A., Granvold, P.W., Hoats, A.S., Nazaroff, W.W., 2006. Intake fraction assessment of the air pollutant exposure implications of a shift toward distributed electricity generation. Atmospheric Environment 40, 7164-7177]. The present paper builds on that study, exploring pollutant- and technology-specific aspects of population inhalation exposure from electricity generation. We compare California's existing CS-based system to one that is more reliant on DG units sited in urban areas. We use Gaussian plume modeling and a GIS-based exposure analysis to assess 25 existing CSs and 11 DG sources hypothetically located in the downtowns of California's most populous cities. We consider population intake of three pollutants—PM 2.5, NO x and formaldehyde—directly emitted by five DG technologies—natural gas (NG)-fired turbines, NG internal combustion engines (ICE), NG microturbines, diesel ICEs, and fuel cells with on-site NG reformers. We also consider intake of these pollutants from existing CS facilities, most of which use large NG turbines, as well as from hypothetical facilities located at these same sites but meeting California's best-available control technology standards. After systematically exploring the sensitivity of iF to pollutant decay rate, the iFs for each of the three pollutants for all DG and CS cases are estimated. To efficiently compare the pollutant- and technology-specific exposure potential on an appropriate common basis, a new metric is introduced and evaluated: the intake-to-delivered-energy ratio (IDER). The IDER expresses the mass of pollutant inhaled by an exposed population owing to emissions from an electricity generation unit per quantity of electric

Fulton Generating Station Units 1 and 2 (Docket Nos. 50-463 and 50-464): Final environmental statement

International Nuclear Information System (INIS)

1975-04-01

The proposed action is the issuance of construction permits to the Philadelphia Electric Company for the construction of the Fulton Generating Station, Units 1 and 2, located in Fulton and Drumore Townships, Lancaster County, Pennsylvania. Makeup water for cooling will be withdrawn form Conowingo Pond at a maximum rate of 43,000 gpm. The dissolved solids content of the blowdown water will be increased by a factor of about two. The remainder of the water will be evaporated to the atmosphere by cooling towers. About 10 acres offsite, some 7 acres of which is woodland, will be used for railroad-spur construction. About 0.25 mile of new transmission-line rights-of-way (9 acres) will be needed, although 49 miles of new transmission line, which will require about 3 miles of selective clearing, will be constructed on existing rights-of-way. An unestablished amount of land will be used for access-road construction, but the applicant will use existing roadway corridors where feasible. A small loss of consumer species will result from loss of habitat. Some loss of benthic and pelagic organisms in Conowingo Pond will be caused by intake and discharge construction. The Station's thermal and chemical discharges will meet the State water-quality standards. The duration of additional ground-level fog caused by Station operation is expected to be less than 3 hr/year. (Sect. 5.3.3). No observable effects are expected from salt deposition from cooling-tower drift. (Sect. 5.3.3). Decomposers, primary producers, and zooplankton will be entrained and killed in the cooling-tower system; they, as well as benthic organisms, will be affected by the heated-water discharge. This loss will have little effect on the pond food web. 30 figs., 76 tabs

Annual report of operation management in nuclear power stations, fiscal year 1985

International Nuclear Information System (INIS)

1986-09-01

Twenty years have elapsed since the first practical nuclear reactor in Japan started the operation. In the generated power in fiscal year 1985, that of nuclear power stations for the first time overtook that of thermal power stations, and now the age of nuclear power as the main and oil power as the subordinate has begun. As of the end of fiscal year 1985, there were 32 nuclear power plants in operation, having total output capacity of 24.521 million kW. In fiscal year 1985, nuclear power plants generated about 159 billion kWh, which is about 26 % of electric power supply. As to the capacity factor, 76 % was attained in fiscal year 1985, and this is ranked in the top group of LWR-operating countries in the world. It showed that the Japanese technology of nuclear power generation is at the top level in the world. However, in order to increase nuclear power generation and to accomplish the role of main electric power source hereafter, it is necessary to further increase the reliability and economical efficiency. The list of nuclear power stations in Japan, the state of operation of nuclear power stations, the state of accidents and troubles, the state of regular inspection, the management of radioactive wastes and the radiation exposure of workers in nuclear power stations, the operational management and others are reported. (Kako, I.)

Optimal Site Selection of Wind-Solar Complementary Power Generation Project for a Large-Scale Plug-In Charging Station

Directory of Open Access Journals (Sweden)

Wenjun Chen

2017-10-01

Full Text Available The wind-solar hybrid power generation project combined with electric vehicle charging stations can effectively reduce the impact on the power system caused by the random charging of electric cars, contribute to the in-situ wind-solar complementary system and reduce the harm arising from its output volatility. In this paper, the site selection index system of a landscape complementary power generation project is established by using the statistical methods and statistical analysis in the literature. Subsequently, using the Analytic Network Process to calculate the index weight, a cloud model was used in combination with preference ranking organization method for enrichment evaluations to transform and sort uncertain language information. Finally, using the results of the decision-making for the location of the Shanghai wind-solar complementary project and by carrying out contrast analysis and sensitivity analysis, the superiority and stability of the decision model constructed in this study was demonstrated.

Gravitational biology on the space station

Science.gov (United States)

Keefe, J. R.; Krikorian, A. D.

1983-01-01

The current status of gravitational biology is summarized, future areas of required basic research in earth-based and spaceflight projects are presented, and potential applications of gravitational biology on a space station are demonstrated. Topics covered include vertebrate reproduction, prenatal/postnatal development, a review of plant space experiments, the facilities needed for growing plants, gravimorphogenesis, thigmomorphogenesis, centrifuges, maintaining a vivarium, tissue culture, and artificial human organ generation. It is proposed that space stations carrying out these types of long-term research be called the National Space Research Facility.

The Trencin water power station

International Nuclear Information System (INIS)

2005-01-01

of the impeller wheel 3800 mm. Its water absorption maximum flow is 90 m 3 .s -1 and operational extension of the head between 13.85 and 10,35 m. Maximum power output of the generator is 11.5 MVA, a nominal voltage 10.5 kV and the power factor cos φ = 0.7. The power station has a block arrangement with its output led out through the 22 kV switchgear that is connected to the 110 kV switchgear. The big inner cubicle-type switchgear of 22 kV provides power supplies for many industrial plants in Trencin and for the city of Trencin itself, as well as interconnection with neighbouring water power stations

Spectral analysis of coolant activity from a commercial nuclear generating station

International Nuclear Information System (INIS)

Swann, J.D.; Lewis, B.J.; Ip, M.

2008-01-01

In support of the development of a real-time on-line fuel failure monitoring system for the CANDU reactor, actual gamma spectroscopy data files from the gaseous fission product (GFP) monitoring system were acquired from almost four years of operation at a commercial Nuclear Generating Station (NGS). Several spectral analysis techniques were used to process the data files. Radioisotopic activity from the plant information (PI) system was compared to an in-house C++ code that was used to determine the photopeak area and to a separate analysis with commercial software from Canberra-Aptec. These various techniques provided for a calculation of the coolant activity concentration of the noble gas and iodine species in the primary heat transport system. These data were then used to benchmark the Visual DETECT code, a user friendly software tool which can be used to characterize the defective fuel state based on a coolant activity analysis. Acceptable agreement was found with the spectral techniques when compared to the known defective bundle history at the commercial reactor. A more generalized method of assessing the fission product release data was also considered with the development of a pre-processor to evaluate the radioisotopic release rate from mass balance considerations. The release rate provided a more efficient means to characterize the occurrence of a defect and was consistent with the actual defect situation at the power plant as determined from in-bay examination of discharged fuel bundles. (author)

Potential for use of condenser cooling waters from fossil fuel and nuclear power generating stations for freshwater aquaculture in cold climates

International Nuclear Information System (INIS)

Armstrong, G.C.

1976-01-01

Some limiting factors to the future development of freshwater aquaculture are considered. The most important of these are the need for new and improved technology for the production of better quality products at lower cost and for the promotion and establishment of new markets. The use of relatively small amounts of heated effluent water from power generating stations to optimize water temperatures is one feasible method for increasing growth and lowering the cost of production. (author)

Physical decommissioning of the Shippingport Atomic Power Station

International Nuclear Information System (INIS)

Crimi, F.P.

1988-01-01

The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy (USDOE), and the turbine-generator and balance of plant which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by USDOE from the Duquesne Light Company. The Shippingport Station Decommissioning Project (SSDP) is being managed for the USDOE by the General Electric Company and its integated subcontractor, Morrison Knudsen-Ferguson (MK-F) Company. The objectives of the Shippingport Station Decommissioning Project (SSDP) are to: Demonstrate the safe and cost effective dismantlement of a large scale nuclear power plant; Provide useful data for future decommissioning projects

Iron turbidity removal from the active process water system of the Kaiga Generating Station Unit 1 using an electrochemical filter

International Nuclear Information System (INIS)

Venkateswaran, G.; Gokhale, B.K.

2007-01-01

Iron turbidity is observed in the intermediate cooling circuit of the active process water system (APWS) of Kaiga Generating Station (KGS). Deposition of hydrous/hydrated oxides of iron on the plate type heat exchanger, which is employed to transfer heat from the APWS to the active process cooling water system (APCWS), can in turn result in higher moderator D 2 O temperatures due to reduced heat transfer. Characterization of turbidity showed that the major component is γ-FeOOH. An in-house designed and fabricated electrochemical filter (ECF) containing an alternate array of 33 pairs of cathode and anode graphite felts was successfully tested for the removal of iron turbidity from the APWS of Kaiga Generating Station Unit No. 1 (KGS No. 1). A total volume of 52.5 m 3 water was processed using the filter. At an average inlet turbidity of 5.6 nephelometric turbidity units (NTU), the outlet turbidity observed from the ECF was 1.6 NTU. A maximum flow rate (10 L . min -1 ) and applied potential of 18.0-20.0 V was found to yield an average turbidity-removal efficiency of ∝ 75 %. When the experiment was terminated, a throughput of > 2.08 . 10 5 NTU-liters was realized without any reduction in the removal efficiency. Removal of the internals of the filter showed that only the bottom 11 pairs of felts had brownish deposits, while the remaining felts looked clean and unused. (orig.)

Energy Management for Automatic Monitoring Stations in Arctic Regions

Science.gov (United States)

Pimentel, Demian

Automatic weather monitoring stations deployed in arctic regions are usually installed in hard to reach locations. Most of the time they run unsupervised and they face severe environmental conditions: very low temperatures, ice riming, etc. It is usual practice to use a local energy source to power the equipment. There are three main ways to achieve this: (1) a generator whose fuel has to be transported to the location at regular intervals (2) a battery and (3) an energy harvesting generator that exploits a local energy source. Hybrid systems are very common. Polar nights and long winters are typical of arctic regions. Solar radiation reaching the ground during this season is very low or non-existent, depending on the geographical location. Therefore, solar power generation is not very effective. One straightforward, but expensive and inefficient solution is the use of a large bank of batteries that is recharged during sunny months and discharged during the winter. The main purpose of the monitoring stations is to collect meteorological data at regular intervals; interruptions due to a lack of electrical energy can be prevented with the use of an energy management subsystem. Keeping a balance between incoming and outgoing energy flows, while assuring the continuous operation of the station, is the delicate task of energy management strategies. This doctoral thesis explores alternate power generation solutions and intelligent energy management techniques for equipment deployed in the arctic. For instance, harvesting energy from the wind to complement solar generation is studied. Nevertheless, harvested energy is a scarce resource and needs to be used efficiently. Genetic algorithms, fuzzy logic, and common sense are used to efficiently manage energy flows within a simulated arctic weather station.

Socio-economic impacts of nuclear generating stations: Diablo Canyon case study

International Nuclear Information System (INIS)

Pijawka, K.D.; Yaquinto, G.

1982-07-01

This report documents a case study of the socioeconomic impacts of the construction and operation of the Diablo Canyon nuclear power station. It is part of a major post-licensing study of the socioeconomic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period, 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socioeconomic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

Electric machinery and drives in thermal power stations

International Nuclear Information System (INIS)

1974-01-01

The following subjects were dealt with during the VDE meeting: 1) Requirements made by the electric network on the generators and their excitation equipment, and the influence thereof on their design; 2) requirements made by the power station process on the electric drives and the influence thereof on type and design; 3) requirements made on protective measures from the point of the electric power station machinery. (TK) [de

Improvement of Point Lepreau Generating Station ROP detector characteristics by adjusting gains in compensation amplifiers

Energy Technology Data Exchange (ETDEWEB)

Anghel, V., E-mail: vinicius.anghel@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Basque, M.-J. [Atlantic Nuclear Services Inc., Fredericton, New Brunswick (Canada); Comeau, D. [Point Lepreau Generating Station, Lepreau, New Brunswick (Canada); Sur, B. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Taylor, D. [Point Lepreau Generating Station, Lepreau, New Brunswick (Canada)

2015-06-15

Canadian Pressurized Heavy Water Reactors are protected against reactor overpower by 2 independent shutdown systems: Shut Down System 1 and 2. At Point Lepreau Generating Station, these shutdown systems can be actuated by signals from Platinum-clad Inconel In-Core Flux Detectors measuring the neutron flux. These detectors have a complex dynamic behaviour, characterized by 'prompt' and 'delayed' components with respect to immediate changes in the in-core neutron flux. In aging detectors, it was found that the prompt response decreases. A detector response that actuates the shutdown system effectively has to have a large prompt response and a small delayed response. These required responses may be obtained by adjusting the dynamic compensation amplifiers (compensator) settings. This paper presents the measured results of a compensation adjustment procedure for the in-core platinum-clad Inconel detectors. The compensation is computed from the detector parameters estimated by VS, a fully automated and qualified computer program that analyzes the response of the detectors. (author)

2008 Science Accomplishments Report of the Pacific Northwest Research Station

Science.gov (United States)

Rhonda Mazza

2009-01-01

This report highlights significant research findings and accomplishments by scientists at the Pacific Northwest (PNW) Research Station during fiscal year 2008. The mission of the PNW Research Station is to generate and communicate scientific knowledge that helps people understand and make informed choices about people, natural resources, and the environment. The work...

Safety Evaluation Report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353). Supplement 2

International Nuclear Information System (INIS)

1984-10-01

In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the applicant) for licenses to operate the Limerick Generating Station, Units 1 and 2, located on a site in Montgomery and Chester Counties, Pennsylvania. This supplement addresses further issues that require resolution and closes them out

Optimization of Mangala Hydropower Station, Pakistan, using Optimization Techniques

Directory of Open Access Journals (Sweden)

Zaman Muhammad

2017-01-01

Full Text Available Hydropower generation is one of the key element in the economy of a country. The present study focusses on the optimal electricity generation from the Mangla reservoir in Pakistan. A mathematical model has been developed for the Mangla hydropower station and particle swarm and genetic algorithm optimization techniques were applied at this model for optimal electricity generation. Results revealed that electricity production increases with the application of optimization techniques at the proposed mathematical model. Genetic Algorithm can produce maximum electricity than Particle swarm optimization but the time of execution of particle swarm optimization is much lesser than the Genetic algorithm. Mangla hydropower station can produce up to 59*109 kWh electricity by using the flows optimally than 47*108 kWh production from traditional methods.

The Prospect of Solar Energy in the Development of Power Stations in the State of Kuwait

Directory of Open Access Journals (Sweden)

Mohammad Ramadhan

2013-01-01

Full Text Available Over the years, the production capacity for power generation has not been able to keep pace with the surge in electricity demand in the oil-rich State of Kuwait. To expand its power generation capacity, Kuwait's strategic energy plans focus on constructing gas turbine and fuel oil stations. This paper aimed to evaluate the prospect of photovoltaic solar energy (PV in generating electricity as an alternative to decrease dependency on combined cycle gas turbine (CCGT power stations. It applies the LCOE framework to evaluate the economic feasibility of installing a 100 MW PV and CCGT power stations in Kuwait. The results indicate that under the assumption of 5% interest rate, the estimated LCOE of PV station ($0.19/kWh is unfeasible in comparison to the generation cost of gas turbine station ($0.11/kWh. However, the analysis has emphasized that evaluation of future electricity generation plans must not be limited to the LCOE criteria and should incorporate the following factors: the effect of natural gas supply constraints on the production of gas turbine plants, the environmental concerns of CO2 emissions, the peak load demand, and the domestic energy balance mix. The paper concludes that once these factors are addressed properly, the prospect of PV power stations becomes relatively feasible.

Nuclear power generation modern power station practice

CERN Document Server

1971-01-01

Nuclear Power Generation focuses on the use of nuclear reactors as heat sources for electricity generation. This volume explains how nuclear energy can be harnessed to produce power by discussing the fundamental physical facts and the properties of matter underlying the operation of a reactor. This book is comprised of five chapters and opens with an overview of nuclear physics, first by considering the structure of matter and basic physical concepts such as atomic structure and nuclear reactions. The second chapter deals with the requirements of a reactor as a heat source, along with the diff

Evaluation of SO{sub 2} control technologies for three SCE&G power stations

Energy Technology Data Exchange (ETDEWEB)

Robinson, J.A. Jr. [South Carolina Electric and Gas, Co., Columbia, SC (United States); Wiggins, D.S. [Raytheon Engineers and Constructors, Philadelphia, PA (United States)

1995-06-01

South Carolina Electric and Gas, Co. (SCE&G) commissioned a detailed engineering study evaluating flue gas desulphurization (FGD) equipment for three coal fired generating stations in 1993. Raytheon Engineers and Constructors performed the study evaluating wet and dry FGD processes at three of SCE&G`s generating stations. This paper presents the results and conclusions from the study. The following areas are discussed: (1) Station Descriptions; (2) Process Design Criteria; (3) Study Goals and Methodology; (4) Results from the Economic and Kepner-Tregoe Analysis; and (5) Study Recommendations. The paper concludes with a lessons learned section discussing issues which arose during the study.

Distributed operating system for NASA ground stations

Science.gov (United States)

Doyle, John F.

1987-01-01

NASA ground stations are characterized by ever changing support requirements, so application software is developed and modified on a continuing basis. A distributed operating system was designed to optimize the generation and maintenance of those applications. Unusual features include automatic program generation from detailed design graphs, on-line software modification in the testing phase, and the incorporation of a relational database within a real-time, distributed system.

Socio-economic impacts of nuclear generating stations: Calvert Cliffs case study

International Nuclear Information System (INIS)

Flynn, J.

1982-07-01

This report documents a case study of the socio-economic impacts of the construction and operation of the Calvert Cliffs nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

Socio-economic impacts of nuclear generating stations: Rancho Seco case study

International Nuclear Information System (INIS)

Bergmann, P.A.

1982-07-01

This report documents a case study of the socio-economic impacts of the construction and operation of the Rancho Seco nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of the construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

Socio-economic impacts of nuclear generating stations: Peach Bottom case study

International Nuclear Information System (INIS)

Pijawka, K.D.

1982-07-01

This report documents a case study of the socio-economic impacts of the construction and operation of the Peach Bottom nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of the construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

NASA's Next Generation Space Geodesy Network

Science.gov (United States)

Desai, S. D.; Gross, R. S.; Hilliard, L.; Lemoine, F. G.; Long, J. L.; Ma, C.; McGarry, J. F.; Merkowitz, S. M.; Murphy, D.; Noll, C. E.;

Palo Verde Nuclear Generating Station, Units 1, 2 and 3 (Docket Nos. STN 50-528, STN 50-529 and STN 50-530): Final environmental statement

International Nuclear Information System (INIS)

1975-09-01

The proposed action is the issuance of construction permits to the Arizona public Service Company for the construction of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3. Preparation of the 3800-acre site will involve the clearing of up to 2500 acres of land, 1500 of which will be prominently devoted to station facilities. An additional 1200- to 1300-acre evaporation pond will ultimately be developed during the lifetime of the station. About 2200 site acres, previously devoted to agriculture, will be excluded from this land use. Soil disturbance during construction of the station, transmission lines, and water conveyance pipeline will tend to promote erosion and increase siltation in local ephemeral water courses. Stringent measures will be taken to minimize these effects. The total radiation dose to construction workers is estimated to be 15 man-rem. This dose is a small fraction of the approximately 470 man-rem which will be received by the construction force over the same period from natural background radiation. Station, transmission line, and water pipeline construction will kill, remove, displace, or otherwise disturb involved flora and fauna, and will eliminate varying amounts of wildlife breeding, nesting, and forage habitat. These will not be important permanent impacts to the population stability and structure of the involved local ecosystems of the Sonoran desert; however, measures will be taken to minimize such effects as do result form the proposed action

2014 Science Accomplishments Report of the Pacific Northwest Research Station

Science.gov (United States)

Rhonda Mazza

2015-01-01

Communicating the scientific knowledge generated by the Pacific Northwest Research Station is integral to our mission. The 2014 Science Accomplishments reports highlights the breadth of the station’s research, the relevance of our science findings, and the application of these findings. The photographs throughout the report showcase the region where we work and how...

2013 Science Accomplishments Report of the Pacific Northwest Research Station

Science.gov (United States)

Rhonda Mazza

2014-01-01

Communicating the scientific knowledge generated by the Pacific Northwest Research Station is integral to our mission. The 2013 Science Accomplishments reports highlights the breadth of the station’s research, the relevance of our science findings, and the application of these findings. The photographs throughout the report showcase the region where we work and how...

Short-term hydro generation scheduling of Xiluodu and Xiangjiaba cascade hydropower stations using improved binary-real coded bee colony optimization algorithm

International Nuclear Information System (INIS)

Lu, Peng; Zhou, Jianzhong; Wang, Chao; Qiao, Qi; Mo, Li

2015-01-01

Highlights: • STHGS problem is decomposed into two parallel sub-problems of UC and ELD. • Binary coded BCO is used to solve UC sub-problem with 0–1 discrete variables. • Real coded BCO is used to solve ELD sub-problem with continuous variables. • Some heuristic repairing strategies are designed to handle various constraints. • The STHGS of Xiluodu and Xiangjiaba cascade stations is solved by IB-RBCO. - Abstract: Short-term hydro generation scheduling (STHGS) of cascade hydropower stations is a typical nonlinear mixed integer optimization problem to minimize the total water consumption while simultaneously meeting the grid requirements and other hydraulic and electrical constraints. In this paper, STHGS problem is decomposed into two parallel sub-problems of unit commitment (UC) and economic load dispatch (ELD), and the methodology of improved binary-real coded bee colony optimization (IB-RBCO) algorithm is proposed to solve them. Firstly, the improved binary coded BCO is used to solve the UC sub-problem with 0–1 discrete variables, and the heuristic repairing strategy for unit state constrains is applied to generate the feasible unit commitment schedule. Then, the improved real coded BCO is used to solve the ELD sub-problem with continuous variables, and an effective method is introduced to handle various unit operation constraints. Especially, the new updating strategy of DE/best/2/bin method with dynamic parameter control mechanism is applied to real coded BCO to improve the search ability of IB-RBCO. Finally, to verify the feasibility and effectiveness of the proposed IB-RBCO method, it is applied to solve the STHGS problem of Xiluodu and Xiangjiaba cascaded hydropower stations, and the simulating results are compared with other intelligence algorithms. The simulation results demonstrate that the proposed IB-RBCO method can get higher-quality solutions with less water consumption and shorter calculating time when facing the complex STHGS problem

Influence of the cost development in power station construction and operation on power station planning with special regard to the effects on electricity supply

International Nuclear Information System (INIS)

Krieb, K.H.; Frenzel, P.; Vogel, J.

1974-01-01

A survey on the present structure of thermal power facilities in the FRG is followed by a discussion of the development of power plant costs in the last few years. Also mentioned are the findings of studies of costs as a function of the power station size and the effects of the overall cost increase on the power generation costs of the last few years. Finally, a model conception for the development of power stations is presented which makes predictions about the future size of power stations and their constructional parts. (UA/AK) [de

Training of engineers for nuclear power station operation

International Nuclear Information System (INIS)

Myerscough, P.B.

1980-01-01

The requirements for staffing and training of a nuclear electric utility are described. Current training facilities at the Central Electricity Generating Board are applicable to gas-cooled technology with the possibility of the introduction of a thermal water system and fast reactors in the future. The CEGB training centres provide for the initial training of operational staff, revision training of experienced operational staff, and training of non-operational staff from the stations and supporting departments. Details are given of the content of the training courses which also provide simulation facilities of the basic dynamics of the CEGB stations. Further developments in simulation will include dynamics of the boiler and turbine plants in Magnox stations. The flexibility of the AGR simulations will enable the training exercises to be adjusted to meet changing operating patterns for each AGR station. (U.K.)

Planning of cascade stations on the Maotiao He detailed

Energy Technology Data Exchange (ETDEWEB)

Guan, W

1984-09-20

Details of the hydroelectric power stations on the Maotiao He cascades and examples of how some problems were resolved begin with a description of the river basin survey for topographical features, hydrometeorological conditions, and geological conditions. The river characteristics survey was the basis for planning the cascade power stations and the selection of installed capacity at each station. The review also covers discharge and flood control planning based on rainfall data and the composition of flood areas. The overall development program emphasizes power generation, but also includes irrigation, industrial water supply, and tourism. 2 figures, 1 table.

Target station design for a 1 MW pulsed spallation neutron source

International Nuclear Information System (INIS)

Russell, G.J.; Baker, G.D.; Brewton, R.J.

1993-01-01

Target stations are vital components of the 1 MW, next generation spallation neutron source proposed for LANSCE. By and large, target stations design determines the overall performance of the facility. Many traditional concepts will probably have to be rethought, and many new concepts will have to be put forward to meet the 1 MW challenge. This article gives a brief overview of the proposed neutron spallation source from the target station viewpoint, as well as the general philosophy adopted for the design of the LANSCE-II target stations. Some of the saliant concepts and features envisioned for LANSCE-II are briefly described

Development of the Next Generation Gas Trap for the Space Station Internal Thermal Control System

Science.gov (United States)

Leimkuehler, Thomas O.; Spelbring, Chris; Reeves, Daniel R.; Holt, James M.

2003-01-01

The current dual-membrane gas trap is designed to remove non-condensed gases (NCG) from the Internal Thermal Control System (ITCS) coolant on board the International Space Station (ISS). To date it has successfully served its purpose of preventing depriming, overspeed, and shutdown of the ITCS pump. However, contamination in the ITCS coolant has adversely affected the gas venting rate and lifetime of the gas trap, warranting a development effort for a next-generation gas trap. Design goals are to meet or exceed the current requirements to (1) include greater operating ranges and conditions, (2) eliminate reliance on the current hydrophilic tube fabrication process, and (3) increase operational life and tolerance to particulate and microbial growth fouling. In addition, the next generation gas trap will essentially be a 'dropin" design such that no modifications to the ITCS pump package assembly (PPA) will be required, and the implementation of the new design will not affect changes to the ITCS operational conditions, interfaces, or software. This paper will present the initial membrane module design and development work which has included (1) a trade study among several conceptual designs, (2) performance modeling of a hydrophobic-only design, and (3) small-scale development test data for the hydrophobic-only design. Testing has shown that the hydrophobic-only design is capable of performing even better than the current dual-membrane design for both steady-state gas removal and gas slug removal.

Realisation and instrumentation of high current power station for superconducting cables testing

International Nuclear Information System (INIS)

Regnaud, S.

2000-05-01

This report deals with the designing of a high current station able to test electric properties of superconductors. This test station will be used for testing the superconducting wires of large hadron collider detectors in CERN. The high current test station will have to generate high intensity continuous current in a magnetic field of 0 to 5 tesla and in temperature conditions of 4.2 K. The length of wire samples submitted to the uniform magnetic field is 300 mm and the installation is fitted with equipment able to measure the magnetic field perpendicular to either faces of the wire. The peculiarity of this station is to use a superconducting transformer in order to generate the high current. The first part of this work recalls important notions concerning superconductivity. The second part presents the high current station by describing the superconducting transformer and the sample-holder. We have studied the designing of a transformer able to yield a secondary current whose intensity reaches 100 kA, such intensity generates powerful electromagnetic forces (566 kN/m) in case of defect, so the sample-holder has to be carefully design to bear them. The third part presents the cryogenic component of the station, the instrumentation of the sample-holder and the method used to measure secondary currents. In the last part we present the performance of a prototype transformer, this prototype is able to deliver a 22 kA secondary current for a 160 A primary current, the uncertainty on the measured value of the secondary current is about 3%

Mapping of groundwater potential zones in Salem Chalk Hills, Tamil Nadu, India, using remote sensing and GIS techniques.

Science.gov (United States)

Thilagavathi, N; Subramani, T; Suresh, M; Karunanidhi, D

2015-04-01

This study proposes to introduce the remote sensing and geographic information system (GIS) techniques in mapping the groundwater potential zones. Remote sensing and GIS techniques have been used to map the groundwater potential zones in Salem Chalk Hills, Tamil Nadu, India. Charnockites and fissile hornblende biotite gneiss are the major rock types in this region. Dunites and peridodites are the ultramafic rocks which cut across the foliation planes of the gneisses and are highly weathered. It comprises magnesite and chromite deposits which are excavated by five mining companies by adopting bench mining. The thickness of weathered and fracture zone varies from 2.2 to 50 m in gneissic formation and 5.8 to 55 m in charnockite. At the contacts of gneiss and charnockite, the thickness ranges from 9.0 to 90.8 m favoring good groundwater potential. The mine lease area is underlined by fractured and sheared hornblende biotite gneiss where groundwater potential is good. Water catchment tanks in this area of 5 km radius are small to moderate in size and are only seasonal. They remain dry during summer seasons. As perennial water resources are remote, the domestic and agricultural activities in this region depend mainly upon the groundwater resources. The mines are located in gently slope area, and accumulation of water is not observed except in mine pits even during the monsoon period. Therefore, it is essential to map the groundwater potential zones for proper management of the aquifer system. Satellite imageries were also used to extract lineaments, hydrogeomorphic landforms, drainage patterns, and land use, which are the major controlling factors for the occurrence of groundwater. Various thematic layers pertaining to groundwater existence such as geology, geomorphology, land use/land cover, lineament, lineament density, drainage, drainage density, slope, and soil were generated using GIS tools. By integrating all the above thematic layers based on the ranks and

Managing operations of plug-in hybrid electric vehicle (PHEV) exchange stations for use with a smart grid

International Nuclear Information System (INIS)

Nurre, Sarah G.; Bent, Russell; Pan, Feng; Sharkey, Thomas C.

2014-01-01

We consider a deterministic integer programming model for determining the optimal operations of multiple plug-in hybrid electric vehicle (PHEV) battery exchange stations over time. The operations include the number of batteries to charge, discharge, and exchange at each point in time over a set time horizon. We allow discharging of batteries back to the power grid, through vehicle-to-grid technology. We incorporate the exchange station's dependence on the power network, transportation network, and other exchange stations. The charging and discharging at these exchange stations lead to a greater amount of variability which creates a less predictable and flat power generation curve. We introduce and test three policies to smooth the power generation curve by balancing its load. Further, tests are conducted evaluating these policies while factoring wind energy into the power generation curve. These computational tests use realistic data and analysis of the results suggest general operating procedures for exchange stations and evaluate the effectiveness of these power flattening policies. - Highlights: • Model the operations of plug-in hybrid electric vehicle battery exchange stations. • Determine the optimal and general charging, discharging, and exchange operations. • Conclude that forced customer service levels are unnecessary with proper pricing. • Examine policies to reduce variability in power generation from PHEVs and wind. • Observe that strict constraints on exchange stations best reduce variability

Improvements in operational safety performance of the Magnox power stations

Energy Technology Data Exchange (ETDEWEB)

Marchese, C.J. [BNFL Magnox Generation, Berkeley (United Kingdom)

2000-10-01

In the 43 years since commencement of operation of Calder Hall, the first Magnox power station, there remain eight Magnox stations and 20 reactors still in operation, owned by BNFL Magnox Generation. This paper describes how the operational safety performance of these stations has significantly improved over the last ten years. This has been achieved against a background of commercial competition introduced by privatization and despite the fact that the Magnox base design belongs to the past. Finally, the company's future plans for continued improvements in operational safety performance are discussed. (author)

Lessons learned from the seismic reevaluation of San Onofre Nuclear Generating Station, Unit 1

International Nuclear Information System (INIS)

Russell, M.J.; Shieh, L.C.; Tsai, N.C.; Cheng, T.M.

1987-01-01

A seismic reevaluation program was conducted for the San Onofre Nuclear Generating Station, Unit No. 1 (SONGS 1). SEP was created by the NRC to provide (1) an assessment of the significance of differences between current technical positions on safety issues and those that existed when a particular plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. The Systematic Evaluation Program (SEP) seismic review for SONGS 1 was exacerbated by the results of an evaluation of an existing capable fault near the site during the design review for Units 2 and 3, which resulted in a design ground acceleration of 0.67g. Southern California Edison Company (SCE), the licensee for SONGS 1, realized that a uniform application of existing seismic criteria and methods would not be feasible for the upgrading of SONGS 1 to such a high seismic requirement. Instead, SCE elected to supplement existing seismic criteria and analysis methods by developing criteria and methods closer to the state of the art in seismic evaluation techniques

Navajo Generating Station and Federal Resource Planning; Volume 1: Sectoral, Technical, and Economic Trends

Energy Technology Data Exchange (ETDEWEB)

Hurlbut, David; Haase, Scott; Barrows, Clayton; Bird, Lori; Brinkman, Greg; Cook, Jeff; Day, Megan; Diakov, Victor; Hale, Elaine; Keyser, David; Lopez, Anthony; Mai, Trieu; McLaren, Joyce; Reiter, Emerson; Stoll, Brady; Tian, Tian; Cutler, Harvey; Bain, Dominique; Acker, Tom

2016-11-01

This study for the U.S. Bureau of Reclamation examines conditions in the electricity sector that are likely to affect federal decisions with respect to Navajo Generating Station (NGS), the largest coal-fired power plant operating in the western United States. The federal government owns 24.3% of the 2.25-gigawatt plant, which amounts to 547 megawatts (MW) of capacity. By focusing on the unique public interests that depend on the federal share of NGS, this baseline study can help the federal government develop a road map for meeting all of its goals with respect to water delivery, clean energy, emission reduction, and economic development. There is no recommendation for action in this report. Rather, its aim is to provide a credible, thorough description of baseline conditions that might affect federal decisions regarding NGS. It describes facts and trends embedded in current data, but there are no conclusions about how Reclamation or DOI should respond to the trends. The interdependencies among the many sectoral trends and federal goals are complex, and the aim of this study is to provide a foundation from which options can be tested in a deliberate manner.

Steam generator life cycle management: Ontario Power Generation (OPG) experience

International Nuclear Information System (INIS)

Maruska, C.C.

2002-01-01

A systematic managed process for steam generators has been implemented at Ontario Power Generation (OPG) nuclear stations for the past several years. One of the key requirements of this managed process is to have in place long range Steam Generator Life Cycle Management (SG LCM) plans for each unit. The primary goal of these plans is to maximize the value of the nuclear facility through safe and reliable steam generator operation over the expected life of the units. The SG LCM plans integrate and schedule all steam generator actions such as inspection, operation, maintenance, modifications, repairs, assessments, R and D, performance monitoring and feedback. This paper discusses OPG steam generator life cycle management experience to date, including successes, failures and how lessons learned have been re-applied. The discussion includes relevant examples from each of the operating stations: Pickering B and Darlington. It also includes some of the experience and lessons learned from the activities carried out to refurbish the steam generators at Pickering A after several years in long term lay-up. The paper is structured along the various degradation modes that have been observed to date at these sites, including monitoring and mitigating actions taken and future plans. (author)

The Miksova water power station

International Nuclear Information System (INIS)

2005-01-01

Miksova water power station produced total of about 7,161,342 MWh of electricity in its 40 years of activity. According to its functionality, the Miksova pumped storage station (Miksova II) the upper reservoir of which was built from 1963 to 1966 on the Benovsky stream, was an interesting hydro-energy construction. The lower reservoir was formed by the enlarged discharge channel of the Miksova water power station. This power station was a pilot project, at which pumping reversible turbines and other mechanical-technical equipment for hydro power stations were tested, especially for the future construction of PVE Ruzin and Liptovska Mara. A turbine set with a diagonal reversible turbine and an installed capacity of 2.6 MW, which had an operational capacity of 11.2 m 3 .s -1 in a turbine mode of operation and using a head of 22 to 28 m, was installed in the machine room. It pumped 8.8 m 3 .s -1 of water with a power input of 3.1 MW in a pumping mode of operation. During the period of its operation from 1971 to 1984, pumping hydro power station Miksova II produced a total of 13,042 MWh of electricity in total, but by testing reversible turbines and the simulation of some special hydraulic phenomena, this power station lost its importance as low-efficiency source, stopped working and its technological equipment was demounted. Experiences from its construction and from its few years of operation were later used during the construction of our pumping hydro power stations. Prolonging its operating period should help with the installation of a bigger basin on the inflow, from which a greater amount of water could be used for the generation of electrical power in turbine mode of operation

Antenna unit and radio base station therewith

Science.gov (United States)

Kuwahara, Mikio; Doi, Nobukazu; Suzuki, Toshiro; Ishida, Yuji; Inoue, Takashi; Niida, Sumaru

2007-04-10

Phase and amplitude deviations, which are generated, for example, by cables connecting an array antenna of a CDMA base station and the base station, are calibrated in the baseband. The base station comprises: an antenna apparatus 1; couplers 2; an RF unit 3 that converts a receive signal to a baseband signal, converts a transmit signal to a radio frequency, and performs power control; an A/D converter 4 for converting a receive signal to a digital signal; a receive beam form unit 6 that multiplies the receive signal by semi-fixed weight; a despreader 7 for this signal input; a time-space demodulator 8 for demodulating user data; a despreader 9 for probe signal; a space modulator 14 for user data; a spreader 13 for user signal; a channel combiner 12; a Tx calibrater 11 for controlling calibration of a signal; a D/A converter 10; a unit 16 for calculation of correlation matrix for generating a probe signal used for controlling an Rx calibration system and a TX calibration system; a spreader 17 for probe signal; a power control unit 18; a D/A converter 19; an RF unit 20 for probe signal; an A/D converter 21 for signal from the couplers 2; and a despreader 22.

New water guidelines developed to battle nuclear corrosion

International Nuclear Information System (INIS)

Strauss, S.D.

1983-01-01

Discusses methods of preventing degradation of nuclear steam generators due to a combination of impurities and corrosion products in the secondary system. Explains that tube and support-plate corrosion has been the main concern, manifesting itself primarily in the recirculating units used in PWR systems. Points out that the battle against corrosion is closely linked to control of ionic impurities, alkalinity, oxidants, and sludge-copper and iron corrosion products, primarily-in condensate and feedwater systems. Examines a set of secondary-water-chemistry guidelines developed by the Steam Generator Owners Group (SGOG). Presents diagram showing changes at Salem 1 to arrest corrosion, including condenser retubing, addition of condensate polisher and recirculation loop. Table indicates how preventive measures at Salem 1, affected secondary-water chemistry

Darlington steam generator life assurance program

International Nuclear Information System (INIS)

Jelinski, E.; Dymarski, M.; Maruska, C.; Cartar, E.

1995-01-01

The Darlington Nuclear Generating Station belonging to Ontario Hydro is one of the most modern and advanced nuclear generating stations in the world. Four reactor units each generate 881 net MW, enough to provide power to a major city, and representing approximately 20% of the Ontario grid. The nuclear generating capacity in Ontario represents approximately 60% of the grid. In order to look after this major asset, many proactive preventative and predictive maintenance programs are being put in place. The steam generators are a major component in any power plant. World wide experience shows that nuclear steam generators require specialized attention to ensure reliable operation over the station life. This paper describes the Darlington steam generator life assurance program in terms of degradation identification, monitoring and management. The requirements for chemistry control, surveillance of process parameters, surveillance of inspection parameters, and the integration of preventative and predictive maintenance programs such as water lancing, chemical cleaning, RIHT monitoring, and other diagnostics to enhance our understanding of life management issues are identified and discussed. We conclude that we have advanced proactive activities to avoid and to minimize many of the problems affecting other steam generators. An effective steam generator maintenance program must expand the knowledge horizon to understand life limiting processes and to analyze and synthesize observations with theory. (author)

Extension of life of nuclear power stations

International Nuclear Information System (INIS)

Takahashi, Hideaki

1991-01-01

At the time of designing nuclear power stations, as their service life, generally 40 years are taken, and the basic design specifications of machinery and equipment are determined. In USA where atomic energy has been developed, the new construction of nuclear power stations is cased for a while, however, if this situation continues as it is, since old power stations reach the service life of 40 years and are retired in near future, it is feared that the circumstance of the total amount of power generation becoming short will occur. As one of the countermeasures to this, the research on the extension of life of nuclear power stations has been carried out in many fields in USA, and it is expected that the application for extending the life for the power stations constructed in the initial period of development is submitted in 1991. The researches that have been carried out for solving the technical problems in this extension of life and the situation in Japan are reported. The NEC of USA decided that the operation period of nuclear power stations in USA, which is considered to be 40 years so far, can be extended up to the limit of 20 years. The background and circumstances of this problem in USA, Nuclear Plant Aging Research Program, Plant Life Extension Program and so on are reported. (K.I.)

Sociological impacts of nuclear generating stations - summary report on the NRC post-licensing studies. Final report 1 Oct 78-4 Jan 82

International Nuclear Information System (INIS)

Chalmers, J.; Pijawka, D.; Branch, K.; Bergmann, P.; Flynn, J.

1982-07-01

The Post-Licensing Studies had four objectives. The first was to identify the socioeconomic effects resulting from the construction and operation of each of twelve nuclear power stations. The socioeconomic variables examined included: economic, demographic, housing, government, public response, and social organization characteristics. The second objective was to determine the way in which the identified effects were evaluated by study area groups. The third objective was to identify the determinants of the project-related effects. This task required knowledge of what combination of site, project, or other determinants was responsible for the project-related effects and for the evaluation of the effects. The fourth objective was to make recommendations with respect to assessment methodologies that could best be used to project the socioeconomic effects of the construction and operation of proposed nuclear generating stations. The objectives of the Post-Licensing Studies are met by the twelve individual case studies and by the Summary Report. The case studies identified the nuclear power stations and describe the evaluation of the effects by area residents. The Summary Report describes the collective findings of the individual case studies, compares the findings across sites to identify possible determinants of the effects, and examines the implication of the findings for future siting decisions and for the methodology most appropriate for projective assessments

Seismic structural fragility investigation for the San Onofre Nuclear Generating Station, Unit 1 (Project I); SONGS-1 AFWS Project

International Nuclear Information System (INIS)

Wesley, D.A.; Hashimoto, P.S.

1982-04-01

An evaluation of the seismic capacities of several of the San Onofre Nuclear Generating Station, Unit 1 (SONGS-1) structures was conducted to determine input to the overall probabilistic methodology developed by Lawrence Livermore National Laboratory. Seismic structural fragilities to be used as input consist of median seismic capacities and their variabilities due to randomness and uncertainty. Potential failure modes were identified for each of the SONGS-1 structures included in this study by establishing the seismic load-paths and comparing expected load distributions to available capacities for the elements of each load-path. Particular attention was given to possible weak links and details. The more likely failure modes were screened for more detailed investigation

Socioeconomic impacts of nuclear generating stations: Arkansas Nuclear One station case study. Technical report 1 Oct 78-4 Jan 82

International Nuclear Information System (INIS)

Pijawka, K.D.

1982-07-01

The report documents a case study of the socioeconomic impacts of the construction and operation of the Arkansas Nuclear One nuclear power station. It is part of a major post-licensing study of the socioeconomic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period, 1980-81. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socioeconomic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

HECO annually conducts and reports results of a biological monitoring program for waters receiving effluent from the Kahe Generating Station, O'ahu, Hawai'i from 1977 to 1996 (NODC Accession 9900012)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The volume of sand and silt entrained and circulated by operation of the Kahe Generating Station is an environmental parameter of considerable geological and...

Modeling Woody Biomass Procurement for Bioenergy Production at the Atikokan Generating Station in Northwestern Ontario, Canada

Directory of Open Access Journals (Sweden)

Thakur Upadhyay

2012-12-01

Full Text Available Efficient procurement and utilization of woody biomass for bioenergy production requires a good understanding of biomass supply chains. In this paper, a dynamic optimization model has been developed and applied to estimate monthly supply and procurement costs of woody biomass required for the Atikokan Generating Station (AGS in northwestern Ontario, based on its monthly electricity production schedule. The decision variables in the model are monthly harvest levels of two types of woody biomass, forest harvest residues and unutilized biomass, from 19,315 forest depletion cells (each 1 km2 for a one year planning horizon. Sixteen scenarios are tested to examine the sensitivity of the cost minimization model to changing economic and technological parameters. Reduction in moisture content and improvement of conversion efficiency showed relatively higher reductions in monthly and total costs of woody biomass feedstock for the AGS. The results of this study help in understanding and designing decision support systems for optimal biomass supply chains under dynamic operational frameworks.

Reliable, fault tolerant control systems for nuclear generating stations

International Nuclear Information System (INIS)

McNeil, T.O.; Olmstead, R.A.; Schafer, S.

1990-01-01

Two operational features of CANDU Nuclear Power Stations provide for high plant availability. First, the plant re-fuels on-line, thereby eliminating the need for periodic and lengthy refuelling 'outages'. Second, the all plants are controlled by real-time computer systems. Later plants are also protected using real-time computer systems. In the past twenty years, the control systems now operating in 21 plants have achieved an availability of 99.8%, making significant contributions to high CANDU plant capacity factors. This paper describes some of the features that ensure the high degree of system fault tolerance and hence high plant availability. The emphasis will be placed on the fault tolerant features of the computer systems included in the latest reactor design - the CANDU 3 (450MWe). (author)

Scheduled Operation of PV Power Station Considering Solar Radiation Forecast Error

Science.gov (United States)

Takayama, Satoshi; Hara, Ryoichi; Kita, Hiroyuki; Ito, Takamitsu; Ueda, Yoshinobu; Saito, Yutaka; Takitani, Katsuyuki; Yamaguchi, Koji

Massive penetration of photovoltaic generation (PV) power stations may cause some serious impacts on a power system operation due to their volatile and unpredictable output. Growth of uncertainty may require larger operating reserve capacity and regulating capacity. Therefore, in order to utilize a PV power station as an alternative for an existing power plant, improvement in controllability and adjustability of station output become very important factor. Purpose of this paper is to develop the scheduled operation technique using a battery system (NAS battery) and the meteorological forecast. The performance of scheduled operation strongly depends on the accuracy of solar radiation forecast. However, the solar radiation forecast contains error. This paper proposes scheduling method and rescheduling method considering the trend of forecast error. More specifically, the forecast error scenario is modeled by means of the clustering analysis of the past actual forecast error. Validity and effectiveness of the proposed method is ascertained through computational simulations using the actual PV generation data monitored at the Wakkanai PV power station and solar radiation forecast data provided by the Japan Weather Association.

Darlington Station outage - a maintenance perspective

International Nuclear Information System (INIS)

Plourde, J.; Marczak, J.; Stone, M.; Myers, R.; Sutton, K.

1997-01-01

Ontario Hydro's Darlington Nuclear Generating Station (4x881MW(e)net) has carried out its first station outage since full commercial operation. The outage presented challenges to the organization in terms of outage planning, support, management, and safe execution within the constraints of schedule, budget and resources. This paper will focus on the success of the outage maintenance program, identifying the major work programs - a vacuum structure and containment outage, an emergency service water system outage, an emergency coolant injection system outage, intake channel inspections, low pressure service water inspections, and significant outage maintenance work on each of the four reactor units. Planning for the outage was initiated early in anticipation of this important milestone in the station's life. Detailed safety reviews - nuclear, radiation, and conventional - were conducted in support of the planned maintenance program. System lineup and work protection were provided by the Station Operator work group. Work protection permitry was initiated well in advance of the outage. Station maintenance staff resources were bolstered in support of the outage to ensure program execution could be maintained within the schedule. Training programs were in place to ensure that expectations were clear and that high standards would be maintained. Materials management issues in support of maintenance activities were given high priority to ensure no delays to the planned work. Station management review and monitoring in preparation for and during the outage ensured that staff priorities remained focused. Lessons learned from the outage execution are being formalized in maintenance procedures and outage management procedures, and shared with the nuclear community. (author)

Monitoring and managing component fatigue at Point Lepreau Generating Station

International Nuclear Information System (INIS)

Stevens, G.L.; Yetisir, M.; Scovil, A.; Slade, J.

2008-01-01

Many CANDU plants are now approaching the end of their design lives and are being considered for extended operation beyond their design life. The Canadian Nuclear Safety Commission (CNSC) has asked utilities to address component fatigue issues in plant life extension (PLEX) applications. In particular, environmental effects on fatigue was identified as an issue that needs to be addressed, similar to being addressed for license renewal for U.S. nuclear power plants. To address CNSC concerns, the CANDU Owners Group (COG) has initiated a program to help utilities develop component fatigue management programs for PLEX operation. A summary of a pilot study that was conducted at the Point Lepreau Generating Station (PLGS) is provided below: A plant-specific Recommendation Study provided a comprehensive review of the existing plant-specific systems, cycle counting procedures, and other fatigue-related requirements, and made some general recommendations on how best to implement a fatigue management system for PLEX. The plant-specific study determined that only 10 to 15% of the design transients have been used after 25 effective full power years (EFPY) of operation. Hence, a significant amount of original design margin for fatigue usage margin remains available for PLEX operation. Environmental fatigue considerations in heavy water (D 2 O) were included in the plant-specific assessment. Only warm-up transients were assessed to have dissolved oxygen concentrations that can result in a significant environmental effect for the ferritic steels used in the CANDU primary systems. Due to the low accumulation of transients and the absence of known thermal stratification mechanisms, thermal fatigue is not as significant an issue in CANDU plants as in pressurized water reactor (PWR) and boiling water reactor (BWR) plants. The needs for implementing a comprehensive Fatigue Management Program for PLGS to satisfy PLEX requirements were defined, and specific direction and strategy for

System of wireless base stations employing shadow prices for power load balancing

NARCIS (Netherlands)

2011-01-01

In one aspect, a system is provided. In one embodiment, the system includes a plurality of wireless base stations that are located in a contiguous spatial coverage region of a cellular communication system. Each wireless base station that is configured to generate a coverage pilot beam to enable

Advances in commercial heavy water reactor power stations

International Nuclear Information System (INIS)

Brooks, G.L.

1987-01-01

Generating stations employing heavy water reactors have now firmly established an enviable record for reliable, economic electricity generation. Their designers recognize, however, that further improvements are both possible and necessary to ensure that this reactor type remains attractively competitive with alternative nuclear power systems and with fossil-fuelled generation plants. This paper outlines planned development thrusts in a number of important areas, viz., capital cost reduction, advanced fuel cycles, safety, capacity factor, life extension, load following, operator aida, and personnel radiation exposure. (author)

Demonstration of containment purge and vent valve operability for the Hope Creek Generating Station, Unit 1 (Docket No. 50-354)

International Nuclear Information System (INIS)

Kido, C.

1985-05-01

The containment purge and vent valve qualification program for the Hope Creek Generating Station has been reviewed by the NRC Licensing Support Section. The review indicates that the licensee has demonstrated the dependability of containment isolation against the buildup of containment pressure due to a LOCA/DBA with the restrictions that during operating conditions 1, 2, and 3 all purge and vent valves will be sealed closed and under administrative control, and during power ascension and descension conditions the 26 in. inboard valve (1-GS-HV-4952) will be used in series with the 2 in. bypass valve (1-GS-HV-4951) to control the release of containment pressure

Alternative methodology for assessing part-through-wall cracks in carbon steel bends removed from Point Lepreau Generating Station

Energy Technology Data Exchange (ETDEWEB)

Duan Xinjian, E-mail: duanx@aecl.c [Senior Engineer, Reactor Engineering Department, Atomic Energy of Canada Ltd., Mississauga, ON (Canada); Kozluk, Michael J., E-mail: kozlukm@aecl.c [Independent Consultant, Oakville, ON (Canada); Gendron, Tracy [Manager-HTS Materials Integrity, Atomic Energy of Canada Ltd., Chalk River, ON (Canada); Slade, John [Senior Technical Advisor, Point Lepreau Generating Station, Lepreau, NB (Canada)

2011-03-15

In 2008 April Point Lepreau Generating Station entered an extended refurbishment outage that will involve the replacement of key reactor components (fuel channels and connecting feeder pipes). Prior to the refurbishment outage, New Brunswick Power Nuclear had been successfully managing intergranular, axial cracking of carbon steel feeder piping, that were also experiencing thinning, in the Point Lepreau Generating Station, primarily by an aggressive program of inspection, repair and testing of ex-service material. For the previous three maintenance outages, a probabilistic safety evaluation (PSE) had been used to demonstrate that annual inspection of the highest risk locations maintains the nuclear safety risk from cracking at an acceptably low level. The PSE makes use of the Failure Assessment Diagram (FAD) model to predict the failure of part-through-wall cracks. Burst-pressure testing of two ex-service feeder pipe sections with part-through-wall cracks showed that this FAD model significantly under predicts the failure pressure measured in the component tests. Use of this FAD model introduces undesirable conservatism into PSE assessments that are used to optimize feeder piping inspection and maintenance plans. This paper describes an alternative finite element approach, which could be used to provide more representative structural models for use in PSE assessments. This alternative approach employs the elasto-plastic large strain finite element formulation; uses representative material properties; considers the spatial microstructural distribution; accounts for the effect of work hardening rate; models all deformation processes, i.e., uniform deformation, localized necking, and failure imitation and propagation. Excellent pre-test prediction was shown for the burst-pressure test performed in 2006. Although cold-worked feeder bends have reduced fracture toughness compared to the parent straight pipe, post-test metallurgical examinations showed that failure at the

Performance diagnostic system for emergency diesel generators

International Nuclear Information System (INIS)

Logan, K.P.

1991-01-01

Diesel generators are commonly used for emergency backup power at nuclear stations. Emergency diesel generators (EDGs) are subject to both start-up and operating failures, due to infrequent and fast-start use. EDG reliability can be critical to plant safety, particularly when station blackout occurs. This paper describes an expert diagnostic system designed to consistently evaluate the operating performance of diesel generators. The prototype system is comprised of a suite of sensor monitoring, cylinder combustion analyzing, and diagnostic workstation computers. On-demand assessments of generator and auxiliary equipment performance are provided along with color trend displays comparing measured performance to reference-normal conditions

Space Station tethered elevator system

Science.gov (United States)

Haddock, Michael H.; Anderson, Loren A.; Hosterman, K.; Decresie, E.; Miranda, P.; Hamilton, R.

1989-01-01

The optimized conceptual engineering design of a space station tethered elevator is presented. The tethered elevator is an unmanned, mobile structure which operates on a ten-kilometer tether spanning the distance between Space Station Freedom and a platform. Its capabilities include providing access to residual gravity levels, remote servicing, and transportation to any point along a tether. The report discusses the potential uses, parameters, and evolution of the spacecraft design. Emphasis is placed on the elevator's structural configuration and three major subsystem designs. First, the design of elevator robotics used to aid in elevator operations and tethered experimentation is presented. Second, the design of drive mechanisms used to propel the vehicle is discussed. Third, the design of an onboard self-sufficient power generation and transmission system is addressed.

Managing nuclear power stations for success

International Nuclear Information System (INIS)

Smith, G.

2006-01-01

Ontario Power Generation's (OPG) top operational priority is to manage its nuclear assets to ensure they operate as safely, efficiently and cost effectively as possible. In meeting these objectives, the company is focused on continuously improving its nuclear performance and benchmarking that performance against the best in North America. This presentation explores how OPG is improving its nuclear performance and the steps it is taking to sustain performance success going forward. Topics to be discussed include the measures OPG is taking to enhance human performance and station reliability as well as the company's preparations to determine if a business case exists for extending the lives of the Pickering B and eventually the Darlington nuclear stations. (author)

Forecasting Canadian nuclear power station construction costs

International Nuclear Information System (INIS)

Keng, C.W.K.

1985-01-01

Because of the huge volume of capital required to construct a modern electric power generating station, investment decisions have to be made with as complete an understanding of the consequences of the decision as possible. This understanding must be provided by the evaluation of future situations. A key consideration in an evaluation is the financial component. This paper attempts to use an econometric method to forecast the construction costs escalation of a standard Canadian nuclear generating station (NGS). A brief review of the history of Canadian nuclear electric power is provided. The major components of the construction costs of a Canadian NGS are studied and summarized. A database is built and indexes are prepared. Based on these indexes, an econometric forecasting model is constructed using an apparently new econometric methodology of forecasting modelling. Forecasts for a period of 40 years are generated and applications (such as alternative scenario forecasts and range forecasts) to uncertainty assessment and/or decision-making are demonstrated. The indexes, the model, and the forecasts and their applications, to the best of the author's knowledge, are the first for Canadian NGS constructions. (author)

Environmental monitoring report for the Point Lepreau, New Brunswick nuclear generating station 1984

International Nuclear Information System (INIS)

Nelson, R.W.P.; Ellis, K.M.; Smith, J.N.

1986-07-01

The Point Lepreau Environmental Monitoring Program (PLEMP) has been established within the Department of Fisheries and Oceans to assess the environmental impact of radioactive, thermal, and chemical releases from the Point Lepreau, N.B. Nuclear Generating Station (NGS) located on the Bay of Fundy. This report contains the results for the second year of the operational phase of the monitoring program. Emphasis has been placed on those areas where effects from the NGS operation were expected to be observed. Further studies were carried out on the characterization of the thermal plume during several pre-arranged tritium releases. Attention was given to tritium levels at the outfall, in the atmosphere and in biological samples. An initial attempt was made to relate the distribution of tritium in the Point Lepreau area in various phases to local meteorological conditions. Radionuclide levels in lichen, including, for the first time, aerial lichen on a regular basis, an efficient accumulator of atmospheric particulates were monitored. In addition, radionuclide measurements were made on samples collected during the pre-operational phase from the major environmental reservoirs and these radioactivity levels were compared to previous measurements to assess the impact of the operation of the NGS. The purpose of this program is to provide government with a comprehensive scientific basis upon which to assess the environmental implications of the operation of nuclear reactors in coastal regions

Geospatial tool-based morphometric analysis using SRTM data in Sarabanga Watershed, Cauvery River, Salem district, Tamil Nadu, India

Science.gov (United States)

Arulbalaji, P.; Gurugnanam, B.

2017-11-01

A morphometric analysis of Sarabanga watershed in Salem district has been chosen for the present study. Geospatial tools, such as remote sensing and GIS, are utilized for the extraction of river basin and its drainage networks. The Shuttle Radar Topographic Mission (SRTM-30 m resolution) data have been used for morphometric analysis and evaluating various morphometric parameters. The morphometric parameters of Sarabanga watershed have been analyzed and evaluated by pioneer methods, such as Horton and Strahler. The dendritic type of drainage pattern is draining the Sarabanga watershed, which indicates that lithology and gentle slope category is controlling the study area. The Sarabanga watershed is covered an area of 1208 km2. The slope of the watershed is various from 10 to 40% and which is controlled by lithology of the watershed. The bifurcation ratio ranges from 3 to 4.66 indicating the influence of geological structure and suffered more structural disturbances. The form factor indicates elongated shape of the study area. The total stream length and area of watershed indicate that mean annual rainfall runoff is relatively moderate. The basin relief expressed that watershed has relatively high denudation rates. The drainage density of the watershed is low indicating that infiltration is more dominant. The ruggedness number shows the peak discharges that are likely to be relatively higher. The present study is very useful to plan the watershed management.

Relationship between IEEE Std. 7-4.3.2-1993 and ASME NQA-1, parts I and II revisions and the impact on nuclear power generating stations

International Nuclear Information System (INIS)

Blauw, R.J.

1996-01-01

Clear understanding of software related design control requirements is key to growth in the use of computers in nuclear power generating stations. Inconsistent terminology within the nuclear and software standards arena has impacted the ability of both nuclear station system engineers (i.e., the domain expert) to clearly communicate with the software/computer hardware experts. In order for computer development to occur both groups need to have a common terminology basis. Without this commonality, inappropriate application of requirements could result. This paper will present a overview of ongoing efforts within the Institute of Electrical and Electronics Engineers Nuclear Power Engineering Committee (IEEE NPEC) and the American Society of Mechanical Engineers Nuclear Quality Assurance (ASME NQA) Committee to develop this commonality

The Burrard utilization study report: Review and analysis of the future role of Burrard Thermal Generating Station

International Nuclear Information System (INIS)

1993-01-01

The Burrard Thermal Generating Station is located at Port Moody, British Columbia, and burns natural gas to supply steam to six turbine units for generating up to 912 MW of electricity. The Burrard plant accounts for ca 8.7% of the provincial generating capability. Burrard is expected to continue to fill a vital role as a supplier of displaceable firm energy to the British Columbia Hydro system. In parallel with a renewed focus on Burrard from a system planning perspective, there have also been concerns about air pollution from the plant in the context of its possible effect on the region's air quality. To address this and other issues surrounding Burrard's future, B.C. Hydro established a project team to conduct a utilization study. The team's work focused on the role of Burrard in providing a reliable and profitable role in electricity generation, the options for dealing with the air quality issue, and the implications of choosing one option over another. The team examined a wide range of issues including the remaining useful productive life of the plant, air quality, emissions reduction technologies, long-term gas prices and availability, and seismic stability of the plant. Key findings and recommendations of the study team are reviewed. A financial analysis showed that operating the plant in the displaceable firm energy mode is clearly superior to shutting the plant down and $100 million superior to operation in the full baseload mode. Selective catalytic reduction technology applied to at least the first four of the plant units is the favored option for ensuring better air quality. The value of Burrard would be increased further if its availability factor could be increased to 85%. 7 figs., 3 tabs

An aerial radiological survey of the South Texas Project Electric Generating Station and surrounding area, Bay City, Texas

International Nuclear Information System (INIS)

Thompson, J.M.

1988-12-01

An aerial radiological survey was conducted over the South Texas Project Electric Generating Station (STPEGS) near Bay City, Texas, during the period 25 March to 4 April 1988. The purpose of the 259-square-kilometer (100-square-mile) survey was to document the terrestrial gamma environment of the plant and surrounding area. An exposure rate contour map at 1 meter above ground level (AGL) was constructed from the gamma data and overlaid on an aerial photograph and map of the area. Exposure rates were observed up to 10μR/h over land. No areas of enhanced exposure rates were observed. Ground-based exposure rate measurements and soil samples were obtained to support the aerial data. Oblique aerial photographs of the plant were also acquired during the survey. 9 refs., 4 figs., 1 tab

Centrifugal Compressor Unit-based Heat Energy Recovery at Compressor Stations

Directory of Open Access Journals (Sweden)

V. S. Shadrin

2016-01-01

Full Text Available About 95% of the electricity consumed by air compressor stations around the world, is transformed into thermal energy, which is making its considerable contribution to global warming. The present article dwells on the re-use (recovery of energy expended for air compression.The article presents the energy analysis of the process of compressing air from the point of view of compressor drive energy conversion into heat energy. The temperature level of excess heat energy has been estimated in terms of a potential to find the ways of recovery of generated heat. It is shown that the temperature level formed by thermal energy depends on the degree of air compression and the number of stages of the compressor.Analysis of technical characteristics of modern equipment from leading manufacturers, as well as projects of the latest air compressor stations have shown that there are two directions for the recovery of heat energy arising from the air compression: Resolving technological problems of compressor units. The use of the excess heat generation to meet the technology objectives of the enterprise. This article examines the schematic diagrams of compressor units to implement the idea of heat recovery compression to solve technological problems: Heating of the air in the suction line during operation of the compressor station in winter conditions. Using compression heat to regenerate the adsorbent in the dryer of compressed air.The article gives an equity assessment of considered solutions in the total amount of heat energy of compressor station. Presented in the present work, the analysis aims to outline the main vectors of technological solutions that reduce negative impacts of heat generation of compressor stations on the environment and creating the potential for reuse of energy, i.e. its recovery.

Long-term scheduling of large cascade hydropower stations in Jinsha River, China

International Nuclear Information System (INIS)

Wang, Chao; Zhou, Jianzhong; Lu, Peng; Yuan, Liu

2015-01-01

Highlights: • Proposing a Gaussian group selection strategy to overcome premature convergence. • Multi-population ant are developed to enhance the search ability. • Proposing a circulatory solution correction to handle constraints. • Numerical and real hydropower system simulation are used to verify its performance. • Compensation analysis has been done to large hydropower stations in Jinsha River. - Abstract: The Jinsha River is the third longest river in the world. It consists of four large hydropower stations with total installed capacity 42,960 MW lying on the upper stretches of the Yangtze River, which is the longest river in the word. Due to the great potential of large cascade hydropower stations on power generation, long-term scheduling of large cascade hydropower stations (LSLCHS) plays an important role in electrical power system. As more and more concentrations focused on the optimal operation of large cascade hydropower stations, the LSLCHS has been taken into a multi-dimensional, non-convex and non-linear optimization problem due to its complicated hydraulic connection relationships and varieties of complex constraints with considering its power generation, shipping and ecological characteristics. In order to solve this problem, a multi-population ant colony optimization for continuous domain (MACO R ) is proposed in this paper. A Gaussian group selection strategy is applied to overcome premature convergence and ants with different characteristics are employed to enhance search ability, and circulatory solution correction strategy is presented to handle outflow, water level and output constraints. Furthermore, the efficiency and stability of MACO R are verified by its more desirable results in comparison to other latest works in numerical simulation, and it can be a viable alternative for solving those complicated optimal problems. With the applications in hydropower operation, LSLCHS can obtain more power generation benefit than other

Energy Sharing Framework for Microgrid-Powered Cellular Base Stations

KAUST Repository

Farooq, Muhammad Junaid; Ghazzai, Hakim; Kadri, Abdullah; Elsawy, Hesham; Alouini, Mohamed-Slim

2017-01-01

Cellular base stations (BSs) are increasingly becoming equipped with renewable energy generators to reduce operational expenditures and carbon footprint of wireless communications. Moreover, advancements in the traditional electricity grid allow two

Safety evaluation report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352-50-353). Supplement 1

International Nuclear Information System (INIS)

1983-12-01

This report supplements the Safety Evaluation Report (NUREG-0991, August 1983) for the application filed by the Philadelphia Electric Company, as applicant and owner, for licenses to operate the Limerick Generating Station Units 1 and 2 (Docket Nos. 50-352 and 50-353). The facility is located near Pottstown, Pennsylvania. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

Obrigheim nuclear power station. Annual report 1987

International Nuclear Information System (INIS)

Koerner, C.

1988-01-01

The Obrigheim nuclear power station was operated at full load during the year 1987; 7.351 operating hours procuded electrical energy of 2.607 GWh. This is the fifth best annual result during Obrigheim's operating period. Since commissioning in October 1968, 139.310 hours of operation have generated 46.681 GWh (gross) and from test operation in March 1969 until the end of 1987, 138.530 hours of operation have generated 46.569 GWh. This is an availability of power of 81.6% in this period and a time availability of 83.9%. In 1987, the plant was shut down for 1.222 hours for the 18th refueling including testing, inspection and repair work. Apart from refueling, the plant had a good time availability and therefore contributed 5% to the safe, economical and environmentally acceptable electricity supply of the Land Baden-Wuerttemberg. The power station is of great significance to the region, both in terms of power supply and the economy. (orig./HP) [de

Safety-evaluation report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353)

International Nuclear Information System (INIS)

1983-08-01

The Safety Evaluation Report for the application filed by the Philadelphia Electric Company, as applicant and owner, for licenses to operate the Limerick Generating Station Units 1 and 2 (Docket Nos. 50-352 and 50-353), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located near Pottstown, Pennsylvania. Subject to favorable resolution of the items discussed in this report, the NRC staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

Plant habitability assessment for Point Lepreau Generating Station during a severe accident resulting from station blackout conditions

International Nuclear Information System (INIS)

Mullin, D.

2015-01-01

In response to the CNSC Fukushima Action Plan, the CANDU Owners Group (COG) developed a methodology for assessing nuclear power plant habitability under Joint Project 4426 and to determine if any improvement actions are necessary to provide a high degree of assurance that a severe accident can be managed from a human and organizational performance perspective. NB Power has applied the methodology considering a station black-out scenario (representative case), and assessed the effects of non-radiological hazards and radiological hazards in the context of operator dose relative to emergency dose limits. The paper will discuss the overall methodology, findings and recommendations. (author)

Plant habitability assessment for Point Lepreau Generating Station during a severe accident resulting from station blackout conditions

Energy Technology Data Exchange (ETDEWEB)

Mullin, D., E-mail: dmullin@nbpower.com [New Brunswick Power Corporation, Point Lepreau Generating Station, Lepreau, NB (Canada)

2015-07-01

In response to the CNSC Fukushima Action Plan, the CANDU Owners Group (COG) developed a methodology for assessing nuclear power plant habitability under Joint Project 4426 and to determine if any improvement actions are necessary to provide a high degree of assurance that a severe accident can be managed from a human and organizational performance perspective. NB Power has applied the methodology considering a station black-out scenario (representative case), and assessed the effects of non-radiological hazards and radiological hazards in the context of operator dose relative to emergency dose limits. The paper will discuss the overall methodology, findings and recommendations. (author)

Tarapur Atomic Power Station - - an overview of experience

International Nuclear Information System (INIS)

Shah, J.C.

1979-01-01

A broad overview of the experience and performance of the Tarapur Atomic Power Station (TAPS) in its role as the developing world's first foray in commercial atomic power has been attempted. The prime objective was not just generation of power but assimilation of an advanced technology on an economically viable basis in the underdeveloped environment compounded with governmental organisational culture. Scientific and technical advances registered through the TAPS experience in the area of design, operation and maintenance are mentioned. Aspects of station performance, management and even economics are also covered. (auth.)

The local economic and social effects of power station siting: anticipated, demonstrated and perceived

International Nuclear Information System (INIS)

Glasson, J.

1980-01-01

The paper discusses the economic and social effects of power station siting at a local level using material based on the interim research findings from a project commissioned by the Central Electricity Generating Board. The cases for and against power station development are outlined and a review of the actual economic and social effects is presented, drawn from a study of a conventional power station at Drax and a nuclear power station at Sizewell. (U.K.)

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Newell, J.E.

1982-11-01

A brief description is given of the design of the steam generators for the proposed Sizewell B power station. A review of the operational behaviour of earlier models is presented. The problem of degradation of steam generator tubes is considered in some detail. Model F steam generator, which has been incorporated into the Sizewell B reference design, is discussed. Finally the impact of steam generator tube degradation upon radiological safety is discussed. (U.K.)

FY 2000 report on the demonstrative research for photovoltaic power generation system in Thailand. Demonstrative study on photovoltaic power generation grid-connected system

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

In relation to the demonstrative study of the photovoltaic power system that is planned in Libong island, Thailand, the FY 2000 results were reported. In this R and D, construction/demonstrative operation were planned for a photovoltaic power station with a generation output of 100kW, photovoltaic power system in school facilities, and system for transmitting/distributing power to houses by connecting the power station and power system. In this fiscal year, the field survey was conducted together with the alteration from Yao Yai island, for which the demonstrative study was planned at first, to Libong island. The electric equipment was selected which met the requests from Thailand and the results of the field survey, and the basic design of the photovoltaic power generation/transmission/distribution system was completed. Based on this, the design/manufacture of photovoltaic power generation modules, power control equipment, measuring equipment, etc. were made. At the construction site of photovoltaic power station, construction work such as land formation was conducted. Further, Thai engineers who visited Japan did the following: discussions about power system, presence at test/inspection of photovoltaic power generation modules, visits to photovoltaic power stations, wind power stations, etc. (NEDO)

Three Mile Island Nuclear Station steam generator chemical cleaning

International Nuclear Information System (INIS)

Hansen, C.A.

1992-01-01

The Three Mile Island-1 steam generators were chemically cleaned in 1991 by the B and W Nuclear Service Co. (BWNS). This secondary side cleaning was accomplished through application of the EPRI/SGOG (Electric Power Research Institute - Steam Generator Owners Group) chemical cleaning iron removal process, followed by sludge lancing. BWNS also performed on-line corrosion monitoring. Corrosion of key steam generator materials was low, and well within established limits. Liquid waste, subsequently processed by BWNS was less than expected. 7 tabs

Wind turbine power stations

International Nuclear Information System (INIS)

Anon.

1992-11-01

The Countryside Council for Wales (CCW's) policy on wind turbine power stations needs to be read in the context of CCW's document Energy:Policy and perspectives for the Welsh countryside. This identifies four levels of action aimed at reducing emission of gases which contribute towards the risk of global warming and gases which cause acid deposition. These are: the need for investment in energy efficiency; the need for investment in conventional power generation in order to meet the highest environmental standards; the need for investment in renewable energy; and the need to use land use transportation policies and decisions to ensure energy efficiency and energy conservation. CCW views wind turbine power stations, along with other renewable energy systems, within this framework. CCW's policy is to welcome the exploitation of renewable energy sources as an element in a complete and environmentally sensitive energy policy, subject to the Environmental Assessment of individual schemes and monitoring of the long-term impact of the various technologies involved. (Author)

Observations of Earth space by self-powered stations in Antarctica.

Science.gov (United States)

Mende, S B; Rachelson, W; Sterling, R; Frey, H U; Harris, S E; McBride, S; Rosenberg, T J; Detrick, D; Doolittle, J L; Engebretson, M; Inan, U; Labelle, J W; Lanzerotti, L J; Weatherwax, A T

2009-12-01

Coupling of the solar wind to the Earth magnetosphere/ionosphere is primarily through the high latitude regions, and there are distinct advantages in making remote sensing observations of these regions with a network of ground-based observatories over other techniques. The Antarctic continent is ideally situated for such a network, especially for optical studies, because the larger offset between geographic and geomagnetic poles in the south enables optical observations at a larger range of magnetic latitudes during the winter darkness. The greatest challenge for such ground-based observations is the generation of power and heat for a sizable ground station that can accommodate an optical imaging instrument. Under the sponsorship of the National Science Foundation, we have developed suitable automatic observing platforms, the Automatic Geophysical Observatories (AGOs) for a network of six autonomous stations on the Antarctic plateau. Each station housed a suite of science instruments including a dual wavelength intensified all-sky camera that records the auroral activity, an imaging riometer, fluxgate and search-coil magnetometers, and ELF/VLF and LM/MF/HF receivers. Originally these stations were powered by propane fuelled thermoelectric generators with the fuel delivered to the site each Antarctic summer. A by-product of this power generation was a large amount of useful heat, which was applied to maintain the operating temperature of the electronics in the stations. Although a reasonable degree of reliability was achieved with these stations, the high cost of the fuel air lift and some remaining technical issues necessitated the development of a different type of power unit. In the second phase of the project we have developed a power generation system using renewable energy that can operate automatically in the Antarctic winter. The most reliable power system consists of a type of wind turbine using a simple permanent magnet rotor and a new type of power

Socio-economic impacts of nuclear generating stations: D. C. Cook case study

International Nuclear Information System (INIS)

Branch, K.

1982-07-01

This report documents a case study of the socio-economic impacts of the construction and operation of the D. C. Cook nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

Socio-economic impacts of nuclear generating stations: Three Mile Island case study

International Nuclear Information System (INIS)

Flynn, C.

1982-07-01

This report documents a case study of the socio-economic impacts of the construction and operation of the Three Mile Island nuclear power stations. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of the construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

Environmental implications of fossil-fuelled power stations

International Nuclear Information System (INIS)

Robson, A.

1979-01-01

The public health and environmental implications of electricity generation by fossil-fuelled power stations are discussed with respect to pollutant emission and the disposal of waste products. The following conclusions were deduced. The policy of using tall chimney stacks has ensured that acceptable concentrations of potential pollutants are observed in the vicinity of power stations. Large scale carbon dioxide emission may represent a problem in the future due to its effect on the climate. The effects of sulphur dioxide and the oxides of nitrogen need to be kept under review but it is likely that sources other than power stations will be of greater importance in this context. Pulverised fuel ash is a safe and useful by product of power production. Finally the radiation dose to man caused by the release of naturally occurring radioisotopes is negligible compared to the natural background levels. (UK)

Construction work management for nuclear power stations

International Nuclear Information System (INIS)

Yoshikawa, Yuichiro

1982-01-01

Nuclear power generation is positioned as the nucleus of petroleum substitution. In the Kansai Electric Power Co., efforts have been made constantly to operate its nuclear power plants in high stability and safety. At present, Kansai Electric Power Co. is constructing Units 3 and 4 in the Takahama Nuclear Power Station in Fukui Prefecture. Under the application of the management of construction works described here, both the nuclear power plants will start operation in 1985. The activities of Kansai Electric Power Co. in the area of this management are described: an outline of the construction works for nuclear power stations, the management of the construction works in nuclear power stations (the stages of design, manufacturing, installation and test operation, respectively), quality assurance activities for the construction works of nuclear power plants, important points in the construction work management (including the aspects of quality control). (J.P.N.)

Small hydroelectric power stations and their reality

International Nuclear Information System (INIS)

Kamenski, Miroslav

1999-01-01

Construction of a small hydroelectric power station provides additional amounts of electric energy, engages a private capital, revives investment activities and promotes the use of renewable energy sources. Transmission losses are reduced, a voltage of higher quality is achieved and idle power is compensated by the generation of electricity in the small hydroelectric power stations and at the place of consumption. Legislation and technical regulations, however, require a multidisciplinary approach, defining of complex spaces and environmental protection. Unfortunately, complete documents should be prepared for small,hydroelectric plants just as for big ones what is a long procedure and many of those papers are unnecessary or even superfluous. (Author)

Toxicity regulation of radioactive liquid waste effluent from CANDU stations - lessons from Ontario's MISA program

International Nuclear Information System (INIS)

Rodgers, D.W.

2009-01-01

Toxicity testing became an issue for Ontario's CANDU stations, when it was required under Ontario's MISA regulations for the Electricity Generation Sector. In initial tests, radioactive liquid waste (RLW) effluent was intermittently toxic to both rainbow trout and Daphnia. Significant differences in RLW toxicity were apparent among stations and contributing streams. Specific treatment systems were designed for three stations, with the fourth electing to use existing treatment systems. Stations now use a combination of chemical analysis and treatment to regulate RLW toxicity. Studies of Ontario CANDU stations provide a basis for minimizing costs and environmental effects of new nuclear stations. (author)

Decommissioning of nuclear power stations

International Nuclear Information System (INIS)

Gregory, A.R.

1988-01-01

In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

Dynamical Mass Generation.

Science.gov (United States)

Mendel Horwitz, Roberto Ruben

1982-03-01

In the framework of the Glashow-Weinberg-Salem model without elementary scalar particles, we show that masses for fermions and intermediate vector bosons can be generated dynamically. The mechanism is the formation of fermion-antifermion pseudoscalar bound states of zero total four momentum, which form a condensate in the physical vacuum. The force responsible for the binding is the short distance part of the net Coulomb force due to photon and Z exchange. Fermions and bosons acquire masses through their interaction with this condensate. The neutrinos remain massless because their righthanded components have no interactions. Also the charge -1/3 quarks remain massless because the repulsive force from the Z exchange dominates over the Coulomb force. To correct this, we propose two possible modifications to the theory. One is to cut off the Z exchange at very small distances, so that all fermions except the neutrinos acquire masses, which are then, purely electromagnetic in origin. The other is to introduce an additional gauge boson that couples to all quarks with a pure vector coupling. To make this vector boson unobservable at usual energies, at least two new fermions must couple to it. The vector boson squared masses receive additive contributions from all the fermion squared masses. The photon remains massless and the masses of the Z and W('(+OR -)) bosons are shown to be related through the Weinberg angle in the conventional way. Assuming only three families of fermions, we obtain estimates for the top quark mass.

Optimizing the use of operating experience at Ontario Hydro's Bruce Nuclear Generating Station 'A'

Energy Technology Data Exchange (ETDEWEB)

Williams, E L [Operating Experience Reactor Safety, Bruce Nuclear Generating Station ' A' , Ontario Hydro, Tiverton, Ontario (Canada)

1991-04-01

One of the most significant lessons learned from the Three Mile Island event (March 1979), and again with the Chernobyl disaster - (April 1986) was the ongoing requirement to learn from our mistakes and near misses, and those of our fellow utilities around the world: so that as an industry we do not repeat the same mistakes. The very future of our industry will depend on how well each one of us accomplishes this important ask. This paper describes in detail the challenges encountered by one station when incorporating a comprehensive 'Operating Program'. It begins with the Corporate Office's directives to its stations for such a program; and follows up with the details of the actual station implementation of the program, and day to day operating experiences. The paper describes in detail the following Operating Experience programs: - Root Cause Determination process. The Institute of Nuclear Power Operations, Human Performance Enhancement System (HPES) as an integral component of the Root Cause process. Finding solutions for our station for problems identified elsewhere is covered herein; - Significant Event Recommendation Tracking System: - Commitment Tracking System; - Operating Experience (Sharing Lessons Learned) System. The paper will show all the above processes tie closely together and complement each other. The paper discusses the staff required for such processes and their training requirements. It recommends process time lines, reporting mechanisms, and sign off requirements. It will describe the equipment utilized to carry out this work effectively, and with a minimum of staff. One unique feature of the Bruce 'A' system is an 'Effectiveness Follow-Up', usually three to six months after the event recommendations have been completed. By rechecking the finished actions and reviewing them with the personnel involved with the originating event we ensure that the real root causes have been identified and resolved. (author)

Optimizing the use of operating experience at Ontario Hydro's Bruce Nuclear Generating Station 'A'

International Nuclear Information System (INIS)

Williams, E.L.

1991-01-01

One of the most significant lessons learned from the Three Mile Island event (March 1979), and again with the Chernobyl disaster - (April 1986) was the ongoing requirement to learn from our mistakes and near misses, and those of our fellow utilities around the world: so that as an industry we do not repeat the same mistakes. The very future of our industry will depend on how well each one of us accomplishes this important ask. This paper describes in detail the challenges encountered by one station when incorporating a comprehensive 'Operating Program'. It begins with the Corporate Office's directives to its stations for such a program; and follows up with the details of the actual station implementation of the program, and day to day operating experiences. The paper describes in detail the following Operating Experience programs: - Root Cause Determination process. The Institute of Nuclear Power Operations, Human Performance Enhancement System (HPES) as an integral component of the Root Cause process. Finding solutions for our station for problems identified elsewhere is covered herein; - Significant Event Recommendation Tracking System: - Commitment Tracking System; - Operating Experience (Sharing Lessons Learned) System. The paper will show all the above processes tie closely together and complement each other. The paper discusses the staff required for such processes and their training requirements. It recommends process time lines, reporting mechanisms, and sign off requirements. It will describe the equipment utilized to carry out this work effectively, and with a minimum of staff. One unique feature of the Bruce 'A' system is an 'Effectiveness Follow-Up', usually three to six months after the event recommendations have been completed. By rechecking the finished actions and reviewing them with the personnel involved with the originating event we ensure that the real root causes have been identified and resolved. (author)

Electric motorcycle charging station powered by solar energy

Science.gov (United States)

Siriwattanapong, Akarawat; Chantharasenawong, Chawin

2018-01-01

This research proposes a design and verification of an off-grid photovoltaic system (PVS) for electric motorcycle charging station to be located in King’s Mongkut’s University of Technology Thonburi, Bangkok, Thailand. The system is designed to work independently (off-grid) and it must be able to fully charge the batteries of a typical passenger electric motorcycle every evening. A 1,000W Toyotron electric motorcycle is chosen for this study. It carries five units of 12.8V 20Ah batteries in series; hence its maximum energy requirement per day is 1,200Wh. An assessment of solar irradiation data and the Generation Factor in Bangkok, Thailand suggests that the charging system consists of one 500W PV panel, an MPPT charge controller, 48V 150Ah battery, a 1,000W DC to AC inverter and other safety devices such as fuses and breakers. An experiment is conducted to verify the viability of the off-grid PVS charging station by collecting the total daily energy generation data in the raining season and winter. The data suggests that the designed off-grid solar power charging station for electric motorcycle is able to supply sufficient energy for daily charging requirements.

Sizewell 'B' power station public inquiry: CEGB proof of evidence

International Nuclear Information System (INIS)

Wright, J.K.

1982-11-01

A description is given of the CEGB's current assessment of the potential contribution to electricity generation of those methods considered to be the most significant alternatives to conventional power stations or thermal nuclear reactors for generating electricity. The state of development of the technology, the timescale on which it could be developed, its ability to generate electricity reliably and the cost of generating electricity are some of the matters considered. The following topics are covered: potential developments in coal fired generating plant; combined heat and power generation; energy storage; electricity generation from renewable energy sources; fast reactors and fusion. (U.K.)

Discharges to the environment and environmental protection at CEGB power stations

International Nuclear Information System (INIS)

Wright, J.K.

1981-01-01

The subject is discussed under the headings: introduction (scope of paper will cover the principles, methods and results obtained in environmental protection in relation to atmospheric discharges made routinely during power generation); air pollution control; nuclear power stations (type of discharge, annual discharges, environmental monitoring); fossil fuelled power stations; health effects; trace elements; long range transport and acid rain; future coal fired plant; carbon dioxide. (U.K.)

Mobile incineration services at Commonwealth Edison's nuclear stations

International Nuclear Information System (INIS)

Smith, K.R.

1985-01-01

As the costs for low-level waste disposal escalate, and as the January 1, 1986 date draws nearer, utilities throughout the United States are formulating and implementing plans to reduce the volumes of the low-level radioactive waste being generated at their nuclear power stations. Techniques being used to accomplish this goal range from sorting of dry active waste to complete volume reduction systems, like the Aerojet VR Systems being installed at Commonwealth Edison's Byron and Braidwood Stations. In between these extremes are partial solutions to the problem, including compaction, shredding and compaction, super-compaction, resin dewatering, liquid drying, and now, mobile incineration. In June, 1983, Commonwealth Edison Company (CECO) of Chicago, Illinois, contracted Aerojet Energy Conversion Company (AECC) of Sacramento, California, to supply mobile VR services to the Dresden, La Salle, Quad Cities, and Zion Nuclear Stations. Per the contract, AECC is responsible for the design, fabrication, delivery, operation, and maintenance of a Mobile Volume Reduction System (MVRS) capable of processing combustible dry active waste and contaminated oil generated at these Com-Ed facilities. Initial commercial operation of the MVRS is planned for the Dresden Nuclear Power Station in May, 1985. This paper is intended to summarize some of the key elements resulting from the design, fabrication, and testing of the MVRS. In addition, it is intended to identify the tasks a potential user of the MVRS service must complete in order to receive permission from the Nuclear Regulatory Commission to operate the MVRS at their site

WGS 84 Coordinate Validation and Improvement for the NIMA and Air Force GPS Tracking Stations

National Research Council Canada - National Science Library

Cunningham, James

1996-01-01

Using 10 days of Global Positioning System (GPS) pseudorange and carrier phase data collected in 1995 from 31 stations and 24 Block II/IIA satellites, estimates of GPS clocks, orbits, and tracking station coordinates were generated...

Technical descriptions of Hudson River electricity generating stations

International Nuclear Information System (INIS)

Hutchison, J.B.

1988-01-01

Six fossil-fueled and one nuclear electricity generating plants are sited along the Hudson River estuary between kilometers 8 and 228, measured from the river mouth. Their aggregate rated capacity is 5,798 MW of electricity; operating at that capacity they would withdraw cooling water from the river at the rate of 1.5 x 10 to the 9th power cu m/d and reject heat at the rate of 155 x 10 to the 9th power kcal/d. Three of these plants, the fossil-fueled Roseton and Bowline and the nuclear Indian Point facilities; account for 75% of total rated capacity, 62% of maximum water withdrawal, and 79% of potential heat rejection. These three plants and a proposed pumped-storage facility at Cornwall, all sited between km 60 and 106, were the focus of environmental litigation. The Indian Point plant normally operates at 100% generation capacity; the other plants may experience daily operating load changes that vary from approximately 50% to 100% of total generation capacity, depending on system electrical demand or economic considerations. All plants experience periodic unscheduled outages for repairs. 6 refs., 7 figs

IEEE Std 323-1983: IEEE standard for qualifying Class 1E equipment for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard describes the basic requirements for qualifying Class 1E equipment with interfaces that are to be used in nuclear power generating stations. The requirements presented include the principles, procedures, and methods of qualification. These qualification requirements, when met, will confirm the adequacy of the equipment design under normal, abnormal, design basis event, post design basis event, and in-service test conditions for the performance of safety function(s). The purpose of this standard is to identify requirements for the qualification of Class 1E equipment, including those interfaces whose failure could adversely affect the performance of Class 1E equipment and systems. The methods described shall be used for qualifying equipment, extending qualification, and updating qualification if the equipment is modified. Other issued IEEE standards which present qualification methods for specific equipment or components, or both, and those that deal with parts of the qualification program, may be used to supplement this standard, as applicable

Decommissioning situation and research and development for the decommissioning of the commercial nuclear power station in Japan

International Nuclear Information System (INIS)

Yamamoto, Tatsumi.

1996-01-01

There are 48 commercial nuclear power stations in operation in Japan as of January 1, 1995, which supplies about 28% (2.2 x 10 8 MWh) of total annual electricity generation in FY 1992. Accordingly, as the nuclear power contributes so much in electricity generation, there is a growing concern in the public toward the safety on decommissioning nuclear power station. It is gravely important to secure the safety throughout the decommissioning. This paper discusses: the decommissioning situation in Japan; the Japanese national policy for decommissioning of commercial nuclear power stations; R and D for decommissioning of commercial nuclear power stations in Japan; and the present conditions of low-level radioactive wastes disposal in Japan

Predicting steam generator crevice chemistry